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REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size: ] PJ ACCESSION NBR;8408}40161 DOC,DATE: 84/08/09 NOTARIZED: NO FACIL:50 244 Robert Emmet Ginna Nuclear Planti Unit }i Rochester G AUTH BYNAME AUTHOR AFFILIATION KOBERiR,N, Rochester Gas 5 Electric Corp. RECIP,NAMEi, RECIPIENT AFFILIATION MURLEYi T'.E+ Region } i Of f ice of Director ( SUBJECT: Forwards= Rev 0 to "Nuclear Emergency Radiation„Plani" f ncorpor at f ng of f si te 8, onsi te p) ans 8 responding to mods recommended, in I Insp Rept= 50-244/ -25. DISTRIBUTION COD: 45S PI REC VE !LTR ENCL TITLE: OR 'Submi tal Emergency Prep or respondence NOTES: NRR/DL/SEP 1 cy, OL: 09/19/69 05000244 RECIPIENT ID CODE/NAME'RR OR85 BC DICKING 01 INTERNAL: AOM-LFMB- IE/OEPER/IRB }? 'RR/DSI'/RAB RGN} COPIES LTTR ENCL' 1 1 1 1 0 1 } 1 1 1 1 RECIPIENT IO CODE/NAME NRR ORB5 LA IE/DEPER/EPB 06 NRR/3) EB ,04 RGN2/DRSS/EPRPB COP IFS LTTR ENCL 1 0 2 2 1 1 1 1 1 1 ~ EXTERNAL'EMA TECH HAZ NRC POR 0?.'- NTIS 05 NOTES: 1 1 1 } 1 LPDR NSIC 03 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16

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Page 1: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS)

DOCKET ¹05000244

size: ] PJ

ACCESSION NBR;8408}40161 DOC,DATE: 84/08/09 NOTARIZED: NO

FACIL:50 244 Robert Emmet Ginna Nuclear Planti Unit }i Rochester G

AUTH

BYNAME

AUTHOR AFFILIATIONKOBERiR,N, Rochester Gas 5 Electric Corp.

RECIP,NAMEi, RECIPIENT AFFILIATIONMURLEYiT'.E+ Region } i Of f ice of Director

(

SUBJECT: Forwards= Rev 0 to "Nuclear Emergency Radiation„Plani"f ncorpor at f ng of fsi te 8, onsi te p) ans 8 responding to modsrecommended, in I Insp Rept= 50-244/ -25.

DISTRIBUTION COD: 45S PI REC VE !LTR ENCLTITLE: OR 'Submi tal Emergency Prep or respondence

NOTES: NRR/DL/SEP 1 cy,OL: 09/19/69

05000244

RECIPIENTID

CODE/NAME'RR

OR85 BC

DICKING

01

INTERNAL: AOM-LFMB-IE/OEPER/IRB }?

'RR/DSI'/RAB

RGN}

COPIESLTTR ENCL'

1

1 1

1 01 }1 1

1 1

RECIPIENTIO CODE/NAME

NRR ORB5 LA

IE/DEPER/EPB 06NRR/3) EB

,04RGN2/DRSS/EPRPB

COP IFSLTTR ENCL

1 0

2 21 1

1 1

1 1 ~

EXTERNAL'EMA TECH HAZNRC POR 0?.'-

NTIS 05

NOTES:

1 1

1 }1

LPDRNSIC

03 1

1 1

TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16

Page 2: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

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Page 3: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

iQIII>'fiPiZI!IIIII//j~ijKLIII>T

ROCHESTER GAS AND ELECTRIC CORPORATION ~

l>(N%>II > l> ~ '>>

\

5(AT(

89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001

ROGER W, 5(OBERVlCC PRCSIOCNTELECTRIC C> STEAM PI(OOVCTION

TCLCI>1>ONC

ARCA COO( 716 546 2700

August 9, 1984

Dr. Thomas E. Murley, Regional AdministratorU. S. Nuclear Regulatory CommissionRegion I631 Park AvenueKing of Prussia, Pennsylvania - 19406

Dear Dr. Murley:

Enclosed is the Rochester Gas and Electric "Nuclear EmergencyRadiation Plan." This plan incorporates the Offsite Radiation Plan withthe onsite plan into a single document, which replaces the SC-1"Radiation Emergency Plan."

Included in this plan are the modifications listed in Enclosure 1

to Inspection No. 50-244/83-25, January 18, 1984, item 3.23.

U truly yours,

Roger Vl. Kober

fEnc. (2)

xc: Document Control Desk (2)

8408i40ihi 840809PDR @DOCK 05000244

PDR

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1

Page 5: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

GING STATION NUCLEAR EMERGENCY RESPONSE PLAN

(NERP)

REVISION NUMBER

REVISION DATE

PORC APPROVED 9 - 0MEETING NO

01 23DATE

NSARB APPROVEDMEETING NO.

0DATE

Page 6: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

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Page 7: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

NUCLEAR EMERGENCY RESPONSE PLANLIST OP REVISIONS - BY PAGE

Page 1

PAGE

1A-1G

10

12

13

14

15

16

17

18

19

20

21

22

23',

0

SION NO. DATE

June 1985

June 1985

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

July 1984

November 1984

November 1984

November 1984

July 1984

June 1985

July 1984

June 1985

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Page 1A

ev sions to uc ear Eme en Res onse Plan cont'd

24

25

26

27

28

29

30

31

32

33

34

35

36'7

38

39

40

41

42

43

44

45

46

47

49

0

0

0

0

0

July 1984

July 1984

November 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

'July 1984

July 1984

July 1984

- July 1984

July 1984

July 1984

July 1984

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Qgl

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Page 1B

evisions to Nuclear Emer en Res onse Plan contend

50

52

53

54

55

56

57

58

60

61

62

63

64

65

66

67

68

70

71

72

73

74

0

July 1984

July 1984

November 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

June 1985

July 1985

July 1984

July 1984

July 1984

July 1984

July,1984

July 1984

July 1984

July 1984

July 1984

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Page 1C

evisions to uclear Eme en Res onse Plan cont'5

76

77

78

79

80

81

82

83

84

85

86

87

88

89

90

92

93

94

95

96

97

98

99

100

101

0

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

July 1984

Ju1.y 1984

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

June 1985

July 1984

July 1984

July 1984

July 1984

June 1985

June 1985

July 1984

July 1984

July 1984

July 1984

July 1984

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iM

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Page 1D

evisions to Nuclear Emer en Res onse Plan cont'd

102

103

104

105

106

107

107A

108

109

110

111

112

113

114

115

116

117

118

119

120

121

122

123

124

125

125A

0

0

2

.0

July 1984,

July 1984

July 1984

July 1984

June 1985

June 1985

June 1985

July 1984

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

July 1984

July 1984

July 1984

July 1984

June 1985

July 1984

July 1984

June 1985

July 1984

June 1985

July 1984

June 1985

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Page 1E

evisions to Nuclear Eme en Res onse P an cont'1

126

127

128

129

130

131

132

133

134

135

136

137

138

138A

138B

138C

139

140

141

142

143

144

145

146

147

148

0

- 0

0

July 1984

July 1984

June 1985

July 1984

July 1984

July 1984

June 1985

.July 1984

November 1984

November 1984

July 1984

July 1984

July 1984

July 1984

July 1984

June,1985

July 1984

July 1984

July 1984

July'984July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

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p3

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Page 1F

ev s ons to uc ea e en es onse an cont'1

149

150

151

152

153

154

155

156

157

157A

157B

158

159

160

161

162

163

164

165

166

167

168

169

170

171

172

0

0'uly

1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

November 1984

November 1984

November 1984

November 1984

November 1984

November 1984

November 1984

November 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

July 1984

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",)~gq,

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Page 1G

ev sions o uc ea e en es onse a ont'd

173

174

175

176

177

178

0

0

0

0

July 1984

July 1984

July 1984

July 1984

June 1985

June 1985

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Age

P

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o Co te

1.0 Scope and Applicability1.1 Definitions

Pacae No.

2 ' Summary of Emergency Plan

3 ~ 0 Emergency Conditions3.1 Local Radiation Emergency3.2 Unusual Event3.3 Alert3.4 Site Area Emergency3.5 General Emergency3.6 'State of New York Emergency Actions3.7 Other Emergency Plans

1314

,141515181820

4.0 Organizational Control of Radiation Emergency4.1 Normal Operating Organization4.2 Emergency Organization4.3 Augmentation of the Emergency Organization

21212430 I

5..0 Emergency Measures5.1 Local Radiation Emergency5.2 Unusual Event5.3 Alert5.4 Site Area Emergency5.5 General Emergency5.6 Major Release to the Lake5.7 Public Relations

3939404143 I

535457-

6 ~ 0 Emergency Facilities6.1 Emergency Response Facilities (RG&E)6.2 Communications System6.3 Assessment Facilities6.4 Protective Facilities6.5 First Aid and Medical Facilities

60so6466:8286.

Revision 9 November 1990

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4'

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Tab s o

7 ' Maintaining Nuclear Emergency Preparedness7.1 Training and Drills7.2 Review and Revision of the Plan and

Procedures7.3 Emergency Equipment and Supplies7.4 Auditing

~Pa ~to.8787

l

9393

8 ~ 0 Headquarters Offsite Response Plan8.1 Summary8.2 Organization8.3 Responsibilities8.4 Facilities8.5 Communications8.6 Training and Procedure Maintenance

9494969798

102103

9.0 Recovery9.1 Recovery Actions

105106

Revision 9 Movaaher 1990

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Z

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en ice

A.

B.

Co

D.

E ~

F.

G.

H.

Z.

Letters of Agreement

Summaries of Znterfacing Emergency Plans

Pre-Calculated Post-Accident Doses

Categories of Emergency Equipment

Emergency Plan Zmplementing Procedures

Population Data in Site VicinityArea Evacuation Time Estimates

NUREG 0654 Evaluation Criteria Cross Reference

Location of Sirens and Tone Alert Radios

Pacae No.

110-129

130-133

134-135

136

137-142

143-146

147-157

158-166

167 174

Revision 9 November 1990

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h 'J

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L st o es and ab es

Table 3.1

Figure 4.1

Table 4.1

Figure 4.2

Figure 4.2A

Figure 4.2B

Figure 4.3

Figure 5.1

Figure 5.2

Table 5.1

Figure 5.7

Figure 6.1

Table 6.3A

Tel~6 ~ 3B

Table 6.3C

Figure 6.3

Figure 7.1

Figure 8.1

Figure 8.2

Figure 8.3

Sample Emergency Classification Guidelines

Ginna Station Organization

Staff Responsibilities, (Emergencies)

Normal Operations Shift Complement

Normal Onsite Organization

Onsite TSC Organization

Interrelationships of Ginna Station &

Response Organization

Ginna Station Notification Scheme

Evacuation Routes

Recommended Protective Actions

Preformatted Press Form

Emergency Center Interfaces

Effluent Radiation Monitors

Sping 4 Radiation Monitoring System

Area Monitors

Thermoluminescent Dosimeter Locations

Emergency Planning Organization

RG&E Emergency SupportOrganization

Joint Emergency News Center

Emergency Operations Facility/EngineeringSupport Center and additional areas

Pacaa No.

22

25

23

26

27

31

51

56

59

61

69-70

71-72

73

79

92

96A

101

101A

Revision 9 November 1990

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Page 31: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

lan APP C

The Nuclear Emergency Response Plan (NERP) describes thetotal preparedness program established, implemented andcoordinated by the Rochester Gas and Electric Corporation(RG&E) to ensure the capability and readiness for copingwith and mitigating both onsite and offsite consequencesof radiological emergencies at RG&E's operating nuclearpower plant, Ginna Station. The plan covers the spectrumof emergencies from minor localized incidents to majoremergencies involving protective measures by offsiteresponse organizations. Included are guidelines forimmediate response, assessment of emergency situationsgdefined action criteria and delineation of support andrecovery functions. Emergency implementing proceduresprovide detailed information for individuals who may beinvolved with specific emergency response functions.The NERP provides for a graded scale of response fordistinct classifications of emergency conditions, actionwithin those classifications and criteria for escalatingto a more severe classification. This classificationsystem is identical to that used by the State of NewYork and the local (Wayne and Monroe County) emergencyresponse agencies. The plans have four categories ofemergencies: Unusual Event, Alert, Site Area Emergencyand General Emergency. A fifth classification, LocalRadiation Emergency has been added. A Local RadiationEmergency is less severe than an Unusual Event and doesnot involve any offsite organization.The NERP describes the activities and provisions otherthan engineered safeguards systems which are intended tolimit exposures to the general public as wall as toplant personnel. The NERP covers the following condi-tions:1) Major release to the atmosphere

2) Major release to the lake.

3) Abnormally high radiation or airborne radioactivityin a particular area of the plant.

4) Plant conditions that may lead to potentialreleases.

Revision 9 Noveaber 1990

Page 32: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

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Page 33: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

Rochester Gas and Electric Corporation has the immediateand continuing responsibility for limiting the conse-quences of an incident at the Ginna Nuclear Power Plant.Limiting the consequences to public health and safetyshould take clear precedence over limiting financialloss or adverse publicity. During a radiologicalemergency, RG&E should take whatever action is deemednecessary to limit the consequences to public health andsafety, even if that action violates the Ginna TechnicalSpecifications. Such actions would require concurrenceof a minimum of two licensed reactor operators andfollow up notification to the NRC in accordance with 10CFR 50 '4X.RG&E is responsible for keeping local, State and Federalauthorities informed on the status of the. emergency asit relates to protection of the public health and safety.RG&E will recommend to local, State and Federal authori-ties specific protective actions to limit the danger tothe public, including evacuation.

RG&E understands that it is the Nuclear Regulatory Commis-sion's policy that the emergency should be managed bythe licensee. The NRC staff at the Region I OperationsCenter is limited in its ability to provide detailedrecommendations to plant personnel or plant managers atthe site. RG&E understands that the NRC Operations Centerwill be the primary location where this agency willmonitor and evaluate licensee actions. During thattime, the normal response roles for the NRC OperationsCenter will be to monitor,,inform, and, upon request,advise licensees and other local, State and Federalauthorities. The authority for managing the NRC'semergency response efforts will be transferred to asenior onsite NRC representative when the NRC RegionalAdministrator is confident the onsite representatives areprepared to receive that authority. Their role willcontinue to be monitoring, advisory and informing plantand local authorities.

t ons:

A. tg f. \gnon-essential personnel congregate following a SiteEvacuation.

B. ~C ter — Locations where communications areavailable, information is available and personnelwill assemble to evaluate conditions during andafter an event. See Section 6.1 for details.

Revision 9 November 1990

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Page 35: BYNAME Nuclear Unit }i Gas Electric Region f Radiation„Plani · REGULATORY NFORMATION DISTRIBUTION SY. 'M (RIDS) DOCKET ¹ 05000244 size:] PJ ACCESSION NBR;8408}40161 DOC,DATE:

o ate Nuclea Eme enc Planner - The individualwho has overall responsibility for maintaining theNuclear Emergency Response Plan and implementingprocedures. He will also coordinate these plans withNew York State and county organizations havingemergency responsibilities. He will act as liaisonwith private organizations in developing plans whichaugment RG&E Plans.

~Di~l - A drill is a supervised instruction periodaimed at developing, maintaining and testing skillsneeded for a particular operation. A drill will besupervised by qualified instructors or controllers.

e lass ev « Four EmergencyClassification Levels have been established by theNRC and incorporated into the NERP and State andCounty Plans. Each class requires a different degreeof response actions by the state, counties andRGEE. The four classes are:

Unusual Event - an event which indicates a potentialdegradation of the level of safety of the plantAlert - an event in progress which involves anactual or potentially substantial degradation ofthe level of safety of the plantSite Area Emergency - events have occurred whichinvolve actual or likely ma) or failures of plantfunctions needed for protection of the publicGeneral Emergency - events which involve actual orimminent substantial core degradation or meltingwith potential for loss of containment integrity

e Coo at - An individual who hasreceived appropriate training in the actions to betaken in the event of an incident at Ginna Station.He has full authority and responsibility for meetingthe emergency. This is the Shift Supervisor untilhe is relieved by the TSC Emergency Coordinatortaking Command and Control. Finally when theEOF/Recovery Center assumes Command and Control,the EOF/Recovery Manager assumes overall responsi-bility for the emergency. The Emergency Coordinatormaintains close liaison between the TSC and EOF.

Revision 9 November 1990

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enc Zone (EPZ) - An area aroundGinna Station divided into Emergency ResponsePlanning Areas (ERPAS) for which preplanned actionsto meet possible hazards have been developed.Actions to meet site hazards are the responsibilityof RG&E. Protective actions in the Plume ExposureZone (approximately 10 miles) are the responsibilityof the county organizations. New York State isresponsible for actions to limit ingestion exposurein the zone out to approximately 50 miles.

i 1 V hfrom this facility to gather actual data forevaluation by the health physicists.

e c 0 e a ion EO - A facilitylocated in the basement of 49 East Avenue fromwhich additional RG&E personnel, consultants, NRCand other individuals can provide assistance to theplant in evaluating any emergency, gaining control.of it and continuing the recovery operation.Meteorology, field monitoring and plant data can beevaluated here by a health physicist and recommendat-ions made to the state and counties for protectionof the public.~~c~s - An exercise is an event that tests theintegrated capability and a ma)or portion of thebasic elements existing within the emergencyresponse plans and organizations.Z t News te - Xs located in theRG&E Corporate Office Building., Zt has facilitiesfor press briefings, rumor control and generalinformation dissemination. Information regardingthe status of Ginna Station will come from theEOF/Recovery Center. The Zoint News Center may beset up prior to activation of the EOt/RecoveryCenter. See EPXP 4-6, "Joint Emergency News CenterActivation" for details.

Revision 9 Noveaber 1990

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olo c er enc — An incident that mayresult in the uncontrolled release of radioactivematerial leading to a hazard or potential hazard tothe health and safety of the general public. As aresult, the Ginna Emergency Organization, RG&ERecovery Organization, State and County EmergencyOrganizations may be activated, depending upon thelevel of response required.

st icted A e - Those areas within the stationfence. Normal access is through the guard-controlledmain gate.

~osite — All public and private property outsidethe site property owned by Rochester Gas andElectric Corporation.

That property around dinna Station whichis owned and controlled by Rochester Gas and ElectricCorporation.

ch ica u o ente T — An onsite facilitywhich is used by the plant staff'o assist theoperating personnel in evaluating an emergency andbringing the plant under control. The TSC is acoordinating center for gathering and initiallyevaluating information relative to accident condi-tions and possible offsite radiation and contamin-ation. The initial EOF actions will take placehere until that Center is manned. The EmergencyCoordinator will maintain communications from herewith the EOF personnel.

Revision 9 November 1990

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11

0The primary object of this plan is to protect the publicand on4ite personnel in the event of a radiation emer-gency. This plan describes in general the actions to betaken by RG&E personnel in coordination with local,state and federal authorities.Through an emergency organization, which is described,the magnitude and impact of radioactive releases will beassessed and the need for the activation of a moreextensive emergency response will be determined. Thesystems for notification of emergency personnel, federalstate and local authorities and the public are describedalong with the emergency facilities and equipment whichare available for the trained emergency staff. The goalof the RG&E Emergency Organization is the safe shutdownand recovery of Ginna Station and protection of thehealth and safety of the public and employees.

The general actions to be taken in the event of aradiation accident include the following:1) Observation and determination of the class of the

occurrence.

2) Prevention or minimization of radiation hazards bythe Emergency Coordinator and the on-duty operators.

3) Evacuation of all non-essential personnel from thePlant to the Ginna Training Center.

4) Involvement of Plant Guards, Supervisory personnel,Chemistry and Health Physics personnel, and otherplant staff.

