ACCKIERAT DOCUMENT DISTRIBUTIONSYSTEMREGULAT . INFORMATION DISTRIBUTIQ1~STEM (RIDE)

ACCESS~ION NBR:9307190252 DOC.DATE: 93/06/30 NOTARIZED: NO DOCKETFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1, Pacific Ga 05000275

50-323 Diablo Canyon Nuclear Power Plant, Unit 2, Pacific Ga 05000323AUTH.NAME AUTHOR AFFILIATION

BOURGO,E. Pacific Gas & Electric Co.STIPICEVICH,J. Pacific Gas & Electric Co.TOWNSEND,J.D. Pacific Gas & Electric Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT: Monthly operating repts for June 1993 for Diablo CanyonUnits 1 & 2.W/930715 ltr.

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE:TITLE: Monthly Operating Report (per Tech Specs)

NOTES:

RECIPIENTID CODE/NAME

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INTERNAL: ACRSAEOD/DSP/TPABNRR/DRIL/RPEBRGN5

COPIESLTTR ENCL

3 31 1

10 101 11 11 1

RECIPIENTID CODE/NAME

PDV PD

AEOD/DOANRR/DO OEABREG~ . 01

COPIESLTTR ENCL

1 '

1 11 11 1

EXTERNAL EG&G BRYCEF J ~ HNSIC

1 11 1

NRC PDR 1 1

NOTE TO ALL"RIDS" RECIPIENTS:

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24

I ~ ) g 'I

~ 0 F

V

Pacific Gas and Electric Company Diablo Canyon Power Plant

P.O. Box 56Avila Beach, CA 93424805/545-6000

John D. Townsend

Vice President-Diablo Canyon

Operations and Plant Manager

July 15, 1993

U.S. NUCLEAR REGULATORY COMMISSIONAttention: Document Control DeskWashington, DC 20555

RE: Docket No. 50-275 and 50-323License No. DPR-80 and DPR-82Monthly Operating Report for June 1993

GENTLEMEN:

Enclosed are the monthly operating report forms for Diablo Canyon Units 1 and 2 forJune 1993. This report is submitted in accordance with Section 6.9.1.7 of the Units1 and 2 Technical Specifications.

Sincerely,

T:kwr

Enclosures

cc Mr. Bobby H. Faulkenberry, Regional AdministratorU.S. Nuclear Regulatory CommissionRegion V1450 Maria Lane, Suite 210Walnut Creek, CA 94596-5268

Ms. Liz Hannon, PresidentUtilityData Institute, Inc.1700 K Street, NW, Suite 400Washington, DC 20006

9307190252 930h30l

PDR ADOCK 05000275R PDR

P

iA l'

bcc WGCROCKETI'A

TAGGARTNRC RESIDENTREG COM ENGR

104/5/506104/3/315104/5/538104/5/23B

JA SEXTONRL RUSSELLALNICHOLSONRL JOHNSON

RF LOCKERJ McDEVITTGM RUEGER

333/A1113333/A 1111333/A1111333/A1111

77/271577/148977/1445

RP POWERS 104/5/507

INPO RECORD CENTER1100 Circle 75 ParkwaySuite 1500Atlanta, GA 30339

SHERI PETERSONU.S. Nuclear Regulatory CommissionOne White Flint NorthMail Stop 13 E16Washington, DC 20555

MR. PAUL KRIPPNERTowne Center, Suite 300S29 South Main StreetW. Hartford, Connecticut 06107-2445

T

MONTHLYNARRATIVEREPORTOF OPERATION

AND MAJOR MAINTENANCEEXPERIENCE

This report describes the operating and major maintenance experience for the month of June1993. This narrative report was prepared by the Plant Staff and is submitted in accordance withSection 6.9.1.7 of the Units 1 and 2 Technical Specifications.

Na ive of Dail Si nificant Plant Events

On June 1, 1993: Unit 1 and Unit 2 started the month in Mode 1 (Power Operation)at 100% power.

On June 3, 1993: Unit 1 reduced power to 85% for load-following per the requestof the PG&E System Dispatcher (due to excess hydro capacity andreduced system loading).

