crystal river, unit 3 - license amendment request #310, revision … · 2012-12-01 · progress...

Progress EnergyCrystal River Nuclear PlantDocket No. 50-302Operating License No. DPR-72

Ref: 10 CFR 50.90

February 26, 20093F0209-06

U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001

Subject: Crystal River Unit 3 - License Amendment Request #310, Revision 0:Application to Adopt Technical Specifications Task Force (TSTF) TravelerTSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCSSpecific Activity Technical Specification"

Reference: The B&W Owners Group to Nuclear Regulatory Commission Letter datedSeptember 13, 2005, "TSTF-490, Revision 0, 'Deletion of E Bar Definition andRevision to RCS Specific Activity Tech Spec"'

Dear Sir:

In accordance with the provisions of Section 50.90 of Title 10 of the Code of FederalRegulations (10 CFR), Florida Power Corporation (FPC), doing business as Progress EnergyFlorida, Inc., is submitting a request for an amendment to the Improved Technical Specifications(ITS) for Crystal River Unit 3 (CR-3). The proposed changes would replace the current ITS3.4.15 limit on RCS gross specific activity with a new limit on RCS noble gas specific activity.The noble gas specific activity limit would be based on a new dose equivalent Xe-133 definitionthat would replace the current E Bar average disintegration energy definition. In addition, thecurrent dose equivalent 1-131 definition would be revised to allow the use of additionalCommitted Effective Dose Equivalent dose conversion factors.

The changes are consistent with NRC-approved Technical Specification Task Force (TSTF)Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCSSpecific Activity Tech Spec." The availability of this Technical Specification improvement wasannounced in the Federal Register on March 19, 2007 (72 FR 12838), "Notice of Availability ofModel Application Concerning Technical Specification Improvement Regarding Deletion of EBar Definition and Revision to Reactor Coolant System Specific Activity TechnicalSpecification Using the Consolidated Line Item Improvement Process."

Attachment A provides a description and assessment of the proposed changes, as well asconfirmation of applicability. Attachment B provides the existing ITS pages and ITS Basesmarked-up to show the proposed changes. Attachment C provides final ITS pages and ITS Basespages.

No new regulatory commitments are being made in this submittal.

Progress Energy Florida, Inc.Crystal River Nuclear Plant15760 W. Powerline StreetCrystal River, FL 34428

U.S. Nuclear Regulatory Commission3F0209-06 of 3

The CR-3 Plant Nuclear Safety Committee has reviewed this request and recommended it forapproval.

FPC requests approval of the proposed license amendment by June 30, 2009 with the amendmentto be implemented during Refuel 17, scheduled for Fall 2011. This LAR is required to supportsubmittal of the EPU LAR. It has been determined to be a linked submittal for the EPU LAR perOffice of Nuclear Reactor Regulation (NRR) Office Instruction LIC-109, "Acceptance ReviewProcedures."

In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being providedto the designated State of Florida Official.

If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Supervisor,Licensing and Regulatory Programs at (352) 563-4796.

(~ ~

'Dale E. YoungVice PresidentCrystal River Nuclear Plant

DEY/par

Attachments: A. Description and AssessmentB. Proposed Improved Technical Specification Changes (Strikeout and

Shadowed Text Format)C. Proposed Improved Technical Specification Changes (Revision Bar Format)

xc: NRR Project ManagerRegional Administrator, Region IISenior Resident InspectorState ContactITSB Branch Chief

U.S. Nuclear Regulatory Commission3F0209-06 of 3

STATE OF FLORIDA

COUNTY OF CITRUS

Jon A. Franke states that he is the Director Site Operations, Crystal River Nuclear Plant

for Florida Power Corporation, doing business as Progress Energy Florida, Inc.; that he is

authorized on the part of said company to sign and file with the Nuclear Regulatory Commission

the information attached hereto; and that all such statements made and matters set forth therein

are true and correct to the best of his knowledge, information, and belief.

Jon A. FrankeDirector Site OperationsCrystal River Nuclear Plant

The foregoing document was acknowledged before me this day of

2009, by Jon A. Franke.