5) Notification of NRC Operations Center and State andLocal Authorities, issuance of news releases, andemergency medical treatment.

6) Activation of Emergency Response and EmergencySupport Organizations.

7) Recovery and restoration of the plant to normaloperation.

The extent of response to an emergency situation isdetermined by the seriousness of potential consequences.With +e potential for effects to the general public,the assistance of state, local and federal agencies willbe required. For situations'hich only affect on-siteoperations, the situation will be met by RG&E capability.

Revision 9 Noveaber 1990

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The awareness of an emergency situation vill most likelyoriginate in the Control Room. From an evaluation ofplant parameters, the seriousness of the incident can bedetermined and the appropriate classification determined.Tho on-duty plant operators, under the dire'ction of theShift Supervisor, in consultation with the ShiftTechnical Advisor, will take action to mitigate theincident and to obtain the assistance of other plant andRG&E personnel.

Personnel onsite vill be alerted by a warning signal ifevacuation is deemed advisable and off-duty personnelwill be called in through an established call procedure.Federal, State and County officials will be notified sothat they may begin to set up their response organiza-tions. If the level of the incident requires activationof the Emergency Organization, trained people will man,theTechnical Support Center, the Survey Center and laterthe Emergency Operations Facility. , These centers willbe activated, per procedure, by designated people whohave'een trained in the'uties required to meet theincident. Sufficient individuals are trained so thatthe Jobs can be filled regardless oi who is on site or'vailable for call-in.Public off'icials vill be kept informed of the situationas it progresses. For certain classes of events, theEOF will be activated for continuing management of theincident and to assist in restoring the plant to normaloperation. A Joint Emergency News Center will beestablished to keep the public avare of the situationand news releases will be coordinated between RG&E, NewYork State and other government agencies.

Revision 9 November 1990

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13

3.0 COND 0

Emergencies are classified into five categories whichcover the entire spectrum from probable incidents topostulated major accidents. This system is coordinatedwith NRC, New York State, Wayne County and Monroe Countyto ensure that the classification system is compatiblewith that used by all organizations. The system providesfor notification of appropriate emergency responseorganizations and implementation of actions immediatelyapplicable to a specific condition. Provisions areincluded for revising the classification level and thecorresponding responses in tha event of a change inseverity of the emergency condition. This sectionidentifies the events which comprise each of the fiveemergency classifications.Criteria for characterizing, recognizing and declaringeach emergency class are given along with appropriateaction levels. Recognition and action level criteriaare based, to the extent feasible, on readily availableinformation such as Control Room instrumentation. Plantparameter values and the corresponding emergency classi-fications are given in appropriate implementing procedu-res. Immediate actions to be taken in response to plantcondition are detailed in plant operating and emergencyprocedures. Other emergency actions in response toradiation emergencies are identified in section 5.0 anddescribed in detail in applicable Emergency Plan Imple-menting Procedures (EPIP) as listed in Appendix E.

The emergency classification system is illustrated bysome examples provided in Table 3.1. A comprehensivelisting of Ginna specific initiating conditions for eachemergency classification is provided in EPIP 1-0. EPIP1-0 is based on NRC guidance provided in NUREG 0654Appendix 1 and demonstrates how an initiating conditionleads directly to the appropriate emergency classi-fication, based on the magnitude of the event. In somecases, extensive assessment is necessary to determinethe applicable emergency classification. In any case,continuing reassessment is required to ensure that theclassification is upgraded or downgraded commensuratewith the severity of the condition.

Procedure EPIP 1-0 among others, can be found in theControl Room, Technical Support Center and EmergencyOperations Facility.

Revision 9 November 1990

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14

3 ' adiat on e e cIncidents may occur which require response only within theplant. A Local Radiation Emergency is defined as aradiation emergency condition whose consequences affectonly personnel onsite. A Local Radiation Emergencyshall be declared when 1) any area monitor alarmsunexpectedly 2) there is reported an unexpected increasein the airborne activity in a work area, 3) there is asignificant radioactive spill in an area, 4) Hi Fluxalarm during shutdown, or 5) the operator in chargedeems it necessary. Operator )udgment shall prevail sothat the emergency procedure may be initiated withouttotal dependence on instruments.

A radiation alarm in the Auxiliary Building couldindicate a faulty monitor, but if the vent monitoralarms concurrently, a serious condition has probablyoccurred. A release rate of less than Technical Specific-ation limits can be treated as a Local Radiation Emer-gency.

An alarm on the liquid effluent monitor (R-18) couldindicate a low level release of radioactivity into thelake. This would require action by plant personnel. Arelease at levels less than the limits given in 10CFR20,Appendix B, Table II, Column 2 can be treated aa a LocalRadiation Emergency.

3 'Events within this classification generally characterizeoff-normal plant conditions which, by themselves, do notconstitute significant emergency conditions. Some ofthese events could, however, indicate a potential de-gradation in the level of plant safety and/or couldescalate to a more severe condit'ion if appropriateaction is not taken.

The primary purpose for this classification ia to ensurethat the plant operating staff recognizes initiatingconditions, takes appropriate action and comes to a stateof readiness to respond in the event that the conditionbecomes more significant. The Unusual Event classifica-tion or higher also requires that off-site authoritiesare promptly informed of'he abnormal condition by useof the Radiological Emergency Communications System(RECS) and the New York State Radiological Data Form,Part I, EPIP 1-5. No response is necessary by off-siteauthorities for events within this classification. TheTSC or EOF will,not usually. be activated, although thePlant Manager, Duty Engi'neer,'nd Operations Nanager ortheir alternates will normally report to the TSC toprovide communications assistance.

Revision 9 Noveaber 1990

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15

An example of EPIP 1-0 (Table 3.1) indicates the degreeof severity which classifies an initiating conditionsuch as an Unusual Event. When giving notice to stateand county officials RG&E will make sure that theyclearly understand the Unusual Event classification andthat if conditions change there will be further notifi-cation.

3 '

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A~crt:

This classification is characterized by events whichindicate an actual degradation of the level of plantsafety. This classification may require response by theplant emergency organization, augmentation of onsiteemergency resources, and constitutes the lowest levelwhere emergency offsite response may be anticipated.EPZP 1-0 shows the degree of severity which categorizesplant conditions as "Alert" class. The Technical SupportCenter will be manned for all conditions of the Alertclass. The EOF may be activated at the discretion ofthe EOF/Recovery Manager.

Prompt notification of an event within this class willbe made to the NRC, State of New York and Monroe andWayne Counties. While the initial assessment would notrequire immediate response, potential releases ofradioactivity make it advisable to alert offsiteorganizations. Periodic status updates will be made tokeep authorities aware of the situation.Ste e Em ecA Site Area Emergency is characterized by events involvingactual or probable major failures of plant functionsneeded for protection of the public. Most events withinthis classification constitute actual or clear potentialfor significant releases of radioactive material to theenvironment. Although emergency actions involvingmembers of the public may not be necessary, offsiteemergency response organizations should be mobilized andready to implement protective measures. Protectiveactions taken onsite are: the evacuation of all personsin areas other than the Control Room and TechnicalSupport Center; activation of the Technical SupportCenters initiation of onsite and offsite radiationmonitoring; and close monitoring of plant status so thatutility and other authorities can be advised of changingconditions, whether increasing or decreasing in severity.Meteorological and release data and survey results willbe used to provide offsite dose estimates. For a SiteArea Emergency the EOF will be activated.

Revision .9 November 1990

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16

Examples oi situations are provided in EPZP 1-0 tocharacterize the types of incidents which are expectedto fall in this class. For the purpose of classifying anemergency, instrument indications in the Control Roomvillhe used. The instruments of interest and appropriateaction points are part of implementing 'procedures.

Revision 9 Noveabor 1990

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18

3 ' ea Emerec

A General Emergency is characterized by events whichinvolve actual or imminent substantial core degradationor melting with potential for loss of containmentintegrity. Initial declaration that a General Emergencymay exist is based on a situation which may have thepotential for serious radiological consequences to thehealth and safety of the general'ublic. A Site AreaEmergency most likely would have been declared earlier,and if events are in progress which may involve coredegradation with potential for loss of containmentintegrity a General Emergency should be declared. For aGeneral Emergency all centers will have to be activated.

The Emergency Coordinator or EOF/Recovery Manager, if hehas assumed command and control, will promptly notifystate and local authorities and the NRC of the plantstatus and reasons for declaring a General Emergency.The Emergency Coordinator or EOF/Recovery Manager willalso make recommendations for offsite emergency measuresto be taken. The responsibility for this recommendationto offsite authorities may not be delegated.

3.6 a e o New o WaLoOs:

o Co e e

It is the responsibility of the Rochester Gas and ElectricCorporation to provide prompt notification to State andCounty authorities when conditions or circumstancesonsite have affected or may affect normal and safe plantoperations.

It is the responsibility of these offsite agencies toprovide prompt notification to their parent and supportorganizations ii it is determined that conditions orcircumstances either offsite or onsite have affected ormay affect normal and safe plant operations, or conditionsin the environs.

Wayne and Monroe Counties decision process includes EPAprotective Action Guidelines (PAG), current road andweather conditions, time requirements for implementingPAGS and accident diagnosis and prognosis received fromthe licensee, NYSDOH, USNRC and DOE.

Revision 9 November 1990

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19

For this purpose, the Nuclear Regulatory Commission(NRC) has established, and the State of New York, hasaccepted four Emergency Classification Levels for whichRG&E shall provide early and prompt notification to bothState and Local (County) authorities. The four EmergencyClassification Levels that are in the New York StateRadiological Emergency Preparedness Plan are:

Unusual events are in progress or have occurredwhich indicate a potential degradation of thelevel of safety of the plant.

b) AlertEvents are in progress or have occurred whichinvolve an actual or potential substantial degrada-tion 'of the level of safety of the plant.

c) S te Area Emer encEvents are in progress or have occurred whichinvolve actual or likely ma)or failures of plantfunctions needed for protection of the public.

d) General Emer e cEvents are in progress or have occurred whichinvolve actual or imminent substantial core degrada-tion or melting with potential for loss of contain-ment integrity.

The rationale for the "Unusual Event" and "Alert" classesis to provide early and prompt notification of minorevents which could lead to more serious consequencesgiven operator error or equipment failure, or whichmight be indicative of more serious conditions which arenot yet fully realized. A gradation is provided toassure more complete response preparations for moreserious indicators.The "Site Area Emergency" class reflects conditions wheresome significant releases are likely or are occurringbut where a core-melt situation is not indicated, basedon current information. The "General Emergency" classinvolves actual or imminent substantial core degradationor melting with the potential for loss of containment.For both the "Site Area Emergency" and "General Emer-gency," full mobilization of emergency personnel in thenear-sita environs is indicated as well aa dispatch ofmonitoring teams and associated communications.

For a "General Emergency" immediate public protectiveactions are necessary. The State Commiss1onor ofHealth, based on information obtained from RG&E or othersources and his own understanding of events and circum-stances, may recommend protective actions of differentseverity than those recommended by RG&E. It he does,the protective action recommended by the State vill be thebasis upon which emergency response actions are declaredby both State and county authorities.

Revision 9 November 1990

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3 ' er e

Zn the event of an emergency such as adverse weather,earthquake, fire or high watex, the appropriate S iteContingency Plan shall be put into effect. These plansare:

SC-2 Adverse Weather Emergency Plan

SC-3 Fixe Emergency Plan and Implementing Procedures

SC-4 High Water (Flood) Emergency Plan

SC-5 Earthquake Emergency Plan

SC-6 Action for Hazardous Chemical Spill and ImplementingProcedures

SC-7 Site Contingency Plan - Aircraft Crash

SC-8 Turbine Blade Failuxe and MissilesGS-50 Security Contingencies

A-7 Procedures for Handling Illness or In)ugly at GinnaStation

In addition, RG&E's NERP and other implementing proceduresare coordinated with those used by external organizationssuch as:

1. Decontamination and Treatment of the RadioactivelyContaminated Patient at oc e te Ge e s ita

2. Decontamination and Treatment of the RadioactivelyContaminated Patient at Newar -Wa e o unitH~os ~ta

3 ~ 1gt 1 8 YPlan.

4. W e Count Radiological Emergency PreparednessPlan.

5. e York State Radiological Emergency PreparednessPlan.

Revision 9 November 1990

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4 ' ON C 0 0 N EMERG NC

4.1

The overall responsibility for safe operation of theplant rests with the Plant Manager. The normal stafforganization is given in Figure 4.1. Individualresponsibilities for normal operations are defined inAdministrative Procedures. The minimum shift complementconsists of the operating personnel as shown in Figure4.2: one Shift Supervisor, one Control Room Foreman, oneHead Control Operator, one Control Operator, twoAuxiliary Operators, ona Communicator, and a ShiftTechnical Advisor as specified in Technical Speci-fications. Also available for operational assessment isa Duty Engineer on 24 hour call. As part of each shifta third Auxiliary Operator is designated Communicator.

Radiation protection within the plant is provided by theHealth Physics Technician on duty. This individual isalso trained in chemistry and is scheduled around theclock for normal operations. According to the call-inprocedure all other technicians and chemists can becalled in to assist in case of emergency. He is augmentedby Auxiliary Operators, who are also trained in healthphysics practices.Xn accordance with the Technical Specifications, a 5person fire brigade is on site at all times. Proceduresprovide for calling the local fire department for assis-tance, if needed.

Medical emergencies and First aid are covered by anadministrative procedure (A-7 "Procedures for Handlingillness or Inguries at Ginna Station). Operations staffare trained in first aid.The operating shift complement provides the initialemergency response and the communications links tooffsite participating emergency organizations and/or to I

off-duty staff personnel. See Figure 5.1.

Site Access Control and Personnel Accountability is theresponsibility of the security personnel.

Revision 9 November 1990

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NORMAL GINNA STAFF ORGANIZATION

PLANTMANAGER

SUPERINTENDENTGINNA

PRODUCTION

CORRECTIVEACTIONS

MATERIAIS.PROCUREMENT

8t BUDGETSAFETY

SUPERINTENDANTSUPPORTSERVICES

OUTAGEPLANNING

OPERATIONSMANAGER

TECHNICALMANAGER

HEALTHPHYSICSCHEMISTRYMANAGER

OPERATIONSASSESSMENT

8r.Qlr.0

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MANAGER

ELECTRICAL/ L/CMANAGER

MECHANICALMAINTENANCE

MANAGER

MODIFICATIONSUPPORT

COORDINATOR

FIREPROTECTION

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Figure 4.1

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NORMALOPERATIONS SHIFT COMPLEMENT

HEALTH PHYSICSTECHNICIAN

1/ SHIFT

SHIFT SUPERVISOR

CONTROL ROOM FOREMAN1/SHIFT.

SHIFT TECHNICALADVISOR

HEAD CONTROL OPERATOR1/SHIFT

CONTROL OPERATOR1/SHIFT

AUXIUARYOPERATORS2/SHIFT

When RCS AverageTemperature > 200'.

" Asecond SROwill beonshift as required by 10CFR 50.54when RES average temperature> 200'.

COMMUNICATOR1/SHIFT

Figure 1.2

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24

4 ' enc Or an z t o

4.2.1 The overall responsibility of the Nuclear EmergencyResponse Plan (NERP) implementation is assigned to anEmergency Coordinator. These individuals have receivedappropriate training in the actions to be taken in theevent of an incident at Ginna Station. He has fullauthority and responsibility for meeting the emergency.This is the Shift Supervisor until he is relieved by theTSC Emergency Coordinator taking Command and Control.Finally when the EOF/Recovery Center assumes Command andControl, the EOF/Recovery Manager assumes overallresponsibility for the emergency. The Emergency Coor-dinator maintains close liaison between the TSC and EOF.

The Emergency Coordinator is authorized to make any andall procurements and expenditures he deems necessary,and to order any services from within or outside theCompany. He shall maintain communication and liaisonwith the NRC, State of New York cognizant agencies andcounty authorities regarding offsite support activitiesand will recommend protective actions based upon availableinformation. Following the transfer of command andcontrol to the EOF/Recovery Center, the EOP/RecoveryManager will assure a continuity of resources for con-tinuous operations over a protracted period of time.Figure 4.2A shows the organization with the ShiftSupervisor as Emergency Coordinator. This Phase Iorganization is the normal Control Room complement andhas Emergency responsibility until relieved by the TSCEmergency Coordinator and a Phase II organization.After the Plant Assessment Team is active, the ControlRoom organization reports to the Plant OperationsAssessment Manager as shown in Figure 4.2B and then hasthe primary function of'afe plant manipulation.Table 4.1 illustrates the correlation between the Plantorganization (Figures 4.2A and 4.2B) and NUREG 0654.

Revision 9 Noveaber 1990

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Revision 8 October 1989

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.Revision 8 October 1989

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NORNAL ONSITE ~ SUBSEQUENT CALL IN

Plant Operations and Assesasant ofOperational Aspects

Shift SupervisorControl Rooa Foreaaniiead Control'peratorControl OperatorAuxiliary OperatorsCoaaunicetor

1

1

1

1

2

1

Operations Assesseent Nenager

Eaergency Oirection and Controlalternate(Eaergency Coordinator)

Shift Supervisor Plant Nanager or qualified

Notification/CoaaunicationNanager

Shift Coaaunicator Ada ini str ~ t i ve/Coaauni cation

Radiological Assessaent and Support ofOperations Accident Assessaent

Offsite SurveysOnsite (out-of. plant)Cheaistry/Radiocheaistry

!D

Plant Systeas Technical Support andCorrective Actions

0Redid tion Protection (In-plant)

Health PhysicsTechnician

Shift Technical Advisor 1

Health Physics TechnicianAuxiliary Operators

Dose Assesseent NanagerHP and Cheaistry NanagerSurvey Center Nanager

Plant Naintenance Assesseent NgrPlant Technical Assessaent Ngr

HP and Cheaistry Nanager

Fire Fighting0

Rescue Operations and Fir at Aid9 SquadI

Fire Brigade per T.S.

F'irst A'Id Tea%

Ontario Fire Co.

Ontario Volunteer Eaergency

Site Access Control and PersonnelAccountability

Cl

Security Personnelper Security Plan

Security Personnel

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II

ONSITE ORGANIZATIONwith Shift Supervisor as Emergency Coordinator

~ I

NRCResidentInspector

SHIFTSUPERVISOR

(Emergency Coordinator)Shift Technical Advisor

Communicator Health PhysicsTechnician

Control Room Foreman

Head Control Operator

Control Operator

AuxiliaryOperators (2)

Figure 4.2A

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E

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I

TECHNICALSUPPORT CENTERORGANIZATIONCHART

EMERGENCY COORDINATOR (TSC Director)

SURVEY CENTERMANAGER

DOSE ASSESSMENTMANAGER

ADMIN/COMM'MANAGER

SECURITYMANAGER

ASSISTANT

COMMUNICATOR

PERSONNELCOORDINATOR

ADDmONALPERSONNEL

SUPPORT STAFF

OFFSITE TEAMS

ONSITE TEAMS

SWITCHBOARDOPERATOR

RADIO OPERATOR

SWITCHBOARD/RADIO MSSNGR

COMMUNICATOR

ADDITIONALPERSONNEL

r.osr0

R0

9

0'EALTH

PHYSICS &CHEM'MANAGER

HEALTH PHYSICS TECH

CHEM TECH

ADDITIONALPERSONNEL

PLANTTECHNICALASSESSMENT MANAGER

NUCLEAR

I/C 8c ELECTRICAL

MECH/HYD

COMPUTER

ADDITIONALPERSONNEL

PLANTMAINTENANCEASSESSMENT MANAGER

OSC PERSONNEL

PLANT OPERATIONSASSESSMENT MANAGER

SHIFT SUPERVI SOR

CONTROL ROOM FOREMAN

HEAD CONTROL OPERATOR

CONTROL OPERATOR

AUXILIARYOPERATOR (2)COMMUNICATOR

Revision 4january 1987

Figure 4.2B

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28

Figure 4.2B shows the Emergency Organization after theTSC Emergency Coordinator assumes command and control.Under the Emergency Coordinator there are eight ma)orfunctions in the emergency organization, Admin./Communi-cation, Security, Dose Assessment, Survey Center, HealthPhysics and Chemistry, Plant Technical Assessment, PlantMaintenance Assessment and Plant Operations Assessment.If onsite, when notified of TSC activation, the emergencyorganization personnel will report immediately to theTSC. If offsite when they receive notification, asspecified in implementing procedures, personnel shallreport to the Plant or Survey Center (if directed) toobtain assignments. The Ginna Training Center is usedas an emergency congregating area for personnel calledfrom offsite. A board in the Survey Center contains anumber of tags on which there is a list of duties foreach person. The tags are picked up in order of highestpriority for which personnel are trained as they arriveat the Survey Center. They will proceed to the TSC asadvised by the Survey Center Manager or EmergencyCoordinator.