Subsequently reduced power to 52% due to Main Feedwater Pump(MFWP) 1-1 stop valve inadvertent closure. MFWP 1-1 wasremoved from service.

Unit 1 was returned to 85% power after inspection of the MFWP1-1 stop valves could not determine a definitive cause for theinadvertent closure.

On June 3, 1993: Unit 2 reduced power to 78% for load-following. Unit 2 returnedto 100% power within two hours since the Unit 1 load curtailmentsdescribed above were adequate to accommodate the reducedgeneration requirements.

On June 4, 1993: Unit 1 reduced power to 50% for circulating water tunnelcleaning.

On June 5, 1993: Unit 1 reduced power to 28% for FCV-510, steam generator 1-1main feedwater valve, positioner repairs, and then returned to 50%power for completion of the circulating water tunnel cleaning.

On June 7, 1993: Unit 1 returned to 100% power following completion of thecirculating water tunnel cleaning.

On June 30, 1993: Unit 1 and Unit 2 ended the month in Mode 1 (Power Operation)at 100% power.

~~

Summa of Plant 0 eratin haracteri ties Power Reduction and nit Shutdowns

Unit 1 operated this month with a unit availability factor of 100.0% and a unit capacity factor(using MDC Net) of 93.45%. Unit 1 reduced power by more than 20%, for more than fourhours this month, three times this month for main feedwater pump stop valve repairs, circulatingwater tunnel cleaning, and steam generator main feedwater valve positioner repairs.

Unit 2 operated this month with a unit availability factor of 100.0% and a unit capacity factor(using MDC Net) of 100.76%. Unit 2 did not reduce power by more than 20% for more thanfour hours this month.

mm f i nific n fet Related Maintenance

Significant safety related maintenance for Unit 1 consisted of:

1. FCV-510, steam generator 1-1 feedwater valve, positioner repairs.

2. The pressurizer level transmitter (cold calibration) was replaced and calibrateddue to component failure.

Significant safety related maintenance for Unit 2 consisted of seal table leak repairs insidecontainment.

Actuation f earn enera r afet or Pres urizer Power era ed Relief Valves

There were no challenges to the steam generator safety valves or the pressurizer power operatedrelief valves.

~~

OPERATING DATAREPORT

PER ATIN TATUSTELEPHONE

DOCKET NO. 50-275UNIT 1

DATE 07/01/93COMPLETED BY E. Bourgo

J. Stipicevich(805) 545-3035/4877

1. Unit Name:

2. Reporting Period:

3. Licensed Thermal Power (MWt):4. Nameplate Rating (Gross MWe):5. Design Electrical Rating (Net Mwe):6. Maximum Dependable Capacity (Gross Mwe):7. Maximum Dependable Capacity (Net MWe):8. Ifchanges occur in capacity ratings (items

3 through 7) since last report, give reasons:

9. Power level to which restricted, ifany (Net MWe):10. Reasons for restrictions, ifany:

Diablo Canyon Unit 1

June 1993

3338

1137

1086

1124

1073.4

N/AN/AN/A

~Thi Month YTD4343,0

4343.0

0.0

4343.0

0.0

140228069

4725800

4501640

100.00

100.00

96.56

95.44

0,00

11 ~ Hours In Reporting Period 720.0

12. Number Of Hours Reactor Was Critical 720.0

13. Reactor Reserve Shutdown Hours 0.014. Hours Generator On-Line 720.0

15. Unit Reserve Shutdown Hours 0.0

16. Gross Thermal Energy Generated (MWH) 2256675

17. Gross Electrical Energy Generated (MWH) 759000

18. Net Electrical Energy Generated (MWH) 722261

19. Unit Service Factor 100.00

20. Unit AvailabilityFactor 100.00

21 ~ Unit Capacity Factor (Using MDC Net) 93.45

22. Unit Capacity Factor (Using DER Net) 92.37

23. Unit Forced Outage Rate 0.00

24. Shutdowns Scheduled Over Next 6 Months

(Type, Date, and Duration of Each): None.