S&L/~1Signature of Notary PublicState Q io-ida

. .... CAROLYN E. PORTrMANNNotary Public - State of FloridaCommission Expires Mar 1, 2010

. •7~- Commission # DD 524380Bonded 8By National Notary Assn.(

(Prinitjy~e,-or-stap con'mirrssioncuName of Notary Public)

Personally ProducedKnown _,_-__ -OR- Identification

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3

DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72

LICENSE AMENDMENT REQUEST #310, REVISION 0

APPLICATION TO ADOPT-TECHNICAL SPECIFICATIONSTASK FORCE (TSTF) TRAVELER TSTF-490, REVISION 0,

"DELETION OF E BAR DEFINITION AND REVISION TO RCSSPECIFIC ACTIVITY TECHNICAL SPECIFICATION"

ATTACHMENT A

DESCRIPTION AND ASSESSMENT

U.S. Nuclear Regulatory Commission Attachment A3F0209-06 Page 1 of 3

Description and Assessment

1.0 DESCRIPTION

This letter is a request to amend Operating License DPR-72 for Crystal River Unit 3(CR-3).

The proposed changes would replace the current limits on primary coolant gross specificactivity with limits on primary coolant noble gas activity. The noble gas activity wouldbe based on DOSE EQUIVALENT XE-133 and would take into account only the noblegas activity in the primary coolant. The changes were approved by the NuclearRegulatory Commission (NRC) staff Safety Evaluation (SE) dated September 27, 2006(ADAMS ML062700612) (Reference 1). Technical Specification Task Force (TSTF)change traveler TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision toRCS Specific Activity Tech Spec" was announced for availability in the Federal Registeron March 19, 2007 (72 FR 12838) as part of the consolidated line item improvementprocess (CLIIP).

2.0 PROPOSED CHANGES

Consistent with NRC-approved TSTF-490, Revision 0, the proposed ITS changes are asfollows:* Revise the definition of DOSE EQUIVALENT 1-13 1.* Delete the definition of"E Bar, AVERAGE DISINTEGRATION ENERGY.* Add a new TS definition for DOSE EQUIVALENT XE-133.* Revise LCO 3.4.15, "RCS Specific Activity" to delete references to gross specific

activity; add limits for DOSE EQUIVALENT 1-131 and DOSE EQUIVALENTXE-133; and delete Figure 3.4.15-1, "Reactor Coolant DOSE EQUIVALENT 1-131Specific Activity Limit versus Percent of RATED THERMAL POWER."

* Revise LCO 3.4.15 "Applicability" to specify the LCO is applicable in MODES 1, 2,3, and 4.

* Modify ITS 3.4.15 ACTIONS Table as follows:A. Condition A is modified to delete the reference to Figure 3.4.15-1, and define an

upper limit that is applicable at all power levels.B. ACTIONS are reordered, moving Condition C to Condition B to be consistent

with the Writer's Guide.C. Condition B is modified to provide a Condition and Required Action for DOSE

EQUIVALENT XE-133 instead of gross specific activity. The Completion Timeis changed from 6 hours to 48 hours. A Note allowing the applicability of LCO3.0.4.c is added, consistent with the Note to Required Action A. 1.

D. Condition C is modified based on the changes to Conditions A and B and toreflect the change in the LCO Applicability.

* Revise. SR 3.4.15.1 to verify the limit for DOSE EQUIVALENT XE-133. A Note isadded, consistent with SR 3.4.15.2 to allow entry into MODES 2, 3, and 4 prior toperformance of the SR.

* Delete SR 3.4.15.3.


3.0 BACKGROUND

The background for this application is as stated in the model SE in NRC's Notice ofAvailability published on March 19, 2007 (72 FR 12838), the NRC Notice for Commentpublished on November 20, 2006 (71 FR 67170), and TSTF-490, Revision 0.

4.0 TECHNICAL ANALYSIS

In the model SE, the NRC included statements that would require Florida PowerCorporation (FPC) to identify specific information in support of adopting TSTF-490.The following provides the CR-3 specific information in this regard.