When onsite, the Operations ,Manager or his alternateshall report to the Technical Support Center to directplant operations in combating the emergency. Accidentassessment will be performed mainly in the TechnicalSupport Center (TSC). This center will be manned byengineer level plant staff and will have available allinformation from the Control Room. The Ginna EmergencyResponse Organization consists of the following positions:Plant Manager, Operations Assessment Manager, Administra-tive/Communications Manager, Plant, Technical AssessmentManager, Plant Maintenance Assessment Manager, DoseAssessment Manager, Health Physics and Chemistry Managerand Survey Center Manager. These positions will bemanned by individuals reporting onsite within one hourof the declaration of an ALERT or higher classification.The Plant Security organization will maintain liaison inthe TSC so as to coordinate its onsite and site perimeteractivities with the needs of the Emergency Coordinator(See Figure 4.2B).

Radiological Exposure Control is the responsibility ofthe Health Physics and Chemistry Manager and his healthphysicists. One Health Physicist is responsible foroffsite dose assessment and one has onsite respon-sibility in the Technical Support Center. Dose assessmentfor offsite areas will be made at the TSC until suchtime as the EOF organization is manned and prepared toassume responsibility for offsite dose assessment.Maps, procedures, trained personnel and current plantdata are available in the TSC for the aid in performingthese assessments.

Revision 9 November 1990

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The initial warning of an emergency situation is givenby the Control Room Operators. They will be aware ofany changes in the situation and give warning of theneed for a higher degree of action. The initial com-iaunication is also from the Control Room to local andstate officials and to the plant staff. As soon as theTechnical Support Center is operational, approximately15 minutes after arrival of trained personnel, individualstrained in using the communications equipment will takethe notification responsibility from the Control Room.They will continue to alert the plant staff and maintaincontact with state and local officials. Thus theControl Room personnel are able to concentrate on theoperations and/or shutdown of the plant.Responsibility for onsite health physics protectionrests with the Plant Health Physics and Chemistry Managerwho is part of the TSC Staff. He will insure theprecautions of section 5.4.4.1 are followed during theemergency.

The. Ginna Training Center basement is used as the SurveyCenter for dispatching monitoring teams. Informationgathered by the teams will be used by RGtE, the StateDepartment of Health and local authorities to determinewhat actions should be taken to limit radiation exposureto the general public. An alternate Survey Team stagingarea will be used in case the Ginna Training CenterBasement is not habitable. Alternate Survey TeamStaging areas may include the onsite Pro)ecta Buildingor other ofisite RGSE facilities. The Emergency Opera-tions Facility (EOF) also maintains radio and talephonecommunications capability for Survey Team deployment andplume tracking.The Survey Center Manager is one of the first positionsfilled. Trained Survey Team members pick up tags asthey arrive and immediately prepare to follow assignedsurvey routes. Their equipment as specified in proceduresincludes radios for communications with the TSC communi-cator and the Dose Assessment Manager. Each team,consisting of two persons obtain transportation (See5.4.7) and monitoring equipment (See 6.3.9 and AppendixD) and can be in the field within 45 minutes after theincident. Survey teams can be directed froa the EOF ifthe Survey Center is not habitable or when EOt.assumesformal control of the offsite teams.

All personnel are trained to specific responsibilitieswithin the Emergency Organization and records aremaintained by the Training Division and in CentralRecords.

Revision 9 Noveaber 1990

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4 '

30

Zf the incident warrants, an EOF/Recovery Center organi-zation vill be established off-site. The personnelwhich eke up this organization are shown in Figure 8.1.Thj EOF Response Organization (See 6.1.6) will be mannedand functioning within one hour of the decision to notifyits personnel upon declaration of a Site Area Emergencyand above. Each section manager maintains an up-to-datecall list for his section. The Plant Manager reportsthrough the Nuclear Operations Manager to the EOF/RecoveryManager.

e tatio o the Eme c 0 a zat o

The Ginna Emergency Organization is augmented by anumber of offsite services. Figure 4.3 shows therelationship of non RGSE offsite organizations inemergency response. Letters of agreement are provided,in Appendix A. These agreements will be consideredvalid until changed by the authors. The role of the EOFStaff, made up of headquarters personnel operating fromthe EOF, is explained in Section 9.0.Plant procedures contain the phone numbers and alternatemeans of contact needed to initiate emergency responseactions. The communicator will initiate a call to NewYork State, Monroe County and Wayne County EOC, usingthe NYS Radiological Emergency Communication System(RECS) hot line. During vorking hours the EOC directorwill respond and during ofi hours a Sheriffs Departmentor the State Police responds for each Emergency Directorto RECS hot line calls.

4 '.1

The EOF/Recovery Manager is alerted by a call from theGinna Control Room. Other offsite assistance such asDOE-RAP team or Westinghouse is alerted by a call fromthe Emergency Coordinator or designee to their dutyofficer at the phone numbers listed in procedures.

Sta o New Yo

RGSE has coordinated this emergency plan with the NevYork State Department of Health, and officials of Monroeand Wayne Counties. RG&E has agreed to notify theseorganizations in the event of any emergency involvingthe general public. The participation of the State andCounties in the emergency action is outlined in the NewYork State Radiological Emergency Preparedness Plan. Ingeneral the responsibility of the State of New York isto minimize the risk to the health of the inhabitants ofthe state, in the event of a radiological emergency.

Revision 9 November 1990

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INTERRELATIONSHIPS OF GINNASTATION AND RESPONSEORGANIZATIONS

r-

/

GINNASTATION CONTROL ROOM OR TSC

MEDICALEMERGENCY FIRE RADIATIONEMERGENCY

OVES PLANTDOCTORS

MEDICALEMERGENCY

CONSULTANTNEW YORK

STATE

N-WCH

ONTARIOFIRE

COMPANY

DOERAP/IRAP

FRMAP

WAYNECOUNTY

MONROECOUNTY

USCGIIL

IIL

SECURITYTHREATEOF

FOR SITE AREA EMERGENCYAND

GENERAL EMERGENCY

WAYNECOUNTY SHERIFF

Revision 8just 1989

Figure 4.9

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32

This will be accomplished by:

identifying measures to prevent and mitigate suchemergency.

2 ~

3 ~

4 ~

Developing mechanisms to coordinate Federal, State,Local and Private Sector resources during and aftersuch an emergency.

Determining and implementing a course of action tominimize the impact of a radiological emergency onthe public health and property.Providing for recovery following a radiologicalemergency.

Revision 4 January 1987

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33

sast o o (Wayne County Office ofEmergency Management and Office of Emergency Preparedness,Monroe County).

Xn general, the responsibilities of the Local DisasterCoordinator in each county include the following:

a) On receipt of notification from the State of NewYork, or Ginna Station Control Room, alert localauthorities and officials in accordance with estab-lished plans.

b) Coordinate response of local authorities andprovide for available local assistance to RG&Eand State authorities in accordance with establishedplans.

The participation of the counties, upon notification ofan event involving the general public, is outlined intheir Radiological Emergency Plans, which are reviewedin Appendix B.

The Office of Emergency Preparedness in each countyconsists of small administrative staffs and a pool ofreserve personnel located throughout the counties.Members receive training in monitoring, establishingrelocation centers and providing medical attention,food, and lodging for evacuees. Extensive communicationresources are available for use by the Local DisasterCoordinators and staff, including a number of radios forcontacting the county Fire Coordinator, the PoliceForces, Public Works and commercial radio stations. Aroster of telephone numbers and contacts is maintainedto communicate with agencies on state and local levels.Monitoring teams are available and radiological kits aremaintained in shelters and fire houses located throughoutthe counties.

t t tes Coas Gu (USCG)

The USCG willprovide emergency response upon notificationhy Wayne and Monroe Counties. Reference: Wayne CountyRadiological Emergency Preparedness Plan (REPP), Appendix

',

and Monroe County REPP, Procedure J.

Revision 7 October 1988

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34

e States Dee o

eto eo ve

adiolo ca Assistancee 0 c Uto e

Since Ginna Station is located in DOE Region I, theBrookhaven Office of the U.S. Department of Energy (DOE)has the responsibility to provide radiological assistancein the event of an emergency. Their principal goal is tobe prepared in the event of a ma)or accidental release,or other loss of control of radioactive material.

Radiological assistance can be requested at any time bycalling and indicating the nature of the incident, thelocation, and how to contact utilityand local 'authoritiesso as to coordinate the Department of Energy response.

The assistance includes advice and emergency actionessential for the control of the immediate hazards'ohealth and safety. This preparedness includes plans andprocedures for: effective and economic use of resources;minimization of radiation exposure of individuals andthe publicg prevention of the spread of radioactivematerials into the environmentg and appropriate counter-measures to control and remove radiological hazards.Large numbers of qualified radiation, nuclear andmedical specialists are the principal resource that canbe made available in an emergency along with quantitiesof radiation monitoring equipment and specializeddetector and test equipment.

Most assistance requests can be handled by giving advice,by sending radiological safety experts to the incidentscene, or by transferring the request to another federalagency or a state agency. The Department of Energy,Brookhaven Office has agreed to provide such assistanceupon notification oi a hazard to the general public.Available resources are noted in the County plans.Assistance could be on site within 4 hours of a request.RG&E will supply whatever support services and resourcesare needed to maintain federal assistance. RAP/IRAP teamsinitiallyreport to the EOP for briefing and coordination.

Zt should be understood that this federal advice,assistance and equipment is provided to the local govern-ment institutions to assist in carrying out theirresponsibilities and authority for protecting the healthand safety of the local population and in no way'upers-edes that local responsibility. Furthermore, thisassistance may be terminated as soon as the 1xaediatehazards are brought under co'ntrol and there ia reaionableassurance that public health and safety are beingprotected.

Revision 9 November 1990

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he

Tha Wayne County Sheriff's Department will assume respon-sibility for necessary police services in Wayne County.They respond to directions and requests from the Directorof Wayne County, Office of Emergency Management, whoidentifies problems and designates responsibilities.RG&E, Ginna Station, does not make direct contact withthe Sheriff's Department for radiation emergency.The same arrangement is true f'r the Monroe CountySheriff's Department which is directed by the MonroeCounty Director of Emergency Preparedness.

Three area physicians have been retained as plant doctorsto be on call for emergency assistance. Whenever RG&Epatients are referred to the hospital, a plant doctormonitors the cases for RG&E. These licensed physiciansare available to Ginna Station as medical consultantsand for immediate emergency treatment. They have attendedthe Training Seminars on Medical Care and Treatment ofRadiation Accidents and seminars given by RadiationManagement Consultants, and NRC.

e c

The responsibility of the Ontario Volunteer EmergencySquad (OVES) is to respond to requests by RG&E to assistin emergency first aid and to transport patients to thehospital if required. The Emergency Medical procedureincludes the means of communications with AmbulanceSquad.

OVES is located about five miles from Ginna Station. Ztis a volunteer organization consisting of about 60members. They have been trained in rescue and first aidand require a certified medic (Emergency Medical Tech-nician - EMT) to respond with all ambulance crews. .Thelevel of patient care OVES provides is sustained duringtransport to other advanced medical facilitiea such asRochester General Hospital. The emergency squad maintainsall required training certifications as required by theNew York State Health Department Bureau of EmergencyHealth Services. Active members are required to be atleast 18 years of age and have a minimum training levelequivalent to the American Red Cross Standard First AidCourse. The members are invited to attend an annualGinna Station site refamiliarization tour and areinstructed'n radiation protection requirements. Anannual training session conducted by Radi'ation ManagementConsultants (RMC) is also offered;

Revision 9 November 1990

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aiinlw -W o u t os-

Arrangements have been made with the designated hospitalsto receive and . assume control of patients from GinnaStation if requested. Implementing procedures includethe means of communication between the utility and thehospital.Facilities are available at the hospitals which can beconverted to a radiation emergency area with adequatecontamination control. Hospital personnel are trained inthe handling of radiation accident patients and eachhospital has an approved radiological emergency planspecific to their individual facilities and resources.

Planning has been carried out with coordination fromRadiation Management Consultants (RMC) who provide formaltraining annually. Health Physics instrumentation hasbeen supplied to the hospital by RG&E. Annual trainingdrills are conducted by RG&E and the hospital staffs andinclude critiques and videos by RMC. Hospital staffalso attend training seminars on treatment of radiationaccident victims.

Radiation Management Consultants (RMC) will respond asfollows upon request from one of the plant doctors orfrom RG&E.

a) Dispatch a radiation emergency medical team, whichis available on a 24 hour basis.

b) Make available the services of the RadiationMedicine Center of'he Hospital of the University'of Pennsylvania.

c) Make arrangements for air or ground transportationof patients to the Hospital of the University ofPennsylvania.

Revision 9 Noveaber 1990

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37

RMC has laboratory facilities at the University CityScience Center in Philadelphia and maintains medicalfacilities at the Hospital of the. University ofPennsylvania. RMC has an arrangement with the hospitalfor management and treatment of'adiation accidentvictims and ensures . that facilities necessary fortreatment are readily available by equipping the hospitalwith the medical and radiological equipment needed. RMChas conducted an initial evaluation and made recommenda-tions for an effective local medical emergency program,coordinating the planning for local medical support with

, RMC and the Hospital of the University of Pennsylvania.Periodic site visits are made to coordinate and reviewemergency medical support vith company officials andlocal medical personnel.

RMC also provides radiological emergency training forplant, hospital and ambulance personnel.

V u e

The'ntario Valunteer Fire Department vill provide firefighting personnel and equipment in accordance vith SiteContingency, Fire Emergency Plans, to supplement thetrained personnel. and equipment which is availableon-site.The Ontario Volunteer Fire Department is located aboutfive miles from the Ginna Station. It is a valunteerorganization consisting of about 50 active members.Additional fire fighting support is available ta theOntario Volunteer Fire Department through the WayneCounty Mutual Aid Fire Coordinator. Weekly trainingmeetings are conducted. On an annual basis the membersare invited to Ginna Station site to refamiliarize themwith the facility and its onsite fire fighting equipmentand vith radiation protection requirements.

C s tat a

Implementing pracedures give the name and phone contactsfor additional consultants and contractors who may berequested to provide technical assistance to the emergencyorganization'.

In case of a radiation event, the Emergency Coordinatorhas the authority to procure the services of any consul-tant group he may feel is needed. Rochester Gas &

Electric as part of the Institute of Nuclear PowerOperations (INPO) can call upon 1NPO reeaurces tosupplement RG&E efforts in executing emergency responseplans. Support may be requested directly from utilitiesand service companies listed in the INPO EmergencyResources Manual or may be obtained by using INPO as anagent to arrange and coordinate the required support.RG&E also has agreements vith Nev York State utilitiesfor mutual assistance in times of emergency.

Revision 9 November 1990

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38

4

There are two radiochemical laboratories at Ginna. oneia adjacent to the controlled area and is used for primarycoolant and other plant samples.

The second laboratory is used for environmental samplesand is located in the Ginna Training Center East, remotefrom the plant. This laboratory duplicates the mainlaboratory equipment and could be used for diluted postaccident samples if needed. Zt would most likely remainat a lower background level.The laboratory at James A. Pitzpatrick Nuclear PowerPlant of NYPA is available for analysis of samples. Thelaboratory is located about 45 miles distant nearFulton, NY.

Revision 9 Noveaber 1990

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The following sections provide the guidelines for theimplementing procedures of the five emergency categoriesdescribed in Section 3.0.

Rad atio Eme e c

A Local Radiation Emergency classification is establishedto provide a level of response to a radiological incidentwhich is less serious than the four Emergency Classifica-tions. It has no effect offsite and has no potentialfor any offsite effects. There is normally no notifica-„tion or actions required by offsite agencies."

a) Any individual aware of an incident shall notifythe Control Room of this fact.

b) The licensed Reactor Operator shall announce overthe Plant P.A. System that a local evacuation ofthe area is required.

c) All personnel in the affected area shall reportto the Lunch Room in the Service Building afterbeing monitored for contamination.

0 -Dut Shift Su e so :

The on-duty Shift Supervisor shall:a) Report to Control Room.

b) Evaluate plant conditions by checking readingsof all control system measured paraaeters andradiation monitors and evaluate any surveys taken.

c) Dispatch a Survey Team (Health Physics Techniciansor Auxiliary Operators) to conduct both in-plantand area surveys as necessary who should:

l. Isolate the affected area (rope barriers if neces-sary).

2. Determine cause of accident and restore conditionsin'the area to normal if possible.

d) Inform the Plant Manager or his alternate and theDuty Engineer.

Revision 9 November 1990

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5 '.2 so e e

The plant Manager, the Duty Engineer and Health physicistwill, if onsite, evaluate the situation and determinethe course of action.

Non-operating personnel in the affected area who are notcontaminated shall report to the Service Building LunchRoom for debriefing. Contaminated personnel shouldreport the Decontamination Area and proceed with decont-amination. Specific instructions are provided inadministrative radiation protection procedures. Ifemergency medical treatment is required, administrativeprocedures provide specific actions for such incidents.

Affected areas will be evacuated for local RadiationEmergencies by making an announcement to clear thoseareas. Upon assessment of plant conditions, the EmergencyCoordinator may determine that the plant is safe forpersonnel to return to normal duties.

5 ' ~ 3 s ent 0 ~

The Shift Supervisor and/or the Plant Manager shalldetermine the course of action to be taken to clean upthe affected area, correct the cause of the accident andreturn the area to normal operation. State and countyauthorities may be notified of the incident for informa-tional purposes but no actions are required off-site.Management will be notified and the Plant OperationReview Committee shall review the accident and recommendactions to prevent its recurrence.

5.2 u Eve t:The purpose for the Unusual Event. classification is toprovide early warning of minor events which could leadto more serious consequences. The Unusual Event condit-ions indicate a potential degradation oi the level, ofsafety of the plant. No releases of radioactive materialrequiring offsite response or monitoring are expectedunless further degradation of safety systems occurs.Declaring an Unusual Event assures that the first stepfor any response later found to be necessary has beencarried out by bringing onsite staff and offsiteorganizations to a state of readiness, thereby providinga system for handling information and decision making.

Revision 9 Noveabor 1990

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The NRC; state and county authorities will be promptlynotified to assure that the first step of any necessary. response can .be initiated. Plant Manager and the DutyEngineer will be notified of the Unusual Event Emergencyto bring the plant staff to a state of readiness andprovide for responsible decision making. On-shiftresources can be augmented so as to be able to assessand respond as needed. Offsite organizations will standby for further information or closeout.