25. IfShut Down At End Of Report Period, Estimate Date of Startup: Not applicable

Cumulative

71445.3

59955.1

0.0

59055.6

0.0

185769371

62516832

59290188

82.66

82.66

77,31

76.42

3.23

AVERAGE DAILYUNIT POWER LEVEL

TELEPHONE

DOCKET NO. 50-275UNIT 1

DATE 07/01/93COMPLETED BY E. Bourgo

J. Stipicevich(805) 545-3035/4877

June 1993 DAY

1

2345678

91011

12131415

161718

192021222324252627282930

AVERAGE DAILYPOWER LEVEL(MWe-Net)

10731073661811334458920

10801080107410771078108110811077107610771076107810731077107310771073107310781073107710771077

The average monthly Electrical Power Level for June 1993 = 1003.14 MWe-Net

UNIT SHUTDOWNS AND POWER -REDUCTIONS

DOCKET NO. 50-275UNIT 1

DATE 07/01/93COMPLETED BY K. W. RichesTELEPHONE (805) 545-3655

REPORT MONTH: June 1993 PAGE 1 OP 2

.: NO;:: ::"'."::."'':DATE :;:;::"=;.:TYPE",-""'"'".:';DUR'ATION::,':,:':;,j''',:.-:. '-';„:„;:; ""'.;;~'(HOURS);", "~

;':;: REA'SON,:,.-.":: :::i.:;~:METHOD:,':.,OF,,.''::::',

''-:;:;SHUTDOWN';,"::,:

;:,.;.;K:;ICENSEE,',:;"'"„

:,":;:.:„-"'.":„:REP,.ORT-,:.,":.:.":>.

,:;,.SYSTEM'i)::,'i.:...COMPONENT::.,;.':.-:CODEi"'"""':.:".:::''-",.-,::.,:.;:,:.:','.CODEs,:;;..:-.".::,;.

-'-:"CAUSE::&'.::CORRECTI...„....;'--;:ACTION.,TO,:;PREVENT:.',:,-.:';:;",'::

06/03/93 1.6 H None N/A N/A Reduced power to 85%power for load-following.

06/03/93

06/04/93

15.2

63.5

A

B

None

None

SJ

N/A N/A

During the load-followingpower reduction, MFWP1-1 stop valve closedinadvertently. Power wasreduced to 50% andMFWP 1-1 was removedfrom service.

Power was reduced to50% for circulating watertunnel cleaning.

1

Type:F-ForcedS-Scheduled

2Reason:A-Equipment Failure (Explain)B-Maintenance or TestC-RefuelingD-Regulatory RestrictionE-Operator Training & License ExaminationF-AdministrativeG-Operational Error (Explain)

3

Method:1-Manual2-Manual Scram3-Automatic Scram4-Continuation from

previous month5-Power reduction6-Other

4EIIS Systems List, Table 1

5IEEE Std. 803A-1983, "IEEERecommended Practice for UniqueIdentification in Power Plants andRelated Facilities - Table 2"

'I4

UNIT SHUTDOWNS AND POWER REDUCTIONS

50-275DOCKET NO.UNIT 1

DATE 07/01/93COMPLETED BY K. W. RichesTELEPHONE (805) 545-3655

REPORT MONTH: June 1993 PAGE2 OF 2

'-"::NO"':i'"i::.'„:'::'.!DATE:.::.::':.:':-.'6/05/93

"":::T'YPEi''. ,::.::.;.;DUR'ATION-'".

;,";:.;;-.:::;;(HOURS)';-.';;.':.;:,:;-:

15.0

:-„:':;.";:REA'SON,.-„:~i'; i--'-METHOD OF-:::

.'';"'„-'!SHUTDOWN„::,;„'i,„''

-;,:;-::::LICENSEE'::

„::;;:,.EVEÃF:;:;':;:;-'„-„:

:;-,i''-;-':;'''REP:,ORTI:.'„.';.-"."'one

:„::::;SYSTEM'-';-'",''

i'":::CODE',:..-:::!."'.:i

SJ

-::::::,COMPONENT;::",::,:::,

~i;CAUSE:::;Sf.'CORRECTI~,.i'-.',"'."A'CTjON::.TOPREUEY7.::~„'-'„;:',,":;,,'':,:::::. RECURRENCB';;-;:..::,:,:::-,'

Power was further reducedto 28% to make positionerrepairs on FCV-510, steamgenerator 1-1 mainfeedwater valve. FCV-510had previously exhibitedflow oscillations, and wasscheduled for repair at thenext unit curtailment withsufficient time to facilitaterepairs.