1. Section 3.1.1 of the model SE includes a list of acceptable dose conversion factors(DCF) for use in the determination of dose equivalent iodine (DEI) in relation to doseconsequence analysis. The CR-3 analyses employ Committed Effective DoseEquivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal GuidanceReport No. 11, "Limiting Values of Radionuclide Intake and Air Concentration andDose Conversion Factors for Inhalation, Submersion, and Ingestion."

2. In the first paragraph of Section 3.1.2 of the Model SE, a bracketed list of isotopes isprovided that designates the noble gases that may be used in the determination ofdose equivalent xenon (DEX). All isotopes depicted within these brackets arecurrently considered in the CR-3 calculation of, DEX. This is reflected in theproposed CR-3 definition Of DEX.

3. Section 3.1.2 of the model SE also provides two possible determination methods forDEX. CR-3 uses the effective dose conversion factors for air submersion listed inTable 111.1 of EA Federal Guidance Report No. 12, 1993, "External Exposure toRadionuclides in Air, Water, and Soil." This is also reflected in the proposed CR-3definition of DEX.

4. Section 3.1.3 of the model SE states that it is incumbent on the licensee to ensure thatthe site specific limits for both DEI and DEX are consistent with the current steamgenerator tube rupture (SGTR) and main steam line break (MSLB) radiologicalconsequence analyses. CR-3 is requesting this LAR for post EPU conditions whichwill be 0.35 ýiCi/g for DEI and 646 gCi/g for DEX as depicted in the proposed CR-3ITS pages. These proposed changes will be implemented prior to the end of Refuel17, scheduled for Fall 2011.

FPC, doing business as Progress Energy Florida, Inc., has reviewed References 1, 2 and3, and the model SE published on November 20, 2006 (71 FR 67170) as part of theCLIIP Notice for Comment. FPC has applied the methodology in Reference 1 to developthe proposed TS changes. FPC has also concluded that the justifications presented inTSTF-490, Revision 0, and the model SE prepared by the NRC staff are applicable toCR-3, and justify this amendment for the incorporation of the changes to the CR-3Improved Technical Specifications (ITS).


5.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatoryrequirements and guidance was provided in the NRC Notice of Availability published onMarch 19, 2007 (72 FR 12838), the NRC Notice for Comment published on November20, 2006 (71 FR 67170), and TSTF-490, Revision 0.

5.0 NO SIGNIFICANT HAZARDS CONSIDERATION

FPC has reviewed the proposed no significant hazards consideration determinationpublished in the Federal Register on March 19, 2007 (72 FR 12838) as part of the CLIIP.FPC has concluded that the proposed determination presented in the notice is applicableto CR-3 and the determination is hereby incorporated by reference to satisfy therequirements of 10 CFR 50.91(a).

7.0 ENVIRONMENTAL EVALUATION

FPC has reviewed the environmental consideration included in the model SE published inthe Federal Register on March 19, 2007 (72 FR 12838) as part of the CLIIP. FPC hasconcluded that the staff's findings presented therein are applicable to CR-3 and thedetermination is hereby incorporated by reference for this application.

8.0 REFERENCES

1. NRC Safety Evaluation (SE) approving TSTF-490, Revision 0, dated September 27,2006

2. Federal Notice for Comment published on November 20, 2006 (71 FR 67170)

3. Federal Notice of Availability published on March 19, 2007 (72 FR 12838)




LICENSE AMENDMENT REQUEST #310, REVISION 0

APPLICATION TO ADOPT TECHNICAL SPECIFICATIONSTASK FORCE (TSTF) TRAVELER TSTF-490, REVISION 0,


ATTACHMENT B

PROPOSED IMPROVED TECHNICAL SPECIFICATIONCHANGES

(STRIKEOUT AND SHADOWED TEXT FORMAT)

Definitions1.1

1.1 Definitions (continued)

CONTROL RODS

CORE ALTERATION

CORE OPERATING LIMITSREPORT (COLR)

CONTROL RODS shall be all full length safety andregulating rods that are used to shut down thereactor and control power level during maneuveringoperations.