5 '

Events of the Alert classification involve actual orpotential degradation of the level of 'safety of theplant. Any radioactivity released would result inexposures only a small fraction of the guidelines forrequired offsite action. By assuring that emergencypersonnel are available to respond if the situationshould become worse, protective. actions could be takenmuch quicker, such as, performing confirmatory radiationmonitoring and providing offsite authorities withcurrent status information.for events which fall in the Alert classification, GinnaStation will promptly notify the NRC, state and countyauthorities of the Alert status and the reasons for theclassification. The Technical Support Center vill bemanned so as to assist in the assessment of the incidentand determination of a proper response. Periodic plantstatus updates will b» given to offsite authorities, vhowill also be advised of any change in the classificationof the incident. The EOF will not necessarily be mannedat this level but the EOF Organization may be put onstandby so as to be ready if the condition degrades.

offsita agencies will activate primary response centersto stand by status and will alert other key emergencypersonnel, such as monitoring teams and communicationscenters, Emergency Broadcast System, or law enforcement.They will be ready to escalate to a more severe classifi-

. cation ii appropriate.

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ROCHESTER GAS AND cLPCTRIC CORPORATION

GINNA NOTIFICATION PROCESS

CONTROLROOM

EMERGENCYCOORDINATOR

SECURITY(ONSITE)

GASDISPATCHER

TELEPHONESERVICE

RECOVERYMANAGER

SECURITY(OFFSITE)

MANAGEMENTDOSE

ASSESSMENT

NUCLEAROPERATIONS

MANAGERCORPORATE

SPOKESPERSON

ENGINEERINGSUPPORT

OPERATIONSASSESSMENT

TECHNICALASSESSMENT

MAINTENANCEASSESSMENT

COMMUNICATIONS

SURVEY CENTER

MANAGER

HEALTH PHYSICS/CHEMISTRY

HEALTH PHYSICSlTECHNICIANS

CORPORATENUCLEAR

EMERGENCYPLANNER

FACILITIES ANDPERSONNEL

OFFSITE AGENCYLIAISON

ADVISORYSUPPORT

EOF DOSE

ASSESSMENT

NEWS CENTERMANAGER

TECHLIAISON

EOC TECHREPS

COMMUNICATIONS

SEC, REC. MANAGER

ADMINISTRATIVEASSISTANT

RECEPTIONIST

COMMUNICATORS FAX OPERATIONS

PLANT COMPUTEROPERATORS

STATUS BOARDKEEPERS

COPIEROPERATIONS

COURIERS

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A Site Area Emergency is declared when events are inprogress or have occurred which involve actual or likelyma)or failures of plant functions needed for the protec-tion of the public. Any releases are not expected toexceed EPA Protective Action Guideline exposure levelsexcept near the site boundary.

In the event that a Site Area Emergency is declared, theactions to be taken by various plant groups are detailedin the implementing procedures for the Plant. TheControl Room will make the initial notification to theNRC, state and county authorities.The purpose of the declaration of a Site Area Emergency'is to assure that personnel required for evacuation ofnear-site areas are at their duty stations if such anevacuation is called for. Also offsite agency authoritieswill be available at primary response centers forconsultation and updates on the situation, and toprovide information to the public.

to o Emerec 0 a tEmergency procedures necessary to cope with the plantsystem malfunction will be implemented. All on-dutyoperations personnel will report to the Control Room.Control Room ventilation dampers will be switched fromoutside to inside air and the charcoal filters will beput into service. Communications will be established byensuring that the emergency radio remote/local switch isin the local position and by plugging in the intercomfor communications with the Emergency Centers as backupfor the phone system. Plant staff will be notified asspecified in the implementing procedures. This seriesof calls is arranged in order of importance and willactivate the Emergency Organization.

Unless they are already in the plant, persons so notifi'edwill report to the Survey Center where )obs are assignedin line with the trained capabilities of the individual.Procedures provide for manning the Technical SupportCenter, the Survey Center and the Operational SupportCenter. The Recovery organization will be activated atthe offsite Emergency Operations Facility. Figure 5.1shows the notification scheme.

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,The plant guards assist in the activation of the plan asfollows: One guard shall deliver the log sheets, extrakeys and radios to the Survey Center. He will unlockthe Training. Center if necessary, report his arrivalthere to the Control Room by radio and direct allnon-essential personnel to the auditorium.

One guard shall proceed with his radio to the Plantentrance at Lake Road and report his arrival there tothe Control Room by radio. He shall direct any trafficenroute to the Plant to the Training Center instead andremain at the Lake Road entrance until released by theEmergency Coordinator. One other guard shall remain inthe Guard House to instruct all plant personnel leavingthe plant to retain their TLD's and standby in theTraining Center until released. After all personnel,except operating personnel, have cleared the plantrestricted area, the guard shall lock the Guard Houseentrance and remain in the Secondary Alara Station.The Plant Guards will stop all visitors and their vehiclesfrom entering the site until the Emergency Coordinatoror his designee notifies them that the condition hasbeen corrected.

1th h s csthe Emergency CoordinatorDuring working hours heTechnical Support Center.personnel will:

st a shall assistin evaluating the emergency.will report directly to theOther Health Physics section

a) Pick up extra survey instruments from the HealthPhysics office.

b) Pick up RWP and SWP Auxiliary Building and Contain-ment sign in sheets.

c) Report to Training Center Basement and pick upnumbered tags or assume responsibilities aa statedin the implementing procedures.

d) One Health Physicist will report to the TechnicalSupport Center.

During off-duty hours the Health Physicists and techni-cians shall report to the Survey Center and pick upnumbered tags or assignments as stated in the implem»enting procedures. The Health Physics technician onshift shall report to Control Room and aisiat aa deemednecessary by the Shift Supervisor.

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t Perso n , upon notification, shall report tothe Survey Center and pick up duty tags and TLD's. Theyshall assist the Emergency Coordinator and the on-dutyShift Supervisor as necessary.

te Assessme t:'Zhe Shift Supervisor shall immediately assess theincident. The Shift Supervisor is responsible for theimplementation of the Emergency Plan until relieved.The Shift Supervisor shall report to the Control Room,evaluate plant conditions by quickly checking the statusof control and safeguards systems, and radiation mon-itors. He shall ensure a call is made to the New YorkState warning point, Albany, New York and give thefollowing information:

a) Name of facility and communicator

b) Date/time oi incident

c) Class of Emergency (Unusual Event, Alert, Site AreaEmergency, General Emergency)

d) Brief Description of Event

e) Radioactive Material Release (None, Atmospheric,Ground, Lake)

i) Protective Actions .Recommended for appropriatepopulation

g) Winds and weather

The Wayne County Office of Emergency Management and MonroeCounty Office of Emergency Preparedness will be notifiedat the same time thru the use of the state hotline. Anemergency communicator is part of each shift and willmaintain contact with NRC, NY State and the Counties.As the hotline is a closed system, call back verificationby the state and counties is not necessary.

Zf necessary, the Shift Supervisor shall issue radiationprotection equipment and dispatch a survey team toconduct in-plant or area surveys. A. relief schedulewill be determined if it is necessary. (See RadiationProtection During an Emergency, Section 5.4.4.1).

Revision 9 November 1990

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etAtTo ensure that immediate and direct action shall betaken in an emergency situation both the TechnicalSupport Center and Survey Center will be manned. Detailsfor manning are in implementing procedures. During normalworking hours individuals assigned to the TechnicalSupport Center will go there directly. Others assignedto the Survey Center will report there.

During off-duty hours, upon notification of an emergencythrough the call procedure, personnel may report to theTSC using normal procedures or they may be directed tothe Survey Center. At the Survey Center a large tagboard displays a series of tags with written instructionsto. ensure that each person knows exactly what to do andin what order. As personnel arrive at the Survey Centereach shall obtain an instruction tag in sequence exceptas detailed in the implementing procedures or as directedby the Emergency Coordinator. The first qualified staffmember shall be Survey Center Manager. When the PlantManager, one of the Superintendents or other qualifiedindividual arrives, he shall assume the responsibilitiesoi Emergency Coordinator.

The Emergency Coordinator shall assume responsibilityfor the plant and Emergency Centers and establishcontact with the Control Room over the direct intercom,the plant intercom system or by telephone. The EmergencyCoordinator will request from the an-duty Shift Supervisoran evaluation of plant conditions and all data which havebeen relayed to the State. Meteorological conditionswill be obtained from weather instrument readouts in theControl Room and X/Q overlays will be selected todetermine maximum concentration points. The EmergencyCoordinator or Survey Center Manager will dispatchoffsite monitoring teams to areas of interest and regnesteach team to report by telephone or radio. Survey teamsshall not receive a whole body dose greater than 1 Remwithout special permission from the Emergency Coordinatoror Dose Assessment.

Revision 9 Novtaber 1990

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The Emergency Coordinator will report the accident andcurrent conditions to Company management as specified inthe implementing procedure. Knowledgeable individualsvill be assigned as the RGEE Technical Liaisons at theState and County Emergency Operating Centers.

The Emergency Coordinator will evaluate radiologicaldata from the survey teams and plant parameters. Currentconditions and follow-up actions will be reported tomanagement periodically. The State Bureau of RadiologicalHealth, Monroe County and Wayne County Directors ofEmergency Management will be kept advised of changingconditions.Follow-up messages to offsite authorities will containthe following information as appropriate:

a) Location, name oi callerb) Class of emergency and date and time of incident

c) 'ype of actual or pro)ected release, estimatedduration and impact time.

d) Estimated quantity of release for various materials

e) Chemical and physical form of release material(noble gases, iodine, particulate)

f) Current weather conditions

g) Actual or pro)ected dose rate and time integrateddose at site boundary

h) Projected dose rate and integrated doses in affectedsectors

i) Estimation of any surface radioactive contamination

g) Recommended emergency response actions or protectivemeasures

k) Prognosis ior course of the event

1) Status of in»plant emergency control actions, andlicensee response to actions underway

m) Request for further support

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The Emergency Medical Plan will be instituted if neces-sary. The Shift Supervisor shall be provided with

any'urveydata necessary for him to meet his responsibili-ties.The Emergency Coordinator will determine if additionalpersonnel should be called to the plant to cope withemergency conditions.

Personnel and cars shall be monitored and surveyed toassess the extent of contamination before leaving thesite. All non-essential personnel should be allowed toleave the site.

5.4 ' 0 s te P otect v Act ons:

During any radiological emergency, protective actionswill be employed as follows:5 ' gal t o rote o a e e

During a radiological emergency, precautions and limita-tions to minimize doses shall be observed by personnelentering an incident area. Zn general, doses will belimited to normal exposure limits. Every effort shallbe made to keep exposure to a minimum while accomplishingthe necessary tasks. Radiation exposures in an emergencyshall be evaluated on an ALARA basis. Survey teams arelimited to l Rem dose during the incident unless specialpermission is given by the. Emergency Coordinator or DoseAssessment.

For life saving actions such as the removal of an injuredperson and providing first aid, ambulance service,medical treatment other actions recgxired to reducesevere health effects to the public, volunteers mayreceive up to 75 Rem whole body exposure. The limit setfor performing assessment actions or undertaking correc-tive actions to prevent substantial radiological releasesis 25 Rem. Authorization to receive these high dosescan be given only by the Emergency Coordinator.

All entries into high radiation areas must be carefullyplanned from available survey data, review of personnelcurrent exposure records, and pre-planning of theactivities to be accomplished. Whenever entering anincident area, high range survey instruments and personnelmonitoring devices shall be employed, protective clothingand self-contained breathing apparatus shall be worn andsurvey teams will consist of at least two persons. TheEmergency Coordinator shall be notified before anysurvey team enters an incident area and close communica-tions shall be maintained as much as possible.

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The radiation program during an emergency will be basedon the program as laid out in the HP series of proce-dures. Dosimeters and film badges are available in theSurvey Center for the survey teams. Provisions forround-the-clock capability to issue dosimeters andmaintain dose records will be established to meet longterm needs of the plant procedures. The capability toread TLDs will be used to maintain control of individualdoses.

kLThe instructions for restricted area evacuation are speci-fied in the implementing procedures. In general, theprocedures provide that:Any licensed Reactor Operator may sound the evacuationalarm (special tone) if evacuation of the plant isdeemed advisable.

Upon becoming aware of the evacuation alarm all personnel,except those whose duties during an emergency specifyotherwise, shall immediately leave their area of work bythe nearest exit. Auxiliary Building exits (south andeast) to the outdoors may be used. Shoe covers shouldbe removed. Personnel will walk to the Assembly Areaand stand by for further instructions. All film badgesand dosimeters will be retained by the individual.The "Assembly Area" refers to the Training Center or.alternate location depending on plume direction andhabitability considerations. Alternate locations mayinclude onsite buildings out of the plume (eg. Pro5ectsBuilding) or other offsite RG&E facilities.The guide accompanying any visitors is responsible tosee that visitors are taken to the Assembly Area. Otherpersonnel who may be on-site outside the restricted areawould hear the site evacuation signal. One siren of theERPA - Wayne 1 is located on-site and would warn theseworkers when the general population is alerted.After evacuation of the plant areas, an accounting willbo made of all personnel who were on site. Accoun»tability of personnel is carried out by plant securityusing the "Onsite» computer list to determine that allpersons are accounted for. A check with Control Room,Technical Support Center, and Operations Support Centerdetermines who is at those locations. Drills haveindicated that this procedure can be completed within 30.minutes. This procedure is verified to be ceaplete bythe Emergency Coordinator using his check list.

Revision 9 Noveaber 1990

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Cars will be monitored and surveyed as necessary beforethey are allowed to leave the site. Personnel leaving the~ite will take a route selected by the Emergency Coordin-ator, after consultation with the Wayne County EmergencyOperations Center giving consideration to the winddirection or road impediments. (See Figure 5.2) Beforeleaving, persons will be monitored for contamination andfilm badges collected.

Normally private cars would be used for leaving thesite. Zn case cars are contaminated, buses will bebrought in for the evacuation. The Emergency Coordinatorwill advise the Wayne County Emergency Director of thepersonnel, vehicles and evacuation routes which will beusedo

e c e c tAll emergency medical treatment will be carried outusing an emergency medical treatment plan. This planspec3,iies the types of medical action to be taken in anytype of radiation or contamination emergency. First aidteam members maintain their proficiency through RedCross First Aid Training.EPZP 2-9 provides guidelines for the administration anduse of potassium iodide (KZ) for onsite personnel andsurvey teams. The determination 'of need for KZ is theresponsibility of the Dose Assessment Manager or HealthPhysics and Chemistry Manager. Approval of the EmergencyCoordinator is required.

Radio-protective drugs will be issued for the generalpublic only if approved by the New York State Departmentof Health.

S a and Res

Following site evacuation all personnel will be accountedfor using security records, sign-in sheets, log sheets,etc. The Emergency Coordinator will determine thenecessity for a search and rescue operation. Such anoperation will be coordinated by the Shift Supervisorand the Emergency Coordinator.

The search and rescue team will consist of at leastthree persons including Security, Health Physics and aperson who knows the missing individual.The search should start at the'ast known location or workassignment of the unaccounted-for individual. Radiationsurveys should be made as the team progresses. It maybe necessary to administer first aid to the individualafter he is located. The Emergency Coordinator orControl Room shall be advised of the situation.

Revision 9 Noveaber 1990

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5.4 ' ' m atoA Health Physics procedure (HP-6.3 "Personnel Decontamina-tion~) provides guidance for graduated measures to beused for decontamination. The ob)ective of decontamina-tion is to prevent the spread of radioactive material onthe individual, to the environment, or to other personneland to reduce the resultant dose. Decontamination isessentially the removal of radioactive material and isperformed starting with the highest level of contaminationusing the simplest procedures. Continued decontaminationmay show diminishing effectiveness and require a decisionto stop or use more potent agents.

Decontamination kits which contain items to decontaminatethe skin, for wound cleansing and nose irrigation areavailable. Decontamination should continue until it. isno longer effective but not so as to abrade skin. Thisprocedure should be effective against Iodine and othercontaminants.

Ii personnel cannot be decontaminated to the limits ofProcedure HP-6. 3, Radiation Management Consultants * maybe contacted.

Instruments are available to determine contaminationlevels of personnel or equipment and the effectivenessof decontamination. Waste drums are available ascontainers for radioactive waste and emergency clothingis available if needed.

5 ' 4~6

Offsite authorities will provide assistance as needed toprotect the public. In the event a Site Area Emergencyis declared this may include activating the publicnotification system and providing information and periodicupdates of the situation through the EBS (EmergencyBroadcast System) and/or press briefings. Resources atprimary response centers will be augmented by callingother emergency services to stand by status and dispatc-hing certain emergency personnel to initiate theirfunctions, ie, monitoring and communications. Informationfrom the licensee, monitoring teams and weather stationsvill be continually evaluated with regard to changes inprotective actions already initiated for the public,such as sheltering of people or milk animals. Monitor-ing results and any actions taken should be reported tothe licensee and others having a need to know.

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5.5

The General Emergency willbe declared when the conditionsdescribed in Section 3.5 exists.The purpose of the General Emergency declaration is to(1) initiate protective actions for the public aspredetermined or as indicated by actual releases, (2)provide continuous assessment of information from GinnaStation and offsite measurements, (3) provide consulta-tion with offsite authorities, and (4) keep the publicinformed thru updates of the situation through the JointEmergency News Center.

5 '.1 tos:A General Emergency requires that all actions prescribedfor the Site Area Emergency (See Section 5.4) be imple-mented. The NRC, State Bureau of Radiological Health,and county authorities who will already have beencontacted for lower classifications, will now be updated.

The Emergency Coordinator may request the assistance ofoffsite groups which could include Radiation ManagementConsultants, plant doctors, and Department of Energy-Brookhaven Radiation Assistance Program. Technicalpersonnel from other RGSE departments and/or consultantswill be called as needed.,

The Emergency Coordinator has the responsibility todetermine the magnitude and extent of the incident byevaluating information from the Control Room and theSurvey Teams. This information will consist of instrum-entation readings and any survey results available. Heshall update the state and local authorities with newsurvey data and other information and recommend protectiveactions. Protective action will be based on the "Manualof Protective Action Guides and Protective Action forNuclear Incidents" EPA-520/1-75-001-A, January 1990,U.S. Environmental Protection Agency. A summary ofrecommended actions is presented in Table 5.1.

In making his recommendation for sheltering or evacuation,the Emergency Coordinator should evaluate the weatherforecast in relation to changing winds and precipitation.he should also evaluate the calculated evacuation times(Appendix G) in relation to predicted start, length andtermination of a release. Due to the nature of ourclimate and corresponding construction of dwellings, theshielding effects of sheltering are greater than in manyother areas. A dose reduction factor of 0.6 - 0.9 isassumed for residences in this area for whole body directplume radiation.(1, 2)

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The Director of the New York State Bureau of RadiologicalHaalth shall determine, by evaluating the informationgiven by the Emergency Coordinator (or EOF/RecoveryManager as appropriate) if area evacuation is necessary,to what extent, and how to undertake protective actionincluding evacuation. A pro)ection of populationdistribution in the 10 mile plume exposure zone isincluded in Appendix F.

All survey and sample analysis results will be retainedby the Health Physics and Chemistry Manager for appropri-ate documentation. Formal reports shall be written anddistributed as required by 10CFR20 and the TechnicalSpecifications. Information concerning the offsite con-sequences of the incident and protective actions toprotect the public will be handled by'ew o k State

diplo ical Emer enc la and County Emergency Plans.An RG&E Corporate Spokesperson in the JENC will releasethe information concerning the plant, plant safeguardsand its employees,- and assistance being provided toState and Local authorities.