1

Type:F-ForcedS-Scheduled

2Reason:A-Equipment Failure (Explain)B-Maintenance or TestC-RefuelingD-Regulatory RestrictionE-Operator Training & License ExaminationF-AdministrativeG-Operational Error (Explain)H-Other (Explain)

3Method:1-Manual2-Manual Scram3-Automatic Scram4-Continuation from

previous month5-Power reduction6-Other

4EIIS Systems List, Table 1

5IEEE Std. 803A-1983, "IEEERecommended Practice for UniqueIdentification in Power Plants andRelated Facilities - Table 2"

OPERATING DATAREPORT

PER ATIN TATUS

DOCKET NO. 50-323UNIT 2DATE 07/01/93COMPLETED BY E. Bourgo

J. StipicevichTELEPHONE (805) 545-3035

1. Unit Name:

2. Reporting Period:

Licensed Thermal Power (MWt):4. Nameplate Rating (Gross MWe):5. Design Electrical Rating (Net MWe):6. Maximum Dependable Capacity (Gross MWe):7. Maximum Dependable Capacity (Net MWe):8. Ifchanges occur in capacity ratings (items

3 through 7) since last report, give reasons:

9. Power level to which restricted, ifany (Net MWe):10. Reasons for restrictions, ifany:

Diablo Canyon Unit 2

June 1993

3411

1164

1119

1137

1087

N/AN/AN/A

~Thi M nth YTD4343.0

2967.8

0.0

2909.2

0.09552989

3193200

3032936

66.99

66.99

64.25

62.41

2.48

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MVM)17. Gross Electrical Energy Generated (MWH)18. Net Electrical Energy Generated (MWH)19. Unit Service Factor

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net)22. Unit Capacity Factor (Using DER Net)

23, Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months

(Type, Date, and Duration of Each): None.

25. IfShut Down At End Of Report Period, Estimate Date of Startup: Not applicable.

~1m i~i/i

64004.

53802.

0.

52914.

0.

17285481

5753859

5466653

82.6

82.6

78.7

76.3

4.2

AVERAGE DAILYUNIT POWER LEVEL

TELEPHONE

DOCKET NO. 50-323UNIT 2DATE 07/01/93COMPLETED BY E. Bourgo

J. Stipicevich(805) 545-3035/48

June 1993 DAY

1

2345678

91011

1213

14

15

161718192021222324252627282930

AVERAGE DAILYPOWER LEVEL(MWe-Net)

109711011080110110971101109610981093109510961097109610971096109610961096109610961093108810881093109710921096109710961096

The average monthly Electrical Power Level for June 1993 = 1095.24 MWe-Net

"I

UNIT SHUTDOWNS AND POWER REDUCTIONSDOCKET NO.UNITDATECOMPLETED BYTELEPHONE

REPORT MONTH: June 1993

50-323207/01/93K. W. Riches(805) 545-3655

None

;::;:O'ATE:-:,.:,: .'--.'.':,iYiE!":':;::,'':::;:::.-.':::DURATION.:;,-'„':':;RE'A'S;ON',,;='::;,'""'-..,".METHOD,-'OF@':::;:::-'::;:.':SHUTDOWN',;.!;

"';:

!„':',:.LICENSEE;;::::,'-::

';,.„"-';.',"',,EVENT.:;:".::.„'.