CORE ALTERATION shall be the movement of any fuel,sources, or other reactivity control components,within the reactor vessel with the vessel headremoved and fuel in the vessel. Suspension ofCORE ALTERATIONS shall not preclude completion ofmovement of a component to a safe position.

The COLR is the unit specific document thatprovides cycle specific parameter limits for thecurrent reload cycle. These cycle specific limitsshall be determined for each reload cycle inaccordance with Specification 5.6.2.18. Plantoperation within these limits is addressed inindividual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQU••ALENT I . 3-- sh1all be IIthat Uoncentrationof I 131 (111[%- ocuI es/grarn) that alone wouldproduce the same thyroid dose as the iuant-I-ty-andisotopi miture 31 I 1:32, i 133, --and 1 135 actually prcsentL. The thyroid doseIonveision factors used for this Iallulation shall

be those listed in international Committee ontRadiation Protection EICRP) 30, Supplement to Part1, page 192 21:2, Table titled, "Committed DosEquivalent in Target Organs or Tissues per intakeof Unit Acttvitv." DOSE EOUIVALENT T-131 shllh

1

(continued)

Crystal River Unit 3 1.1-3 Amendment No. 1-4-9

rL A% [RAG[L -- 1% V I--I -•

Definitions

Xe-135m-, X-e~- 15, and Xke--1-3-8- ac-tua]]y present.If a sp~ecific no~ble gas nuclide is not detected,,,it shouldbe assumed toe• e present at the mnimum

,etectable activity.- Th'determination of DOSE)EQUIVALENT XE *133~ ' ha]T -bepe'rform~ed using,effective dose con'viersion~ factors for ailrL-ýsubmiersion ]isted in Table 111.1 of EPA. Fed~eral1_Guidatnce Report NJo.-112, 1993; "External Exposrto Radionuclide~s" ir~j~ater, and Soil~

EI shall be the average (weighted in poototo th@ concentration of aeah radionuclide in thereactor coolant at the time of sampling) oftesum of the average beta and gamma enrie "edisintegration (in M.V) for t other thaniodines, with half lives5 15 10inute@S , making u-pat least 95% of the total non iodine activity inthe coolant.

EFPD shall be the ratio of the number of hoursof production of a given THERMAL POWER to24 hours, multiplied by the ratio of the givenTHERMAL POWER to the RTP. One EFPD is equivalentto the thermal energy produced by operating the

uttstN I tbK~A! t UN tNtltb.y

EFFECTIVE FULL POWERDAY (EFPD)

(continued)


RCS Specific Activity3.4.15

3.4 REACTOR COOLANT SYSTEM (RCS)

3.4.15 RCS Specific Activity

LCO 3.4.15 The speczificz activity of the reactor coolant RCS DOSEEQU~IVALENT 1131 and DOSE EQUIVALENTF XE-133 specificactivity shall be within limits.

APPLICABILITY: MODES 1- and 2, 1, 2, 3,, and 4MOD[ 3 with RCS average tempe rat ure(T--GF-

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. DOSE EQUIVALENT 1-131 ------------- NOTE-------> 1.-0 - Cil-tg not LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hoursEQUIVALENT, -131within the acceptable

Figure 3.4.15 1 21

ipCi/g.

AND

A.2 Restore DOSE 48 hoursEQUIVALENT 1-131 towithin limit.

Xi Inot wiIthin LCO 3.0.4.c is appli .abeIe

limit .• ---.---- --- .---. -- -- -- -

B.1 Restore DOSE 48 hoursEQUIVALENT XE-133 towithi n li mit.

(continued)

Crystal River Unit 3 3.4-30 Amendment No. 21-5


ACTIONS (conti nued)


B5,. Required Action and O.1 Be in MODE 3 with 6 hoursassociated Completion - < -5-O2F.Time of Condition AfB: not met. AND

OR C 2> _T Beours:E7

DOSE EQUIVALENT 1-131in the unacceptableregion of Fiur

C. Gross specific C.1 Perform SR 3.4.15.2.. 4-hoursacivity %of th-e

coolant not within AND

C.2 Be in MODE 3 with6hor

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.4.15.1 V e r Ify r eaco cool ,t UU1ant14- gIros55s spiecific

Only yrf4Ui red to be performed i n 7MODE1.--------------------------------------

Veify reactor coolant D~OSE E~QUIVALENT 7 days

E-133 .acivit < 646 .Ci-/g. .