5.5 ' 0 s te Aut orities ct o s:

5 '

All actions of paragraph 5.4.4.6 for Site Area Emergencywill be reviewed and enacted for a General Emergency. Allemergency personnel will have been activated and allresponse centers are operating. Information ia evaluatedand passed to the proper authorities and the public.Protective actions will be instituted as needed for thepublic and animals.

o ease tIf a ma)or release to the lake occurs which exceeds theTechnical Specification limit or the limiting concen-trations specified in 10CFR20, Appendix B, Table II,Column 2, at the point of discharge the following actionsshall be taken:

The release will be classified per EPIP 1-0, "GinnaStation Event Evaluation and Classification" and appropri-ate notifications .will be made, if necessary, per theclassification and corresponding procedurea. The OntarioWater District will be notified. The waste dischargewill be isolated, grab samples will be obtained, anddilution will be estimated.

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The Health Physics section will be instructed to monitorthe Ontario Water District Station water.

(1) Reference: "Public Protection Strategies for potentialNuclear Reactor Accidents" Sheltering Concepts withExisting Public and Private Structures" (SAND 77-1725),Sandia Laboratory.

(2) Protective Action Evaluation Part II, Evacuation andSheltering as Protective Actions Against Nuclear AccidentsInvolving Gaseous Releases" (EPA 520/1-78-001B). U. S.Environmental Protection Agency.

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TABLE 5.1 Recommended protective Actions to Reduce Vhole Body and Thyroid Dose from Exposure to ~ Gaseous PLume(EPA 520/1-75-001 ' January 1990)

Projected Dose (Rem)to the population )

IVhole body «1

I

I

Thyroid «5

I

Recommended Actions (a)

No planned protective actions. (b)State may issue an advisory to seek shelterinstructions.Monitor environmental radiation Levels.

Iand auait further(

I

Comments

Previously recommended protectiveactions may be reconsidered orterminated.

LOpoO.

pf~lL)

890't$

~ Q~ 0

Vhole body 1 to «5

I

I

Thyroid 6 to «25

I

I

)Vhole body 5 and above)I I

)Thyroid 25 and above)I

Projected Dose (Rem)to Emergency TeamVorkers'

I

Vhole body 25

I

ThyroidI

I

Vhole bodyI

I

I

Seek shelter as a minimum.Consider evacuation. Evacuate unless constraints make itimpractical'lonitor environmental radiation levels and adjust area formandatory evacuation baaed on these Levels. Control access.

Conduct mandatory evacuation.Nonitor environmental radiation Levels and adjust area formandatory evacuation based on these Levels. Control access.

Control exposure of emergency team members to these levelsexcept for Lifesaving missions. (Appropriate controls foremergency uorkers,.include time Limitations, respirators,and stable iodine).

Control exposure of emergency team members performingLifesaving ~ issions to this level. (Control of time ofexposure QLLL be most ~ ff~ ctive.)

lf constraints exist, specialconsideration should be given forevacuation of children andpregnant uomen.

Seeking shelter uould be an I~ Lternative if evacuation were not)immediately possible. I

Although respirators should beused where effective to controldose to emergency team workers,thyroid dose may not be a Limiting)factor for lifesaving missions.

( ~ ) these sct>ons ~ re recommended for planning purposes. Protective action decisionstrike existing conditions into consideration.

at the time of the incident must

(b) At the time of the incident, officials may implement Lou-impact protective actionsmaintaining radiation exposures as Lou as reasonable achievable.

in keeping with the principle of

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1

I

I

~ I

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57

5.7 e t o

Public information willbe released by an RG&E InformationOfficer operating from the Joint Emergency News Center.Public Information personnel will be assisted by aTechnical Spokesman who keeps in touch with the EmergencyCoordinator and EOF operations. RG&E personnel willexchange information with government Public Information

" Officers on a timely basis. All news releases will becoordinated among Federal, State, County and RG&E sources.

Rochester Gas & Electric Corporation Public RelationsDepartment will be notified of any activation of thisplan as soon as practical. Generally this notice willbe from the Emergency Coordinator after he has compiledhis evaluation of the situation.A Joint Emergency News Center (6.1.7) will be establishedwhich may be activated during a nuclear emergency. Itcan be activated for the Alert Class or a less severeevent. The Emergency Plan Implementing Proceduresprovide for staffing this center and outlines the dutiesoi various positions. Individuals who are qualified toassume those positions are designated. Space is allocatedin the Joint Emergency News Center ior the use ofvarious regulatory and government officials so as tocoordinate and facilitate the flow of accurate informationto the public. A Corporate Spokesperson who has accessto the EOF will be available to the news media forbriefing and questions.

Inf'ormation concerning the status of the plant employeesand Public Safety Recommendations shall be released bythe Public Inf'ormation Officers representing RG&E andlocal, state, and federal governments.

A public information program to acquaint the public withthe proper actions to be taken in the event of a nuclearemergency at Ginna Station will be provided on an annualbasis. This program will include information aboutradiation, protective actions which can bo taken,suggested evacuation routes, special needs of thehandicapped, proper responses to warning signals, andwhere additional information can be obtained. Theprogram will be coordinated with RG&E, State and CountyOfficials.Material for placement in parks, motels and retailestablishments to which transients have access vill beprovided on an annual basis.

'evision 8 October 1989

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y vW

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58

An annual briefing and training session will be held toacquaint the news media with our emergency plans.Xnformation on plant operation, radiation effects andconcerns, the implementation of our emergency plan/points of contact for the release of public informationat RQSE and other relevant topics will be kept currentthrough these sessions.

Figure 5.7 is a preformatted press statement which canbe used to inform the public of the situation at Ginna.

Revision 8 October 1989

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,„~ce

'I

'l»

I>

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59

PRESS STATEMENT RtVZSC 7-28-89

JtOCHES TEIt G1$ 4HD ELEC rffIC~ 1 te$ 1'svlsvt 4OCwlStlI V «Jest ~ <we .! 'VO

DATE'ot.R:

ROCHESTER'Y ROCHESTER GAS AND ELECTRIC CORPORATION REPORTED

ANO (ALERT) (SITE EHERGENCY) (GENERAL EMERGENCY) AT ZTS SINNA

NUCLEAR STATION LOCATED IN THI TOMN OF ONTARIO'AYNES COUNTYt NaW

YORK'l6 MILES EAST OF ROCHESTER ON LAKI ONTARIO AT (TZNl) ON

(DATj) .

PRELIMINARY INFORMATION INDICATE5 (GIVE NATURE OF PROILEH) ~

THE STATU5 OF THI STATZON ZS (STAILK) (IMPROVING) (DEGRADING)

(NOT KKOMN) ~

A RILIASI OF RADIOACTIVITY (IS) (I5 NOT) TAKING PLACI.

(PROVZDC SPICZFZC INFORNATZON If RELEASE Z5 TAKZNG PLACI.)

ADDITIONAL DETAILS MILL II PROVIDED AS AVAZLAILR (IF PRl5$

IRIEFZNGS HAVR IEEN SCHEDULED'ROVIDE 5CHEDULE AND LOCATION) ~

THIS. {IS) {IS NOT) A DRILl.

NtfFigure 5.7

KXNIIITiRevision 8 October 1989

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4AJy,

(~

~&

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60

6 ~ 0

Emergency facilities comprise a number of categoriesincluding emergency response facilities,'ommunicationssystems, assessment facilities, protective facilitiesand first aid and medical facilities. Each is brieflydescribed as follows:

F 1 Emer enc Res onse Facilities G&E

Locations have been designated to be used for evaluationand control of an emergency situation; the Control Room,the Survey Center, the Technical Support Center, Opera-tions Support Center, Emergency Operations Facility,Engineering Support Center and the Joint Emergency NewsCenter. Figure 6.1 shows the relationship of theseCenters during an emergency.

6.1.1 o Room'

).2

The Ginna Station Control Room is designed for continuousoccupancy following the most limiting accident; therefore,control of plant systems will take place from thiscenter, and on-shift crew activities relating to mitiga-ting the consequences of the accident will be initiatedand coordinated by the on-duty Shift Supervisor in theControl Room. Equipment for radiation monitoring andprotective clothing and respiratory equipment is kept inan emergency cabinet.

Ce te C

The basement of the Ginna Training Center will be usedas dispatching center for survey teams. Their equipmentwill be stored in lockers so that availability ofequipment is assured. All field monitoring data vill bereported 'through a communicator to the TSC or EOF DoseAssessment Manager as appropriate. The Dose AssessmentManager will evaluate the data and make protectiveaction recommendation if needed.

Revision 9 Noveaber 1990

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a p

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ROCHESTER GAS AND ELECTRIC CORPORATION

GINNASTATION EMERGENCY CENTER INTERFACES

CONTROL ROOM

OPERATIONALSUPPORTCENTER

TECHNICALSUPPORT .

CENTER

NRCSTATE

EOCCOUNTY

EOC'S

SURVEYCENTER

EMERGENCYOPERATIONS

FAOLITY

ENGINEERINGSUPPORTCENTER

nOD'

INITIALCONTACT ONLY--

)OINTEMERGENCY

NEWS CENTER

figure 6.1t

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Ai

4

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I

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62

t Surve e ta ea:

An alternate Survey Team Staging Area will be designatedby the Emergency Coordinator if the SC is not habitablebecause of high radiation levels or airborne contaminationlevels. Alternate Survey Team Staging Areas may includethe onsite Prospects Building or other offsite RG&Efacilities.Te h ica Su ort enter TSC

An area at the east end of Ginna Station Turbine Buildinghas been constructed for use as the TSC. Zt is equippedwith an intercom for direct communication with theControl Room, Survey Center, and Operational SupportCenter. The TSC also has direct phone lines to the NRC,New York State, Monroe and Wayne Counties as well asradios and normal phones. A terminal to the plant processcomputer data link is installed in the Center forobtaining plant operational data. Piping and equipmentdrawings are also available. A radiation monitor ismounted in the Technical Support Center. The center hasfiltered air supply and is shielded to meet the samehabitability requirements as the Control Room. Aconstant air monitor is installed to indicate theactivity of airborne particulate., This center meets thecriteria of NUREG 0696 and is within 2 minutes walkingtime of the Contxol Room. Protective clothing andbreathing apparatus are available if needed.

0 e tional Su ort Ce te C

An area within the TSC has been designated as the OSC.Personnel will be assigned to this area in case of anemergency who are capable of giving support to operationalneeds of the plant. They will be directed from theControl Room or the TSC. Phones and the plant GAI-tronics page are available.This area was selected for its capacity to provide anadequate assembly area for operators, technicians, andrepairmen. Personnel designated by implementing proced-ures will report to the OSC, either directly if alreadyon site or through"the Survey Center if called in fromoff-hours. The OSC meets the criteria of NUREG - 0696.Supplies provided at'his center include respiratoryprotection equipment, protective clothing, portablelighting and portable radios.

Revision 9 November 1990

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~,

Pt, i

II

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63

Potassium Iodide tablets and self-reading pocket dosi-meters are included in the equipment stored in the OSC.Radiation monitoring equipment for surveys of the OSC orfor use out on a )ob is available in the TSC or asdedicated equipment in the Health Physic's office.Emergency equipment necessary to repair, control ormitigate the consequences of an accident are availablein shops and the stockroom within the plant.

c 0 e t o s aci tThe EOF has been established offsite ad)acent to RG&EHeadquarters in Rochester. This facility meets thecriteria of NUREG-0696. Offices will be provided forFederal, State, and Local Officials. In addition,sufficient offices for RG&E support personnel and backupgroups (such as Westinghouse, Gilbert Commonwealth,etc.) is available in the same building. A work areasized to accommodate the numbers of people anticipatedand the facilities for these people will also be in-corporated into the complex. Facilities are providedfor the news media and RG&E public relations personnelin the headquarters building.Ample telephone communications will be provided, withdegrees of redundancy achieved by utilizing the RochesterTelephone system in conjunction with the New YorkTelephone system. Also a microwave system providescommunication capability between Technical Support Centerand the EOF.

To aid in emergency assessment, pertinent information(such as blue prints, UFSAR, Technical Specifications,etc.) are stored at the facility and will be keptcurrent. A data link will provide hard copy informationfrom the plant computer to the EOF. This information isprogrammed into groups of various essential plant andsite parameters required for emergency evaluation. Asthe emergency is evaluated, accurate and up-to-dateinformation of the situation is relayed to appropriategovernmental agencies and the public through this Center.

Communications equipment and radiation monitoringequipment for use by field teams from the EOF is main-tained and readily available to them.

J e en News Cente JENC

A JENC has been established in con)unction with theEOF. The center will house offices for the NRC, FEMA,NYS, Wayne and Monroe County, and RG&E Public InformationOfficers. It will also have facilities for pressbriefing, small conference rooms, General Informationand Rumor Control, and Security.

Revision 9 November 1990

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~

'I

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64

Basic information regarding the status of the GinnaNuclear Power Plant will come from the Emergency Coordi-nator. After review by RG&E corporate personnel, n e w sreleases will be issued from the Emergency News Center.A telephone center for response to the general publicwill be established and the RG&E Government RelationsDepartment will be in contact with elected officials.See EPZP 4-4 and 4-6 for details.

6 '

6 ~ 2 ~ 1

Commu ications S stems: (Ginna Station)

A broad range of communications equipment is availableat Ginna Station. Several systems are installed forcommunications between RG&E Emergency Centers, and forcommunications with outside agencies. Equipment isperiodically verified operable by plant procedure. Theuse of particular types are specified in the appropriateimplementing procedures as first choice and backupsystems. All services other than radio are undergroundbetween centers. Communications'ystems are testedperiodically.

a atio Wa inA special warbling tone on the GAZ-Tronica page systemis sounded from the Control Room to warn personnel of asite evacuation. Warning is immediate to all personson-site at the time of an accident. High noise areashave, in addition to the Public Address system, redwarning lights with signs to direct personnel to evacua-te. Special .announcements on the page and special tonesare used for other emergencies.

6 ' ' s

Communications between the Control Room, TechnicalSupport Center, Survey Center and other operationscenters can be established using either telephone, 2-wayintercom, radio or plant PA System. Coamnicationssystems are tested periodically according to the schedulein implementing procedure.

The AT&T System 75. telephone system at,Ginna affords agreat deal of flexibility and capacity. Calls can bereceived or made to either the Rochester TelephoneSystem or the Ontario System (New York Telephone Co.).The AT&T system has its own power supply located on-sitewhich could maintain house phones independent ofoff-site lines. There are also Rochester direct linesthat are powered by Rochester Telephone and Ontario.direct lines powered by New York Telephone. During anemergency phone usage can be controlled by an operatorat the console located in the Technical Support Center.

Revision 9 November 1990

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65

In case of an emergency,- personnel not at the plant canbe summoned using either the AT&T phones or direct linesto the Ontario and Rochester Systems; If necessary,Control Room personnel may use the direct lines to aRochester located dispatcher who would then make thenecessary offsite calls. A base radio transmitter inthe Control Room may be used to call the Electric LineOperator who can also call personnel to the plant.

o S stems:

There are three frequencies available for use at GinnaStation. They are assigned to the Fire Brigade, Securityand Radiation Survey Teams. The base stations andantennae are located for maximum transmission coverageof the areas of use. The security channel is monitoredat Central Security and at the Guardhouse. The RadiationSurvey Teams have operator capability at the SurveyCenter, Technical Support Center and at the EmergencyOperations Facility. The Fire Brigade communicator willbe in the Control Room. Portable radios with threechannels are available for the use of survey teams inthe field.

t

The Ginna Control Room also has a receiving and broad-casting station on a frequency which is monitored off-siteby Electric Power Control and Line Maintenance. Thischannel is available for indirect communication to theState Police, Monroe and Wayne County Sheriffs and Wayneor Monroe County EOC's.

Portable low power hand radio sets are located in theTechnical Support Center to be distributed in the eventof an emergency for backup or mobile communication.Portable hand radio sets are also located in the SurveyCenter for the use of survey teams. Offsite surveyteams can communicate through these portable radio setsto a base station which may be set up at either theSurvey Center, Technical Support Center or EOF. Thebase station is capable of operating with l2 volt'Cpower (an automobile system) as an alternate power source.

Revision 9 Noveaber 1990

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66

6.2 ' 0 e

6 '

Notification to state and county emergency responseorganizations is available 24 hours per day. The StateWarning Point is staffed during normal working hours bythe Office of Disaster Preparedness. Monroe CountyOffice of Emergency Preparedness and Wayne County Officeof Emergency Management answer the RECS line during thework day. During non-business hours, weekends andholidays, the same phone line is covered for the Stateby the State Police Warning Point and for Monroe Countyat the Rochester Fire and Public Safety Building. ForWayne County the Sheriffs Office covers the warning systemduring off hours. At Ginna Station there are alwaysControl Room personnel to originate calls. New YorkState has responsibility for communications to other'counties which may fall within the ingestion pa thwayexposure zone. Any contacts with Canada or OntarioProvince would also be through the state agencies.

To contact appropriate offsite agencies the telephoneswould normally be used as above (6.2.2), with directlines or the dimension system. If necessary the PowerControl Dispatcher or Electric Line Operator may becontacted as described above and instructed to notifythe state police or sheriff and relay message throughtheir radio systems.

Communications with federal emergency response organi»zations consists of telephone contact to the Departmentof Energy Brookhaven Radiological Assistance Program.This call would be made by the Emergency Coordinator perour letter of agreement with Brookhaven. Their assistancemay also be requested by the State or counties.

NRC Emergency Notification System (ENS) "red phones" areinstalled in the Control Room, the EOF and the TechnicalSupport Center. NRC Health Physics Network phones arealso available in the Technical Support Center and EOF.

c iFacilities are provided for the assessment of postaccident radiological conditions in order to determinethe appropriate emergency measures. They consist ofonsite monitoring systems, laboratory facilities andenvironmental radiological monitoring and samplingequipment.

Revision 9 Noveabor 1990

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cess Radiatio tor S st m:

67

The process radiation monitoring system provides indi-cations and alarms which permit assessment of in-plantconditions, as well as providing certain automaticactuations. The general functions of these systems areas follows:

a) To indicate primary system leakage and fuel rodfailures.

b) To indicate radioactivity levels in selected processsystems.

c) To indicate radioactivity released through vents ordrains.

d) To provide visible and audible alarms in theControl Room when a significant increase inradiation occurs in systems or areas.

e) 'o alarm in the Control Room on monitoring equipmentfailure.f) To shut down a purge or a release if radioactivity

reaches the alarm setpoints and thereby avoidexceeding the discharge limits.

uent Monitors:

Effluent monitors available at Ginna are listed inTables 6.3A and 6.3B. Of these monitors, particularimportance is placed upon the plant vent monitors andliquid release monitor; the former because, as describedin Section 3.0, Emergency Conditions, in combinationwith other monitors, it indicates the need for siteevacuation and protective actions for the public; thelatter because it indicates the need for protectivemeasures with regard to the use of lake water.

Alarm setpoints are based upon the maximum allowableenvironmental radioactivity concentration and dose whichmight result from a release and set at a fraction ofthose values. Monitor calibration factors, correlatingmonitor readings and vent concentrations can be used toestimate the release rate. Prom vent concentrations,the offsite dose or concentration levels can be calcu-lated. Table 6.3A summarizes these monitors and alarmfunctions..Several approaches are available to supplement effluentmonitor readings for the assessment of release rates andpro)ected doses. Estimates of radioactive materialsreleased and pro)ected doses are provided for variousaccident categories and modes of safeguard equipmentoperation in an implementing procedure for the EmergencyCoordinator's use.

Revision 9 November 1990

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68

High range monitors have been established for theestimation of noble gas release from the plant ventilationexhaust point in the event that normal range effluentmonitors are off scale or inoperable. Periodic grabsamples of effluent release paths would also be used toquantify and further refine estimated releases from theplant. Table 6.3B summarizes the SPING 4 high rangemonitoring system.