~";;;:;;:.",REPORT„"::-.":;.i'".,:

::::;:SYSTEM'''"';

;:;.;::'-,::;CODE4;::;".;-;,::;

:,'';COMP,'OiiENT--':: "'"'."::,:,:-',."'.'-''CORRECTIVE-'.:.".;::,.;";!"'-'-

COD'Es':;'::.:':::..:'.::'::'.:.::.::"::::-:::;::;:::A'CTION:TO PREVENi;..:ii';;:-'::;:":;i';-'l.";,::-:.:,';":,:;:'.'::.:,.,:.:,':::::-;.;:;-":..;.',"..:;,'„''-"„RECURRENCB;-':;-;-";;-':.";:-'

Type:F-ForcedS-Scheduled

2Reason:A-Equipment Failure (Explain)B-Maintenance or TestC-RefuelingD-Regulatory RestrictionE-Operator Training Ec License ExaminationF- AdministrativeG-Operational Error (Explain)H-Other (Explain)

3

Method:1-Manual2-Manual Scram3-Automatic Scram4-Continuation from

previous month5-Power reduction6-Other

4EIIS Systems List, Table 1

5IEEE Std. 803A-1983, "IEEERecommended Practice for UniqueIdentification in Power Plants andRelated Facilities - Table 2"

REFUELING INFORMATIONREQUEST

DOCKET NO. 50-275UNIT 1

DATE 07/01/93COMPLETED BY M. L. Mayer

K. W. RichesTELEPHONE (805) 545-4674/3655

1. Name of facility: Diablo Canyon Unit 1

2. Scheduled date for next refueling shutdown: March 5, 1994 (estimated).

3. Scheduled date for restart following refueling; May 2, 1994 (estimated).

4 Willrefueling or resumption of operation thereafter require a technical specificationchange or other license amendment? Ifanswer is yes, what, in general, will there be?Ifanswer is no, has the reload fuel design and core configuration been reviewed byyour Plant Safety Review Committee to determine whether any unreviewed safetyquestions are associated with the core reload (Ref. 10 CFR Section 50.59)? Ifno suchreview has taken place, when is it scheduled?

No. The PSRC is scheduled to review the cycle 7 core reload on April 4, 1994(estimated).

5. Scheduled date(s) for submitting proposed licensing action and supporting information:N/A

6. Important licensing considerations associated with refueling, e.g., new or differentfuel design or supplier, unreviewed design or performance analysis methods,significant changes in fuel design, new operating procedures: N/A

7. As of May 31, 1993, the number of fuel assemblies (a) in the core and (b) in the spentfuel storage pool were:

(a) 193 (b) 376

8. The present licensed spent fuel pool storage capacity and the size of any increase inlicensed storage capacity that has been requested or is planned, in number of fuelassemblies:

Present 1324 Increase size by 0

9. The projected date of the last refueling that can be discharged to the spent fuel poolassuming the present licensed capacity: 2006 (Loss of full core offload capability).

REFUELING INFORMATIONREQUEST

DOCKET NO. 50-323UNIT 2DATE 07/01/93COMPLETED BY M. L. Mayer

K. W. RichesTELEPHONE (805) 545-4674/3655

1. Name of facility: Diablo Canyon Unit 2

2. Scheduled date for next refueling shutdown: September 15, 1994 (estimated).

3. Scheduled date for restart following refueling: November 6, 1994 (estimated).

4 Willrefueling or resumption of operation thereafter require a technical specificationchange or other license amendment? Ifanswer is yes, what, in general, will there be?Ifanswer is no, has the reload fuel design and core configuration been reviewed byyour Plant Safety Review Committee to determine whether any unreviewed safetyquestions are associated with the core reload (Ref. 10 CFR Section 50.59)? Ifno suchreview has taken place, when is it scheduled?

No. The PSRC reviewed and approved the cycle 6 core reload on March 10, 1993.

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A

6. Important licensing considerations associated with refueling, e.g., new or differentfuel design or supplier, unreviewed design or performance analysis methods,significant changes in fuel design, new operating procedures: NA

7. As of May 31, 1993, the number of fuel assemblies (a) in the core and (b) in the spentfuel storage pool were:

(a) 193 (b) 396

8. The present licensed spent fuel pool storage capacity and the size of any increase inlicensed storage capacity that has been requested or is planned, in number of fuelassemblies:

Present 1324 Increase size by 0

9. The projected date of the last refueling that can be discharged to the spent fuel poolassuming the present licensed capacity: 2006 (Loss of full core offload capability).

tI

~ pL

V II

+14