SR 3.4.15.2 ------------ NOTE---------Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days

1-131 specific activity • pj~~Ci/g.

AND

Between 2 and

6 hours after

THERMAL POWER

change of Ž! 15%

RTP within a

1 hour period



SURVEILLANCE REQUIREMENTS (continued)


SR 3.4.15.3 NOTENot required to be performed until 31: daysrafter a mnimum of 2 [FPD and 20 days ofMODE 1 operation have elapsed since thereactor was last subcritical for-ý1 48• hourIsII. Il~I I •. L rJ (;IIL £ I(L • U

ýýi UI; I III I I [Il 1 L.



E250

-.-

i--

S 200

U_

C1.CnLU"

'-- 150

00

0I,... -

C)

50

'< 100

,--

LU

0

=1Uf)0

\z

___ - UNACCEPTABOPERATIC

ACCEP BLEOPE lION___ __ _ _ _

0

PER4CdENT R RATH THEIAL OWER U ,uu

Figure 3.4.15-1 (page 1 of 1)React Coolant DOSE EQUIVALENT 1-131 Specific Activity imit

Versu Percent of RATED THERMAL POWER With Reactor Coo •tSpecific Activity >1.0 pCi/gm DOSE EQUIVALENT 1-131

vstal River Unit 3 3.4-33 Amendment No.Cr 149

Complete Replacement of the Existing 3.4.15 Bases

RCS Specific ActivityB 3.4.15

B3. _47_REACTaR CO'O&LAT SYSTEM -0ýCS)j

B3747f5RCSpecjfi7vctiI ty

BW5E'S

BAýKRGUROND The maximum~ d ose7T~ thti ni___ at thie exclusion dr-bounda.ry cani receive for 2 hours following ~an accident, rathe low population Zone outer bOLundary for the ~radiologicalrelease duration, is speci~fied in 10Q CFR~ 50.67 (Ref. 1). Doses,to control~ room operators ~must be W1imited per GDC 19. Thelimits on specific ac~tivity ensu~eta the offsite and con'tr6T,room doses are appropriatel li~ted during analyzed transientsand accidents.

The RCS s IeI fiJ c acti viT~ tyLO miT th& t T6alI wbl e,concentration~ level of radionuclides in the~ reactor coo~lant.,dthe LWO limits are established to minim~ize ~the dose-]consequences-rn the event of a steam line break (SLB)or sýte~am

_eerator tube rupture_(S¶LRY-accddent.'

L7~T~ CO cont-ai-in--s. sp'e-ifi'c,,a-c-tivitI sfrIohL5~EQUIVALENT 17-131 anhd DOSE EQUIEVALENT XE-1-33.~ The atlow'a5Td!levels are intended to ensure that offsite and control roomidoses meet the~ appropri .ateacceptance criteri .a i the S~tanda-r-R'eview _Plan (Ref. 2).

-The -aaly-ses Kflor the SLB an~d 'SGTR ý_aec~ide ris- esrtWflls~h the.acceptance liiamt's'for_ RCS ,;spec'if;i*,c ,-ýactivity. Referenjý to1h e'se' analyses 'is 'used lto Iassess e'hanhges t6totthe 'itit tat1co..uld affect' RCS ~specific_- acti .vi .ty,1 .as they relate to the

(continued)

Crystal River Unit 3 B 3.4-71 Revision No. 3-7ý


RCS Specific Activity

B 3.4.15

OPcases of' ,jtU7reac~tor cýooIaiiSAFETY ANALYSES iodine, specific activity. One case, assumes, spe-Ci fi cF(conti nued) , activty at 0.35 pCi]/g DOSE EQUIVALENT. 1-131 with ah

concurrent larg& iodIne spike that increases ',the, ,rate oý frelease of iodine from the fuel rods contai ning- claddihng-

-- decfects to the' primary coolant immedi-ate~ly; a',fter .a-SLB -(jbv5',a factor of 500.),. or SGTR (by a factor , of, ,335), _ _

[r.espectively: The second case assumes "the initil eacrtcoolant iodiHne activity at 21.0 6c•/g. DOSE EQUIVALENT7 1311Sue to an iodine spike caused dbya reactor or an 'RCS

tnaIs0 p.ori•ot..the a~ci&e , In both cases, t~he'moS1egas sgi fic ac~tivity is assumed to be. 4 ii/~gas cspec •~~a .... sapOzoDOSEEQUIVAL" NT, , XE- - 13 3.