Zf no release data are available, a method for assessmentof release rates is used in con)unction with the X/Q mapoverlays and offsite concentrations. The release rateof radio active material from the plant can be calculatedfrom the measured airborne concentration at a givendownwind sample location and the X/Q value for thatlocation read from the map overlay. The airborne concen-tration is divided by the X/Q value and multiplied bythe wind speed to obtain an estimated release rate fromthe plant.Appendix C, Table C-1 of this plan contains a table ofresultant doses and quantities released from selectedpotential accidents. These doses and releases are basedupon 104 of the values used as part of the plant safetyevaluation.

"Manual of Protection Actions Guides and ProtectiveActions for Nuclear Incidents" (EPA 520/1-75-001), NUREG133 (Nov. 78) and Regulatory Guide 1.109 Rev. 1 (Oct. 77)provide the methodology for relating radiologicalmeasurements in various environmental media or effluentmonitor readings to offsite dose or dose rates. Meteoro-logical conditions can be factored into these calcula-tions.A procedure for manually estimating offsite doses forareas around the plant is available at the TSC and EOF.Based upon these results, protective actions can berecommended. A computer program operating on a micro-computer is also available in the TSC and EOF. Thissystem mimics the overlay method of calculating downwinddose rates and airborne contamination levels. A moresophisticated computer program which uses the methodsused for environmental dose calculations required byFederal regulations is also available to assess dosesduring and after an emergency. Additional information onthe radiological consequences of a variety of accidentscan be found in Chapter 15 of the Ginna Updated FinalSafety Analysis Report..

Revision 9 November 1990

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RAD I AT I ON. DETECTOR NETER0 U OS

R 10AContainaent

R-10$Plant Vent

Top F loor ColdSide Interaed.

Scintillation control Rooa 10 -10 cpaDetector C Plant Coaput

10 .107 cpa

Indicates the concentration of Iodine-131 in the Containaent Building or

n a Qen V tIndicates concentration of Iodine- 131

in the Plant Vent air

RE llContainmentParticulate

- R.12ContainmentGas

10 .107 cpa

10 10 cpm

Normally aeasures short-lived partic-ulate daughters of noble gases in the

Containment Vent or ContainaentAtmos herHeasures the noble gas concentrationin uhich Zenon, 133 is the major I

isotope present in the ContainmentVen r Con a nm m s h

R-13Plant Vent

10 .10 cpa Plant Vent particulate aonitornoraally measures short-lived par-

cula d u r

ahp

R 14

Plant Vent10 10 cpa Plant Vent noble gas aonitor noraally

aeasures Lou concentrations of Xe- 133from Reactor Coolant Leak in the Aux.

Ld3l0

R. 15Air Ejector

N.E. Corner TopF loor Turb. Bldg.

10 - 10 cpa Measures condenser off gas and isusually the first sensor of priaary

r

r.0

R-16 Basement Floor ColdContainaent Fan Side tnteraediate

d b

10 - 10 cpa Honitors the service uater froa theContainaent Fan Coolers

RE 17

CoaponentIntermediate FloorAux. ~ Ldg. NUT Area

10 - 10 cpa Used to detect leakage of primarycoolant into the Coaponent Cooling

R Lg

Liqu>4 us ~ t ~

Ava. ALE . NestIA4 Imp Floor

Scintill~ tion Control Rooa C 10 F 10 cpa Nonitors liquid released for unexpect-0 ~ t ~ ctor Plant Computer ed activity levels . an alara uILL

I Let r e e

0 O

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TA

RAD I AT ION DETECTOR HETER

R-19.S/G BLo»doun

R.20ASpent Fuel PoolNeat Exchg. 1A

R.20$Spent fuel PoolHeat Exchg. 1B

0 Ws r

Intermediate floorHot aide Intermed.

West endIntermediate FloorAuxiliary Bldg.

Aux. B ldg.~ Top floor

~ 110 -10 cpm

10 -10 cpm

101-10 cpm

Honi tora Steam Generator bloMdoun Waterfor primary to secondary Leakage High

c

Honitors for Leakage from the Spentfuel Pool into the service mater due

to heat tube Leaks

Honitors for leakage from the Spentfuel Pool into the service uatir dueto heat exchanger tube Leaks

R-21-Retention Tonk

Basement Serv.Bldg. Recircu-lation Line

ScintillationDetector

Local ly Alarmin CR

10 -10 cpm Honitors Retention Tank ueter uhichis collected from normally cleanareas of the plant . and vill isolatenormal rcless eth uh n on slera

RE 22

High Conduct-s TSAL

AVT Room Scintilla tion AVT Control 10 -10 cpm Honitors Condensate Polisher regenere.Detector Panel tion waste voter activity and Mill is-

olet h normal d cher e u o eler 0

8

Lere0

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0

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I

TABLE 6 3BSPTNG 4 RA01AT10N HON1TORTNG SYS TEN

Unit ¹01 Containment Vent Sampler, Unit ¹02 Plant Vent Sampler

¹01Beta Particulate Scintit lation 1.0x10 to 1x10o uCi/on the f liter

¹02Alpha Particulate Open Face Diode Radon/thoron detector to correct

beta particulate levels.

iodine¹03

Scintillation, 2x2Nsl single ChannelAnalyzer

to 10 uCi on the filter

¹04iodine Adjacent Nindog -Scintillation Note this channel only compensates

channeL 3

¹05Noble Gss Loi Range Scintill~ tion 1.0x10 to 1x10 uCi/cc Eq Xe

¹06Area Honitor G H Tube 0.001 to 1000 mR/hr. Honitors

Radiation Levels at Unit

¹07Noble Gss Hid. Range G-H Tube 1.0x10 to lx10 uCi/cc Eq Xe

¹OBGamma Background G.H Tube Note this channel is used onty

for Gamma compensation on channel05 snd 07.

(09spots CD s Nigh Range G AH Tube 1.0x10 to 1.0x10 uCi/cc Eq Xe 133

Note. U„its 1 snd 2 csn be read on the PPCS or locally on the 296 ~ level of the clean side of the intermediateBuilding. Read out of SPING 4 data is svsi table in the TSC.

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TABLE 6.3B (CONTTNUED)SPiNG 4 RADIATTON HONiTORiNG SYSTEH

Unit ¹03 Ajr ejector aonitor. Note: Channel 1 ' exist in the unit but are not used. Unit 3 can be readthe TSC or the turbine f loor of the Turbine Building ANorth Vail).

¹05Noble Gas Lou Range Scintillation 1.0 10 to 1 10 uCi/ Eq X

¹06Area Nonitor 0-H Tube 0.001 to 1000 aR/hr

¹07Noble G ~ s Ned. Range G-N Tube 1 'x10 to 1x10 uCi/cc Eq Xe

¹08Gaaaa Background G-H Tube Channel 8 only compensates channel

05 and 07.

¹09Noble Gas High Range G-N Tube 1.0x10 to 1.0x105 i 133uCi/cc Eq Xe

Unit ¹04 Steaaline Nonitors. ~: Unit 04 can be read on the PPCS,on a control rooa recorder, in the TSC, or at the 296'evel of theclean aide of the tnteraediate Building.

¹01"A" Steaaline Nonitor G-N Tube 10 to 10+ aR/hr

009U'

¹02age Steaaline Honitor G-N Tube 10 2 to 10 eR/hr

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~ABL 6 3C

RADIATION DETECTOR HETERT N

POSSIBLE HEANINGS OF ALARH OR

U N N

R-1 . ~

Control Room

R 2

Containment

Control Room

By Personnel Natch

IonizationChamber

Control Room 10 -10 mR/hr't Plant Compt.

Rising Radiation Level in theControl Room Possible Control Room

c i i litRising Radiation Levels InContainment

R.7Incore Detector

R ~ 9

Letdown LineI I

R.29Nigh Range Con-

Intermedi ~ t ~ FloorsContainment

NaON Tank Room

Basement FloorAuxi ar . d

Containment NM

Operating FloorIonizationChamber

1 R/hr ~ 10 R/hr

Indicates Flux Happing in Progressor possible rising radiation

l i con m

Increasing Radiation Levels in theReactor Coolant System

Primary Coolant Leak in Contain-

mentt

8Q

R.30Nigh Range Con-

Containment NE

Operating FloorIonizationChamber

1 R/hr-10 R/hr Primary Coolant Leak in Contain-

mentt

x0po

8

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74

External dose or dose rates from surface contamination orairborne radioactivity are determined by direct fieldxeawurements (TLD or survey meter.) Xnternal dosecommitments from key isotopes via water or airbornepathways would be evaluated using the uptake rates,dose conversion factors, and other pathway parametersgiven in EPA 520, NUREG 133 and Regulatory Guide 1.109.Computer software is available through consultants usingthese dose calculational models so as to determine theradiological dose assessment. Zn this manner, rapiddetermination of dose estimates from multiple pathwaysmay be made for comparison with protective action guides.

adiatio o to s ~

The plant area radiation monitoring system providesindications and alarms which assist in assessment ofplant conditions. Its general functions are as follows:a) To indicate the general radiation level in specified

areas of the plant.b) To provide visible and audible alarms at both the

Control Room and the remote meter location whena significant increase in radiation level occurs.

c) To provide a visible alarm in Control Rooa on meteror detector failure.

As described in Section 3.0, Emergency Conditions, thissystem is used to initiate local radiation eaergencyprotective action, and in combination with other systemsto indicate the need for a site evacuation and possibleofi-site protective measures. TABLE 6.3C lists thelocation of area monitors of ma)or interest. Alarmsetpoints can be found in Procedure P-9.

High Range Radiation Monitors are installed withincontainment with digital readout in the Control Room. Aprocedure is available by which readings can bo convertedto an interpretation of the extent of fuel daaage and/orradioactivity released to the containment atmosphere.

0 an e Nuclear nst entatioThe two source range channels are used at shutdown toprovide an audible count rate signal and audible alarmsboth in the Control Room and Containment to call attentionto unexpected increase in neutron flux. A high sourcerange alarm in containment .is the signal to evacuate thearea.

Revision 8 October 1989

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t ous A o s:

Several mobile radiation monitors are available withinthe controlled areas particularly for use during workwhere local detection of excessive airborne contaminationis advisable. Various combinations of noble gases,iodine and particulate analyzers are available. Theseare equipped with meter and chart readouts, as well asaudible and visible alarms.

Portab e Monitors Sam lin E i ment and Other S ecialSDLig

Portable monitors, sampling equipment and other specialequipment for assessing the extent of the consequencesof a radiation emergency are located in the ControlRoom, the Health Physics Office, the Auxiliary Buildingand the Survey Center, including individual surveyequipment boxes for each survey team. A summary of thisequipment is given in Appendix D. Additional samplingand monitoring equipment is also available in the TSCand the EOF.

Process and Containment Monitors:

Numerous process variables are indicated and recorded inthe Control Room to ensure safe and orderly operation ofall systems and processes over the full operating rangeof the plant, as well as for detection of off-normal oremergency conditions. Of these monitors, particularimportance is placed upon those which provide fordetection of a loss of coolant accident and the immediateautomatic actuation of equipment to mitigate its con-sequences. These include 4 channels 'for Pressurizerpressure, 3 channels for Pressurizer level, 4 channelsfor Steam Generator level, 4 channels for Reactor Coolantaverage temperature, 2 channels for steam flow and feed-water flow for each Steam Generator. Along with theseare indications of Containment conditions which include6 channels for Containment pressure, sump level and pumpactuation, safety in)ection recirculation sump levelindicator, 4 channels for fan cooler condensate level,and 6 channels for dew point temperature. Greater detailfor. the process and containment monitors is given in theUFSAR, Chapter 7 and in our letter dated January 31, 1984from John E. Maier, RG&E to Dennis Crutchfield, NRC.

Seismic and hydrologic emergencies are treated byprocedure SC-5 and SC-4 respectively. A seismic monitor(Accelograph) is located in the intermediate buildingsub-basement and a lake level indication is availablefrom the plant computers.

Information concerning seismic or hydrologic eventscan be obtained from offsite agencigs such as the NYSgeologist at the State Education Dept.'or at CornellUniversity Geology Dept.

Revision 9 November 1990

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t Labo ato e

The laboratory area of the plant is maintained for thepurpose of monitoring the condition of a variety offluid streams and stored fluids, including the activityand isotopic content; for assessing the degree of conta-mination of plant areas, movable items and personnel;and for storing, calibrating and maintaining portableand laboratory radiation measuring instruments. Separatelaboratory facilities are provided for assessing theeffect of the plant operation on the environs.

By the use of a Post Accident Sampling System located inthe controlled area of the Intermediate Building,samples can be drawn from reactor coolant, containmentatmosphere, and containment sump. These samples areprocessed from a remote control board to open valvescollect the sample and read out results of analysis.The sample can be remotely analyzed for dissolvedhydrogen, dissolved oxygen, boron and pH. Analysis forchlorides and radioactive isotopes can be completed ondiluted, shielded grab samples in a laboratory facilitywithin the times required by NRC NUREG-0737. Samplescan be taken and analyzed without exceeding personneldoses of 5 Rem. This system will also be used fornormal operational samples.

In addition to laboratory facilities within the plant,some laboratory capability is provided at the SurveyCenter for use in assessing the offsite effects of anincident. An Environmental Laboratory, located on thesite property, but outside the main plant building/contains all the equipment necessary for isotopic analy-sis. The resources of the Environmental Laboratoryoperated by the New York Power Authority at Fulton, NewYork are also available as noted in a letter of agreement.

Meteo olo ica o tor n

Data on meteorological conditions are available to theControl Room for use in assessing the consequences of anairborne release of radioactive matter. All meteorolog-ical measuring devices, with the exception of theprecipitation measuring system, are mounted on a 250foot weather tower located at the Ginna Plant site.Windspeed, wind direction and temperature are measuredat the 33, 150, and 250 foot levels. The 33 ft. wind,speed and direction sensor readings are recorded on theRadiation Monitoring System Panel in the Ginna ControlRoom. Temperatures at three tower levels are alsoindicated in the Control Room by digital display. Thisinformation will be relayed tc the NRC OperationsCenter, the New York State and County EOCa. Meteoro-logical data is available continuously and is alsoprogrammed for print out at 15 minute averages, accessiblefrom the TSC and EOF.

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77

Rainfall is measured by a tipping bucket rain gaugelocated at the base of the Ginna weather tower. Winddirection, windspeed, and temperature indications fromthe three tower elevations are also registered on theGinna Plant Process. Computer System. Instrumentation andcalibration procedures associated with the Ginna meteor-ological program are in conformance with RegulatoryGuide 1.23.

The weather tower is equipped with redundant sensingdevices for use as backup indicators of windspeed,direction, temperature and temperature difference. Allmeteorological data will be collected and computer-processed to provide estimates of radioactive materialstransport and diffusion under routine and accidentalconditions. Power for the meteorological measurementssystem and associated equipment is supplied by anelectrical feed separate from the plant. Means forremote interrogation of the meteorological system bytelephone link, is available to the Technical SupportCenter and EOF via computer terminals at each location.Rochester Monroe County Airport (US Weather Service) .hasmeteorological instrumentation readings which can beaccessed by private phone number on a 24 hour basis. Abackup weather tower is located on Rt. 104, approximately3.5 miles south of the plant and has wind and temperaturerecorders. Means for remote interrogation of the back-up meteorological system is available at the TSC and EOFvia computer terminal.An implementing procedure describes the method by whichonsite meteorological information is used for theestimation of offsite radiation doses. Based upon windconditions and determined atmospheric stability, estimatesof downwind radioactivity concentrations and doses canbe made by the Health Physicist in the Dose AssessmentAreas using pre-printed overlays placed on a regional map.

Revision 9 November 1990r

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Environs Radiolo ical Monitorin

Sampling systems are established for normal environmentalsampling in the immediate area surrounding the plant andalso in locations whose distance from the plant roughlycorresponds to 1/100th of the onsite radioactivityconcentrations estimated from annual average atmosphericdispersion. These stations contain provisions for airsampling and for radiation dose measurement. Certainstations include precipitation collectors. They provideinformation about the extent of a general emergency andits effect on the environment, in accordance withappropriate implementing procedure.

In addition, an array of thermoluminescent dosimeters(TLD's) is in place at the site boundary, at approximately5 miles from the site, at the offsite sampling stations(approximately 10 miles) and at the onsite samplingstations. The survey teams willplace up to 25 additionalTLD's at specified locations during their tours after anincident, which will add to the evaluation of dosesthroughout the emergency planning zone. The placementof these TLD's around Ginna Station for routine or postaccident radiation assessment is given in an imple-menting procedure. Maps are included in that procedureso as to locate the TLD's for best coverage (Figure6.3). The radiological program provided meets theminimum requirements of the NRC Radiological AssessmentBranch Technical Position for Environmental RadiologicalMonitoring.

Monitoring teams are quickly dispatched to followdesignated routes for the field monitoring within theplume exposure zone. A Ginna Station procedure detailsthe method used for the rapid field determination ofairborne particulate and radioiodine concentrationsfollowing an accident in addition to radiation levels.The procedure consists of operating a portable airsampler which contains a silver zeolite cartridge andparticulate filter, followed by direct filter measurementwith a count rate meter probe. The minimum sensitivityfor iodine by this method, based upon a 6 minutesampling time is approximately 2.3 E-8 uCi/cc.It is recognized that under certain post-accident condi-tions, some unavoidable interference from noble gas orhigh background levels may affect the initial filterreadings being taken in the field. The absorption ofnoble gases in the charcoal cartridge would lead to anover estimate of airborne radioiodine concentrations.Therefore, silver zeolite is used. If background levelsare too high to determine a proper filter reading, analternate location out of the radiation plume will beused to obtain filter measurements.

Revision. 9 November 1990

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80

Air samples collected by survey teams from portablesampling devices and from fixed air monitoring systemsmay be evaluated using higher sensitivity methods withonsite or near-site analytical equipment (e.g., environ-mental laboratory trailer).Emer enc Instruments and E i ment:

Emergency equipment for the various centers is describedin Appendix D. This equipment is checked monthly to becertain that it is available, in place and operable.Any instrument or equipment found to be in need ofrepair or calibration is immediately replaced from theHealth Physics reserve supplies. Instruments arecalibrated along with plant instruments by the HealthPhysics Section according to HP Procedures which meetthe manufacturers recommendations. Sufficient reservesof instruments and equipment to replace those that areremoved from service for maintenance and/or calibrationare available.Pub ic Alertin S ste

An alerting system to make the public aware of an incidentat Ginna Station which may require protective action ontheir part has been developed and installed. The Ginnaprompt public notification system consists of 96 sirenssupplemented by more than 40 tone alert radios atschools, nursing homes and industrial establishments.The special needs of transient populations at locations,such as motels, parks and work camps will be addressedby utilizing mobile loud speakers and direct facilitynotification. Instructions for transient populationshave been distributed to such locations.The design obgective for this system is to completethe initia'1 alerting of the affected population within thePlume Exposure Pathway within 15 minutes after thenotification of local and state government by theNuclear Facility Operator. The system was designedto assure coverage of essentially. 1004 of the populationwithin the 10 mile Emergency Planning Zone.

Revision 9 Noveaber 1990

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81

The control of the system rests with the County officialswithin their respective borders. Zn Monroe County theCounty Executive has this authority and in Nayne County,it is the Chairman of the Board of Supervisors. RG&Eand the NYS Health Department will make recommendationsto activate the system if necessary.

Sirens and tone alerts are activated by a radio signaland a digital encoding system is employed to insure asecure, reliable control.

A backup transmitter is available in each county foractivating the alert system should the primary transmitterfail. The siren portion of the alert system is designedto produce a minimum 10dB(c) above ambient sound levelsin all portions of the Emergency Planning Zone or aminimum of 70dB at. 100 ft. from the siren base.

The ob)ectives of the Ginna prompt public notificationsystem are two fold: to notify the general public bothindoors and out of the existence 'of an emergency situat»ion, and to provide for the communication of preliminaryemergency information.

Zn conjunction with the alert system, the public will bekept informed of the procedures they should follow if thesystem is activated, .through activation of the EmergencyBroadcast System.

Sample message to. be given over the EBS radio are partof the county procedures. A brochure to be distributedannually provides information regarding the system andappropriate actions to be taken.

Siren reliability will be tested .periodically at 3levels of operation.

1. Bi-weekly silent tests to verify system electroniccomponents are functioning.

2. Quarterly manually activated growl testa.3. Annual full duration audible tests of the entire

system.

Periodic surveys will be taken by the Federal EmergencyManagement Agency to determine any difficulties whichmay recpxire corrective measures.

Revision 9 Noveaber 1990

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82

6 ' '3

Alert system operational reliability is expected to begreater than 954. Sirens are powered off the RG&Edistribution system which has better than 99% avail-ability. It is fed from the New York State Power Poolgrid, therefore, it is not dependent on the operation ofGinna. Rochester Gas and Electric Corporation has theresponsibility for maintaining the alert system opera-tive. The location of sirens and tone alert radios isgiven in Appendix I.Fire Protection Facilities:

6.4

The fire protection facilities comprise a number ofautomatic and non-automatic protection systems as wellas assessment and alerting equipment.

Fire protection facilities have been installed in accor-dance with the Ginna Station Technical Specificationsand NRC Fire Protection Safety Evaluations. Detectionis provided in all areas of the plant that containvital equipment. The system initiates suppressionsystems and alarms in the Control Room.

Protective Facilities:

6 ~ 4 ~ 1

Aspects of the plant which are provided to serve aprotective function to personnel onsite in the event ofan emergency are described in this section. Theyinclude accident shielding, protective ventilation,emergency condition signaling equipment, reassemblylocations, containment control provisions, and otherprotective equipment and supplies. First aid and medicalfacilities are treated separately in Section 6.5.Acie S e

The containment vessel consists of the 3 ft. - 6 in. thickreinforced concrete cylinder capped by a hemisphericalreinforced concrete dome of' 2 ft. — 6 in. thickness.The shielding includes supplemental shields in front ofthe containment personnel hatch and 20 inch walls, eastand south sides and the roof of the Control Rooa. Theequipment access hatch is shielded by a 3-foot thickconcrete shadow shield and a 1-foot concrete roof toreduce scattered dose levels. Concrete walls andceiling of the Technical Support Center provide shielding.

Revision 9 Noveaber 1990

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83

tective Ventilat o

During normal operation fresh makeup air is admitted tothe Control Room ventilation system through an intakelouvre located in the Turbine Building outside wall; theamount of makeup air varies between, 15 and 100 percentof the unit flow rate, depending on outside air tempera-ture. Pneumatically operated dampers can be positionedfrom the Control Room to isolate the fresh air intakeand to place a separate charcoal filter unit in recircu-lation service.

The charcoal filter unit includes both high efficiencyparticulate air (HEPA) and charcoal filters for removingradioactive particulate and gaseous iodine from theControl Room atmosphere. Its capacity is approximately25 percent of the system flow rate, and the unit isinstalled in a normally isolated bypass circuit. In theevent of high radiation levels in the Control Room, theControl Room radiation monitor will automatically closethe redundant dampers in the fresh air intake duct andthe dampers in the return air duct to the TurbineBuilding, and will open the damper in the charcoalfilter unit inlet duct. This signal will also start aseparate fan to provide flow through the charcoal filterunit.Until radioactivity in the Control Room atmosphere isreduced to a safe level, system flow will be in a closedcycle from the Control Room, with approximately 25percent bypass flow through the charcoal filter unit,through the air conditioning unit and back to theControl Room.,

The dampers can also be positioned to permit fresh airmakeup to the system through the charcoal filter unit.Since all Control Room penetrations including doors aredesigned to high standards of leak tightness and theControl Room is .maintained at essentially atmosphericpressure, the'nfiltration of contaminated air into theControl Room is limited to a very low rate. Nith thecharcoal filter unit, in service, airborne particulateactivity can be cleaned up at an effective rate ofapproximately 5 air changes per hour. In addition,Control Room personnel have access to portable respiratoryequipment.

The Control Room contains sufficient air to permit safeoccupancy by the operating staff for as long as necessarybefore outside air makeup is required for breathing.Bottled air is available.The Technical Support Center has filtered fresh airmakeup, with charcoal filtration, to meet habitabilityrequirements for unlimited occupancy.

Revision 9 November 1990

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84

e in E me t:Plant personnel are signaled to evacuate at once by aspecial tone, activated manually in the Control Room.In areas where audible signals may not be heard specialflashing lights have been installed. For fire andMedical emergencies, an explicit announcement is madeover the PA system.

eassembl Locat o s:

Several reassembly locations have been established, theselection of which will depend on the conditions of theemergency. Non-operating personnel affected by a localradiation emergency are to report to the DecontaminationArea or the Service Building Lunch Room, depending onthe presence of personal contamination.

In the event of a site evacuation, all Control Roomoperators are to report to the Control Room, the protec-tive features of which are described above. Non-operatingpersonnel are to reassemble at the Ginna Training Center,except for those having a role in the Technical SupportCenter, Operational Support Center or the Survey Centerdescribed in Section 6.1. The Training Center Audit-orium, roughly 600 feet from the Reactor, seats 150people; there is additional room in the classrooms andoffices. A local radiation monitor is installed on theTraining Center which houses the Survey Center to aid inthe evaluation of the necessity for emergency organizationpersonnel to relocate.Contamination Contro Provisio s:

The plant site is divided into two categories, the CleanArea and the Radiation Control Area. Entry to and exitfrom the Radiation Control Area is normally through thedesignated Access Control Point. Any area in whichradioactive materials and radiation are present shall besurveyed, classified, roped and conspicuously postedwith the appropriate radiation caution sign. These thenbecome Radiation Control Areas and proper access isprovided and controlled. Plant procedures provide theradiation or contamination levels at which an area isdeclared, a Radiation Control Area or reaaved fromradiation control status.

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85

The general arrangement of the service facilities isdesigned to provide adequate personnel decontaminationand change areas. The clean locker room is used tostore items of personal clothing not required or allowedin the Radiation Control Area.

The Access Control Point is employed as a protectiveclothing change area. A supply of clean protectiveclothing for personnel is maintained in this area, andthere is provision for collection of used protectiveclothing.All personnel will survey themselves on leaving theRadiation Control Area using equipment provided at theAccess Control Point. A decontamination shower andwashroom are located adjacent to the Access Control Point.

Personnel decontamination kits with instructions postedfor their use are available in the dispensary describedin Section 6.5, First Aid and Medical Facilities. Thedispensary also contains an emergency treatment anddecontamination table for handling contaminated personnelwho are seriously injured.In the event of a site evacuation, provisions for decon-tamination are available at the Survey Center.

A 1000-gallon holding tank is available to containdecontamination water from a sink and shower located inthe Survey Center. Decontamination water will besampled prior to transfer, treatment or disposal.

Protective E me t and Su 1 s:

All personnel entering the Radiation Control Area arerequired to wear protective clothing. The nature of thework to be done governs the selection of protectiveclothing to be worn by individuals. The protectiveapparel available are shoe covers, head covers, glovesand coveralls. Additional items of specialized apparelsuch as plastic suits, face shields, and respirators areavailable for operations involving high level cont-amination. In all cases, Health Physics personnel shallevaluate the radiological conditions and specify therequired items of protective clothing to be worn.Respiratory protective devices are required wherever anairborne radiation area exists or is expected. In suchcases, health physics personnel monitor the airborneconcentrations and specify the necessary protectivedevices according to concentration and type of airbornecontaminants present.

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6 ' '

Available respiratory devices include full or half faceair purifying respirators (filter type both negative andpressured powered air purifying units). Air linesupplied respirators of pressure demand type are usedas well as constant flow hoods. Self-Contained BreathingApparatus using full face masks and pressure demandregulators are also available.

For use in an emergency, equipment and supplies arelocated in the Control Room, Technical Support Center,Respiratory Protection Facility and the Survey Center.Equipment categories are given in Appendix D.

er enc Vehicles:

In the event it becomes necessary to make use of automo-tive equipment, a number of vehicles will be available.These include company-owned vehicles and personalvehicles. A small delivery truck and a small work truckare assigned to the Station. The ground maintenancegarage, nearby, is assigned a 4-wheel drive truck. Useoi personal vehicles is allowed by the Company policyregarding paid mileage for company use. Lastly, a largeand diverse fleet of vehicles is available from theRochester Gas and Electric Transportation Department.

6 ' st A d and ed c ac es:

First Aid and medical provisions include both onsite andoffsite facilities. The latter are described in Section4.3, Augmentation of the Emergency Organization. Adispensary on site contains sinks, a toilet, an emergencytreatment and decontamination table, personnel decontami-nation and bioassay collection kits,. a bed, a stretcherand miscellaneous first aid equipment and supplies.Additional decontamination kits can be obtained from themain H.P. Frisking Station area.

Operations personnel, shop foremen, Health PhysicsTechnicians and Plant Staff are trained in first aidprocedures using Red Cross Multi-Media or an equivalentprogram. An administrative procedure establishes aFirst Aid Team and the actions to be followed in theevent of illness or in)ury at Ginna Station

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7 ' NTAINING NUCLE EMEROENC REPARED 8

7 '

Formalized training program(s) have been established toensure that all personnel who actively participate inthe Nuclear Emergency Response Plan (NERP) maintain theirfamiliarity with the plan and their recpxired response.A radiation emergency exercise shall be conducted atleast annually, with emphasis placed upon orderly imple-mentation of the emergency plan.

Personnel trained for onsite response to a radiationemergency are part of the regular plant staff and aretrained to specific responsibilities within the EmergencyOrganization. Training is documented by the DepartmentManager, Production Division Training and CorporateNuclear Emergency Planner. Any Emergency Plan work byconsultants will be under the control of, and reviewedby, the Corporate Nuclear Emergency Planner.

Drills shall be evaluated by the Corporate NuclearEmergency Planner and reviewed by the Plant OperationsReview Committee, thus assuring the effectiveness of theplan throughout the lifetime oi the R.E. Ginna facility.

aini nd

Training classes on the emergency plan shall be conductedannually for all RG&E personnel who may actively partici-pate in the radiation emergency plan. Details of thetraining programs are established in EPZP 5-4. Trainingwill include a demonstration of their ability to performthe functions to which they may be assigned. Duringdrills on the spot corrections'f erroneous performancewill be made, followed by a demonstration of properperformance.

Specialized Training will be provided for:l.2 ~

3 ~

4 ~

5 ~

6 ~

7 ~

8 ~

Technical Support Center assignees .

Operatio'n Support Center assigneesFirst Aid TeamsSurvey TeamsEmergency Operations Facility personnelSecurity personnelLocal Emergency Support Services personnelFire Brigade personnel

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7.1.2 c Coor a o

Training of Emergency Coordinators will be given annuallyto the Plant Manager, plant superintendents, shiftsupervisors, and engineering staff who may be assistingthe Emergency Coordinator during a Site RadiationEmergency. This training will cover responsibilities,communications, Emergency Action Levels, protectiveAction Recommendations, and review of all procedurespertinent to the Nuclear Emergency Response Plan. TheTraining Manager shall prepare necessary lesson plansand document this training. The individuals to betrained and material to be covered are delineated inEPXP 5-4.

F 1 3 Su e earns

7 ' ~ 4

Survey Team training will be given to selected personnel.Training material will cover health physics practicesand techniques utilized during radiation monitoring,Survey Center equipment and its use, radio communicationstechniques, monitoring and sampling procedures, surveyroutes and sample points, contamination and decontamin-ation considerations, and review of implementing proce-dures used by survey teams. Field training will begiven as needed.

eci rai in or artici atin A e c es:

Training shall be provided for the following groups:

a) Ontario Volunteer Fire Company

b) Ontario Volunteer Emergency Squad

c) Rochester General Hospital

d) Newark-Wayne Community Hospital, Inc.

Training for these groups consist of lectures concerningtheir required involvement during radiation emergencies,procedures for notification and basic radiation protec-tion.

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D 1 s and Exe ciseAn administrative procedure establishes the trainingprogram which develops and maintains the proficiency ofemergency response personnel. This program meets therequirements of 10CFR50 Appendix E Section IV F regardingcoping with emergencies. Through the training programpersonnel will be familiarized with the intent of theplan and the content of implementing procedures. Keypersonnel will be trained in the specific duties to whichthey may be assigned. Lectures and field training willbe used, as appropriate, to familiarize personnel intheir duties.Communications equipment and processes are checkedperiodically as established by an implementing 'procedure.The New York State-County Hot Line and the NRC Hotline aretested monthly. Fire drills are conducted in accordancewith plant Technical Specifications and implementingprocedures. A medical emergency drill which involves asimulated contaminated/in)ured individual and partici-pation by the local support services will be conductedannually. A plant environs radiological monitoring drill(onsite and ofisite) will be conducted annually incon)unction with training for and during the annual exer-cise. This shall include collection and review oianalysis procedures for environmental samples. HealthPhysics drills, which include sampling and analysis ofsimulated high activity post accident samples using thepost accident sampling system, will be conducted semi-annually.

Preparation of the scenarios for use in exercises anddrills will be coordinated by the Corporate NuclearEmergency Planner (CNEP). The scenario package shallinclude the scope, goals and objectives oi the exercise,a time-line of real and simulated events, a narrativesummary, participating organizations, appropriate Rsssagesand data sheets, evaluation criteria, and information forofficial observers. The CNEP with the assistance of theDepartment Manager, Production Division Training, willarrange for qualified observers/controllers and coordinateactivities of participating organizations. The scenarioshould be varied from year to year to teat all ma)orelements of the plan within a 5 year period. Theexercise shall simulate an emergency that results inoffsite radiological releases which require response byoffsite authorities.

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Annually, a radiation emergency exercise will be held.This exercise will be coordinated with participatingoffsite agencies, testing at a minimum the communicationslinks and one other element. Drills will be started atvarious times of the day and under various weatherconditions. Some exercises will be unannounced.Scenarios will be developed which allow for free playin decision making by those individuals in responsiblepositions. Structured responses will be used only tothe extent necessary to keep the exercise moving so asto meet the ob)ectives of the exercise.

Written evaluation of the Radiation Emergency Exerciseshall be submitted by the CNEP to the Plant OperationsReview Committee emphasizing areas of strength andweakness and outlining plans for remedial action, asnecessary.

A critique at which controllers, observers or partici-pants may make comments will be held as soon as practicalafter the exercise to evaluate the actions and inter-actions of response organizations. Training EvaluationAction Reports (TEARS) may develop from the critiquecomments. TEARS are reviewed by the Plant OperationsReview Committee, Plant Manager and the CNEP to assurethat necessary corrections to the Plan are implemented.

Co orate Nuclea Emer enc Pla ner P a OnsiteEmer enc Planner 0 P :

The Corporate Nuclear Emergency Planner (CNEP) isresponsible ior coordinating the NERP with other responseorganizations. He will review the Plan and agreementsto certify that they are current. The update will takeinto account changes identified by drills and exercises.

The CNEP reports to the Director, Corporate RadiationProtection within the Electric Production Department.An Onsite Emergency Planner (OEP) provides assistapce onEmergency Planning issues in the plant and will bedesignated duties and responsibilities similar to thoseof the CNEP. See Figure 7.1.

The CNEP/OEP will maintain his awareness of emergencyresponse activities, facilities and procedures„ byparticipating in related committees and reviewingcompleted documentation. The CNEP is a member of theEmergency Plan Implementing Procedures Committee (EPIPC)which reviews all changes to EPIP's and eaergencyfacilities.The CNEP/OEP conduct surveillance of the EmergencyResponse Facilities through scheduled inspections andtests to ensure their readiness.

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The CNEP/OEP meet routinely with Ginna Management andsupervisors to discuss emergency concerns, training andchanges relative to emergency planning. These meetingsinclude: Milestone Committee, PORC, EPIPC, MOPAR, andSpecial Task Forces.

The CNEP/OEP will attend appropriate training, seminars,workshops, and conferences sponsored by RG&E, theNuclear Industry, Federal, State and Local Governmentsto keep current on Emergency Planning techniques andconcepts.

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NUCLEAR EMERGENCY PLANNINGORGANIZATION

'ICE PRESIDENTGINNA

NUCLEAR PRODUCTION

DIRECTORCORPORATERADIATION

PROTECTION

CORPORATEHEALTH

PHYSICIST

CORPORATENUCLEAR

EMERGENCYPLANNER

ONSITEEMERGENCEY

PLANNER

Figure 7.1

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7 ' v e an Revision o t e a n P o edures:

7 '

Review and revision of the Nuclear Emergency ResponsePlan and the Emergency Plan Implementing Procedures (EPIP)may be the result of drills, exercises or routinesurveillances. Revisions to the plan are subject toapproval by PORC and the Nuclear Safety and Audit ReviewBoard (NSARB).

Plant and corporate implementing procedures are reviewedby EPIPC and approved by PORC.

An Administrative procedure provides for the distributionof revised procedures and a PORC review of each

procedure'very

2 1/2 years.

Emergency procedure changes are controlled so that onlycurrent copies are available for use. Revised proceduresare distributed to a list of controlled copy holderswith receipt verification. Shift Operators and LicensedStaff are made aware of revisions by initialing anOperator Acknowledge Sheet for relevant procedurechanges. Emergency telephone numbers are kept up to datethrough quarterly review and distribution of revisions.

e e c E i me t a d S es:

7 '

~ The operational readiness of all items of emergencyequipment and supplies will be assured through monthly

. inspections of emergency equipment. The implementingprocedure includes inspecting and testing of equipmentstored in the Control Room, Survey Center, TechnicalSupport Center, Health Physics office and EOF/RecoveryCenter. Also included is the procedure for testing theoperability of the equipment.

Necessary transportation for offsite surveys will be apersonal car supplied by one member of the team.Company policy provides for mileage reimbursement;therefore, no lack of vehicles is anticipated, due tothe remoteness of the facility, employees commute byprivate car.

g~d+t~:The Nuclear Emergency Response "Plan, its implementing,.procedures, equipment, training and interface with stateand county authorities is audited at the frequencyrequired by Ginna Technical Specifications and isreviewed by the NSARB. Any audit findings are documentedand reviewed with the Vice President, Ginna NuclearProduction. An Audit Finding Corrective Action Report(AFCAR) is used to document the corrective action. Theaudit results are also reviewed by NSARB. Audit documentsare retained for S years.

Revision 9 November l990

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8.0 HE UARTERS OFFSITE RESPONSE PLAN:

8 '

This Section provides guidance for the RG&E Headquartersresponse to, and recovery from, an emergency conditionat the Ginna Nuclear Power Plant. In the event of anemergency condition at Ginna, the normal companyheadquarters and the plant organizational structureswill be transformed into an Emergency Response Organi-zation or Emergency Support Organization.

The Company's Emergency Support Organization is chargedwith the responsibility of bringing together a cohesiveCompany management and technical team. This organizationwill be calling upon the maximum resources availablewithin the Company and the entire nuclear industry forthe goals of (1) assuring the safe shutdown and recoveryof Ginna Station following an accident condition and,(2) minimizing the impact of the situation on the healthand safety of the public.The Company's Emergency Support Organization is establish-ed 'under the leadership of a single individual calledthe EOF/Recovery Manager. The EOF/Recovery Manager issupported by various technical and advisory disciplinesincluding Engineering, Facilities and Personnel, NuclearOperations, Public Affairs and System Operations.

This Emergency Support Organization will be available tothe Ginna Station Plant Manager for implementation oflong-term recovery operations. The Ginna Station short-term responding organization is made-up of site personnel,those on-shift and those immediately available from theplant staff complement.

The Nuclear Emergency Response Plan is compatible withthe New York .State and local (Wayne and Monroe Counties)emergency plans. Total emergency response, ia therefore,a combined and coordinated effort involving plant,company, private, local, and State resources.

This portion of the plan provides a mechaniaa by whichthe functions of the station and corporate staffs areimmediately directed to accident termination or mitiga-tion, the determination of offsite"conditions and stationrecovery operations. The plan also provides for obtainingadditional support if the emergency is of such a magnitudethat Company resources are overextended. Such supportmay be additiona'1 manpower'o augment the station'soperating staff, manpower in specialized disciplines, orspecialized emergency response equipment and services.

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Ginna Station procedures provide that the Senior VicePresident, Production and Engineering is notified andprovided with details concerning the " emergency, theemergency classification, station status, and immediateCorporate assistance, if any, which may be required.The EOF/Recovery Manager has the authority to activate theEmergency Support Organization. The Emergency SupportOrganization Figure 8.1 will be activated under the SiteArea and General Emer encies although it may be eitherpartially or fully activated under other categories.The EOF/Recovery Manager will be responsible for theoffsite radiological consequence assessment and intera-ction with the remainder of emergency and recovery planarrangements. Emergency Support Organization participantsunder the EOF/Recovery Manager possess the necessaryexperience and expertise in radiological assessment toeffectively evaluate possible accident consequences.The EOF/Recovery Manager will be responsible for communi-cations with offsite authority designated in theEmergency Plan and for providing the accident diagnosisand prognosis information for the offsite authorities toassist in their emergency response. He will arrangethrough the other Emergency Support Organization membersfor the dispatch of any special assistance or servicerequested by the station and serve as the primarycoordinator between the station and Emergency SupportOrganization.

Reporting to the EOF/Recovery Manager will be theEmergency Support Organization. Members of the EmergencySupport Organization are company officials experiencedin their area of responsibility. Each official willmanage an adequately staffed group in the following areas:

Technical support with the nuclear experience andtechnical expertise in support of station operationsand recovery.

2 ~ Offsite Dose Assessment, radiological control andwaste management with the nuclear experience andtechnical expertise to manage the Offsite DoseAssessment, radioactive waste and radiologicalcontrol aspects of the response and recovery opera-tions.

3 ~ Design and construction support with the responsi-bility of coordinating the activities of theCompany, A/E, NSSS supplier and construction forceson proposed station- modifications or other designand construction support required for response andrecovery.

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96

Advisory support function with advisory supportconsisting of senior representatives of the NSSSsupplier and special consultants as necessary.

5. Public affairs staff with the responsi.bility ofproviding administration, logistics, communications,and personnel support for response and recoveryoperations.

6. Administration and logistics with the responsibilityof providing administration. logistics, communica-tions, and personnel support for response andrecovery operations.

An. organization chart for the Emergency Support Organiza-tion is provi.ded in Secti.on 8.2.

The EOF/Recovery Manager may call on other people withinthe company to support the emergency response effort andmay request assistance from other utilities, ZNPO,consultants, vendors or any other sources capable ofproviding support.

Upon activation of the Emergency Support Organization,the EOF/Recovery Center is established in the leasedoffice building basement, ad)acent to corporate head-quarters.

A Joint Emergency News Center will also be activatedupon activation of the Emergency Support Organization orin other situations as may be required. The Center willbe used to coordinate all news releases and press con-ferences with the appropriate Federal, State, and localauthorities.Personnel who have responsibilities in the EOF/Recovery<Center will be notified of an inci.dent and the need forthem to report to the EOF/Recovery Center according to anapproved procedure. Each individual assigned to theCenter will have a designated alternate who will be.notified as necessary. The EOF/Recovery Center will haactivated and manned by RG&E personnel within about onehour of declaration of a Site Area Emergency and above.Other personnel from RG&E, consultants, and contractpersonnel will be called to the EOF/Recovery Center toassist as needed.

8 ' Or ani atioThe EOF/Recovery Center will be organized as shown onthe attached Emergency Support Organization Chart figure8.1. The positions will be filled by trained individualsas listed in Section 8.3.

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PRESIDENT AND CHIEFOPERATING OFFICER

EOF IRECOVERYMANAGER

OFFSITEDOSE

ASSESSMENT

ADVISORYSUPPORT

MANAGER

NUCLEAROPERATIONS

MANAGER

ENGINEERINGSUPPORT

MANAGER

FACIUTIES ANDPERSONNELMANAGER

OFFSITEAGENCYLIAISON

CORPORATESPOKESPERSON

CORPORATENUCLEAR

EMERGENCYPLANNER

RESPONSEENGINEERING

MANAGER

CONSTRUCTIONMANAGER

UCENSING 5ASSESSMENT

MANAGER

NEWS CENTERMANAGER

EMERGENCYCOORDINATOR PROCUREMENT FACIUTIES PERSONNEL SECURITY

MEDIACOORDINATION

DOSE.ASSESSMENT

SECURITY

$4< la pet 5

PLANTASSESSMENT

ADMINISTRATIONCOMMUNICATIONS

RG8cE NUCLEAR EIVIERGENCY SUPPORT ORGANIZATION

FIGURE 8.1

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8 ' es o s bilit es

The following positions are the principal managers andcoordinators which make up the team in the EOF/RecoveryCenter and Joint Emergency News Center in response to anuclear emergency at Ginna Station. The responsibilitiesfor each position are given in EPZP 5-7.

8 ~ 3 ~ 1 EOF/Recovery Manager

8.3.2 Advisory Support Manager

8 ' ' Nuclear Operations Manager

8.3.4 Engineering Support Manager

8.3.5 Facilities and Personnel Manager

8 ' ' News Center Manager (at EJNC —via Corporate Spokesperson)

8.F 7 Corporate Spokesperson '

~ 3 ~ 8 Offsite Agency Liaison

8 ' ' EOF Dose Assessment Manager

8.3.10 Corporate Nuclear Emergency Planner

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8 ' Facilities8 '.1

A. Joint Eme e c News Cente JENC

B.

The Joint Emergency News Center for the Ginna NuclearPower Plant is located in the Rochester Gas andElectric Corporation office building. The buildingis a twelve story structural steel, reinforcedconcrete floor, structural tile wall structure withbrick facing. The structure was built in accordancewith the City of Rochester building code.

En ineerin Su ort Center ESC

C.

The engineering organization works out of their nor-mal office area and is managed from the EngineeringSupport Center where the engineering supportmanagers can coordinate their activities. This islocated on the fourth floor of the leased officebuilding at 49 East Avenue. As structural recordsare incomplete, it is assumed to be a structuralsteel reinforced concrete floor structure, built inaccordance with the City of Rochester building codes.

Emer enc 0 erations Facilit EOFThe Emergency Operations Facility (EOF) for the GinnaNuclear Power Plant is located in the basement ofthe Rochester Gas and Electric Corporation leasedoffice building at 49 East Avenue, next to the maincorporate office building. An area of the basementis designated and kept, in readiness to operate asan EOF. The building is assumed to be a structuralsteel reinforced concrete floor structure, built inaccordance with the City of Rochester building codes.

The leased office building and the corporate officebuilding are located approximately 18 miles WSW ofthe Ginna plant in the center of the City of Roches-ter.

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During emergency operation, the basement and theFourth Floor of the leased office building and thebasement of the corporate office building will besecured from the remainder of the buildings forexclusive use by emergency personnel. The basementlevel of the corporate office building willbe utili-zed by Rochester Gas and Electric Public Affairspersonnel and the news media. A portion of theFourth Floor of the leased office building will'beoccupied by engineering support personnel and aportion of the basement floor by Rochester Gas andElectric Management personnel assigned to directoverall Company operation during a Ginna plant acci-dent. Also, responsible emergency personnel fromLocal, State and Federal agencies will be located inthe basements and furnished with the appropriateaccommodations.

Size and StaffingA. Jo nt Emer e c News Ce te

B.

During a Ginna plant emergency, ma)or corridors, theauditorium and other facilities in the basement of89 East Avenue will be made exclusively availableto Rochester Gas and Electric, Federal, State andLocal agencies public .relations personnel. Themajor corridors (approximately 700 sq. ft.) will beused for phone communications by the news media.Participating emergency agencies will occupyapproximately 2500 sq. feet for private use and theremaining offices on the floor are for RG&E PublicRelations personnel use. A media work area hasbeen designated which will be. equipped with type-writers, tables, chairs and office supplies insupport of the news media objective. The auditoriumhas a 250 seat capacity, with a 300 sq. ft. raisedstage at the north end. The auditorium will beused for press conferences during the emergency,and when not used for press conferences, it will .bepartitioned into a work area and conference room.Figure 8-2 is a layout of the basement as it willbe used for a Joint Emergency News Center.

En ineerin Su ort Center ESC

The Fourth Floor at, 49 East, Avenue is normallyoccupied by the RG&E Engineering Department. Allfacilities required for the engineering functionsthat are necessary to support the Gipna plant, i.e.reproduction, word processing, drafting, records,drawings, equipment manuals, plant. technicalspecifications, FSAR, Ginna procedures, computerterminals, data displays, communications, etc. areeither located on this floor or in the building.

Revision 9 . November 1990

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During an emergency, engineering support personnelfor the plant will locate here, since such personnelare in fact Engineering Department personnel. Theywill be supplemented by outside consultants andaccommodations will be made available for thesegroups

C. Emer enc 0 e ations Facil t EOF

The basement of 49 East Avenue, a large area(approximately 3200 sq. ft.) set aside for theEmergency Operations Facility (EOF) and dedicatedfor use by emergency personnel. Federal, State andLocal agencies involved and RGSE Management assignedto the Ginna plant emergency operations locatehere. Figure 8.3 is a layout drawing of the EOFand adjacent floorspace for use by NRC.

During an emergency, the entire basement levelwill be secured for exclusive use by emergencypersonnel. Although the entire area may not berequired to cope with the emergency, it is availableif unforeseen circumstances arise.

Habitab itThese facilities are located in the opposite directionof the prevailing winds, and is such distance from theGinna plant, that radiation protection equipment is nota consideration. Building heat is supplied by thedowntown Rochester District Heating Cooperative. Electricrequirements are provided by the RG&E llKV undergrounddowntown electric network systems two circuits to 89East Avenue and one circuit to 49 East Avenue. Lavatoryfacilities are available on each floor and can accommodatethe normal work force of the buildings and any additionalemergency personnel anticipated. First Aid facilitiesare available on the first floor of 89 East Avenue andare manned during normal working hours. They can beavailable at anytime as determined by the Facilities andPersonnel Manager.

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102

8 ' cations

8.F 1 e ho e andExtensive phone communications capability exists at theRG&E Corporate main office and the 49 East Avenuebuilding. There are presently 600 telephone lines fromthe Corporate main office to the Corporate telephoneexchanges at Front and Andrews Streets (a mile distance).Each one of these lines can have several handsets atdifferent locations sharing a common circuit. The RG&ECorporate System is powered by two redundant AC powersupplies which are backed up with a motor generator andbattery uninterruptible power supply. The Corporatephone system can communicate with the Ginna plant systemover 15 two-way tie lines —9 in the RG&E wholly owned2 GHZ Microwave System —6 in New York Telephone andRochester Telephone facilities. Additional circuits tothe Ginna plant are provided by five outgoing, and fiveincoming lines provided by the New York Telephone System.

A 98 line Centrex System from RTC Central Office to theEOF and Joint News Center is totally separate from theRG&E corporate system.A direct line is connected betweenEOF dose assessment and TSC dose assessment. Also, aGinna Station telephone system line has several drops inthe EOF/Recovery Center.

A radio communications system provides the backup to theGinna phone system. The Control Room has direct contactwith Power Control by radio on a frequency of ~ 53 KHertz. Three other frequencies are available in theControl Room and Technical Support Center for the use ofFire Brigades, Radiation Survey Teams, and PlantSecurity. The use of these channels are explained inSection 6.2.3, Page 66.

The EOF/Recovery Center has access to all channels exceptsecurity and provides monitoring of the Radiation SurveyTeams during an incident.Direct contact between the EOF and the TSC or ControlRoom is possible on the 153.53 K Hertz channel in caseof phone failure.The New York State Radiological Emergency CommunicationsSystem (RECS) has drops at 14 locations across the stateconnecting Ginna Plant, TSC, EOF, 2 Counties and New YorkState Emergency Preparedness centers and State Police.

There is also a network of facsimile machines connectingkey areas as well as telephone paging units for key staffposition persons.

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103

8 ' ' Safety Assessment System and Plant Process ComputerSystem (SAS/PPCS)

The SAS/PPCS computer system at Ginna Station provideshistorical and real time plant information via displaysand hard copy devices that are located in the GinnaControl Room, the Technical Support Center, the EmergencyOperations Facility and the Engineering Support Center.The SAS and PPCS are two independent computer systems.

SAS display information is accessed solely via pushbutton requests. SAS provides the Safety ParameterDisplay System capability. SAS also provides CRT trendsof critical plant parameters.

PPCS display and report information is accessed via analpha-numeric keyboard that supports both menu drivenfunctions and push button requests. PPCS provides thelogging and archival capability.Both computer systems are designed to assist controlroom operators and emergency response personnel in thedecision making process during normal and abnormal plantconditions.

8 ' ' Records Management and AvailabilityAs previously described, all the required records andinformation necessary to support the recovery of theGinna plant in an emergency is available and up-to-dateat the EOF. Specifically, this information is locatedat 49 East Avenue in the Engineering Records Room and theTechnical Information Center (Technical Library). On adaily basis several people maintain these two sources ofinformation in a current status since these centers ofinformation are primary sources of information to boththe Engineering Department and the Ginna plant. Duringan emergency, the responsible managers of these informa-tional sources are assigned to the Technical Supportstaff to insure immediate availability of information.

8 ' and Procedure Ma tena ce

Individuals responsible for various aspects of theseplans and procedures will receive initial training andwill be retrained annually through formal sessions anddrills. The drills will check communication systems,response time, performance of participants, and interre-lations of. the various, emergency centers. Training'rills may'e held prior to any exercises. Exerciseswill be held in conjunction with Ginna Station, New YorkState and local governments as required by regulationsand Technical Specifications. ~

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All aspects of an exercise will be monitored by trainedobservers and a report made to the Nuclear Safety Auditand Review Board. Any comments will be evaluated andactions taken if appropriate.

Managers of EOF functions will evaluate their procedures,notification lists, and equipment needs annually toensure that they can meet their assigned functions.

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105

~COVERY

After the initial emergency response actions are concluded(i.e., the plant is in cold shutdown and under control),a decision to begin the recovery phase will be initiated.A number of considerations will enter into this decisionto begin the recovery phase and dismantle the EmergencyResponse Organization. The decision to enter the recoveryphase will be made by the EOF/Recovery Manager inconsultation with his Support Managers, NSARB and onsitepersonnel.

The decision to enter the recovery phase should be basedupon a comprehensive review of station parameters andconditions. These should include, but are 'not limitedto the following:1. Station parameters of operation no long indicate a

potential or actual emergency exists.2. The reactor shutdown conditions are stable.3. The reactor containment building integrity is

sufficient to meet shutdown conditions.4. The release of radioactivity from the station is

controllable and no longer exceeds permissiblelevels, and no danger to the general public fromthe above source(s) is credible.

5. Plant radioactive waste systems and decontaminationfacilities are operable to the extent needed;

6. A reactor heat sink is available and operating.

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Power supplies and electrical equipment needed forthe station to be capable of sustaining itself in along-term shutdown condition are available.The operability and integrity of instrumentation,including radiation monitor equipment needed tomaintain shutdown has been demonstrated.

9. Trained personnel and support services are availablefor station 'entry and cleanup, without workersreceiving an excess of their permissible exposures.

Federal, State and Local authorities shall be advised ofany decisions and resulting changes pertaining to theEmergency Response Organization 'status.

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Recove Actions

Re-entry of the plant, decontamination, repair, andreturn to operation will be controlled by a generalimplementing procedure which provides for development ofa flexible plan of actions and specifies particularevaluation and planning activities. A recovery organiza-tion to provide long term augmentation of the emergencyorganization has been established. Figure 8.1 showsthis organization by function of those involved. Aprocedure to alert these people and put the EOF/RecoveryCenter into operation is part of our implementing proce-dures.

RG&E personnel are assigned to the Recovery Organizationto fillthe following positions:

EOF/Recovery Manager

Nuclear Operations Manager

Engineering Support. Manager

Advisory Support Manager

Facilities and Personnel Manager

News Center Manager

EOF Dose Assessment Manager

Offsite Agency Liaison

Corporate Spokesperson

Corporate Nuclear Emergency Planner

Each of the aforementioned will have a designatedalternate and a staff assigned to assist in the event ofan accident. The EOF/Recovery Center will be activatedand manned by RG&E personnel within 1 hour after thedecision to establish an off-site recovery organizationhas been made for Site and General Emergencies. ThisOrganization would be available to assist the Plant andthe Emergency Coordinator in the event of an extendedemergency situation. The members of the Recovery Organ-ization will be given appropriate training annually.

In order for the recovery phase to commence, the condi-tions which caused the incident must no longer exist.(See Section 3.0, Emergency Conditions). If the EmergencyCoordinator, on evaluating survey data, finds no readingssignificantly above background, and on consultation withthe Operating Shift Supervisor, determines that theemergen'cy is or was local, personnel. may return to theplant.

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If off-site consequences of the occurrence were suchthat off-site support assistance was required, the RG&ENuclear Safety Audit and Review Board and the PlantOperations Review Committee must agree that the site issafe and the plant can be returned to normal operation.

The EOF/Recovery Manager will notify all responseorganizations that recovery operations are underway.

In the recovery phase, all actions will be carefullyplanned by station supervisory personnel in conjunctionwith the Recovery Team, the Technical Support Centerpersonnel and the Plant Operations Review Committee.Planning for recovery will include evaluation'f surveydata, review of exposures incurred, projection of manpowerand equipment needs, and re-entry survey team activities.Actions prescribed upon re-entry include a comprehensivesurvey of the plant to define radiological problemareas. Based on survey results, high radiation areasand areas of contamination will be isolated and posted,and, if possible, portable shielding will be used, asappropriate.

Upon evaluation of plant conditions, further activitiesfor making necessary repairs, decontamination and resto«ration to normal operations will be outlined by thePlant Operations Review Committee in accordance withstandard Health Physics practices. Personnel radiationexposure during the recovery stage of the incident shallbe closely controlled and documented. Individualexposures shall be in accordance with 10CFR20 limits.Corporate management and technical support personnelwill augment the Plant Staff in long tera recoveryoperations.

a) The Employee Relations Department has investi-gated the availability and made preliminary plansfor providing logistics support.

b) Technical Support will be provided by the NuclearEngineering Services Department and consultants underthe direction. of the Department Manager, NuclearEngineering Services.

c) The Sr. Vice President, Production and Engineering,will provide management 'evel interface withgovernment authorities. He will be assisted by theGovernmental Affairs Group.

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108

d) Communicating with the President of the Un].tedStates and the Governor of New York State, is theresponsibility of RG&E senior management.

e) The Public Affairs Department, through a series ofEPZPs, will coordinate general news releases with thegovernment authorities.

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