The SGTR~ diily assumes a rilse -ThprDeýsLsure in tfheruptured SG causes radioactively contam Iinaed steam toidtscharge to the atmosphere through the atmosphterc ldumpvalves or the main steam safety valves. The atmosphericdischarge stops when theturbine bypas~s to the conden 'se 'r'removes the excess eneg~y to ra~pidly reduce the RCSpressure and close the valves. The unaffected Grmvscore decay heat by ven~tinp'g steam until the cooldown e -nds;a nd the Decay Heat Remioval (DHR) system is_ place in'service.

~TheSL~B radýT -1 og-i Cl anal ysi s assumie s t~at-6f f ste~, oiwe~r sJ os t a~t the same time as the pip bireak occurs outside7''containment. The, affected SC blows down complete~ly a':steam is vented directly to the atmodsphere. ,The unaffecý-ted&CG''removes core devcay heat by venting steam to th4___tamshr ~unti~l the cool~down ends ~and the ~DHR ~systm~~plIaced in' se rviceý.

Jpra greate Eh i1th&eLCO -limit i~s permissible, if the ýacti v ity leel do t!'exicgd__ZLQpjO .for more than ~48, .hours.

T 1- TW -m-1 -fts o n R-CS s~p'e -c i fi-c-fi~ Vitt ya re-& aT W6-sii- f0establishi~ng stanidard~ization in raditaion shielding~andplaqnt,_per'sonnel ~radiation protection prctices.i

RCS specifi1c acti vity Safi sf i esCHtriT 2o `0 F50.36(c) (2) (1J) .. o~ f.IOC

(continued)

Crystal River Unit 3 B 3.4-72 Revision No. 55



ICCUA ~tat te' al'cuT~ aed does are wi TmFin ~_ Violation of the Ce maypresult' in reacterccrtlanee

Lradioactivity levels that ~could, fin ~the- event 'of a7-S[B-OHLKSTR, lead to doses that exc~eed> the. SRP, a~cceptance cri~te~rsiL(Ref. 2)j

-Pr DOSE, EQU.VALNT 1-131 and DOSE EQUIVALENT•;XE-133 is,__necesisary to limit the poten~tia~l cons~equences of'a S'LB_'O-6T towthnthe SRP acceptance cri~teria (RLIY._.2_

In MODES 5 n ~i~6, the steamn gener'ato6rs are n6-ft be-g usedý6,for decay heat removal~, the RCS and. steam geeatr ar'dpesrzd anid primary. to ~secondary leakage is ~minimial.T~herefore, thea Imonitoring of RCS specific -ac~tivity isntrequire.~

AC-TIONS §A. I and A.2

With the DO@SE EQUIVALENT 1-131 great~er than the LCO li-mi-t,samples at *interv~als o~f 4 hours mu~st be takenf todiemonstrate that the specific activity is < 21.0 P~i/g.The Comple~tion~ Time of 4 hours is requi red to ~ob~tai~n and'lanalyze a. sample. ~SaW i ngis continued every 4 hiours to,provide_ a tr'end.,

~The D0SE'EQUIV'ALENT T-131 must be restored to w~hniiiIwithin 48 hours. The CompletionTime of 48 hours ~i S'"acceptable s~ince it is expected that, if therewere~a,odine spike, the normal coolant iodine concentration W6ýldberestored ý.Ithin this time period. Also, ther~e is a low

prob'abil-ity of a SIB or SGT~R ocurndrnti ie-'p -------

r"iodd

(conti nued)

Crystal River Unit 3 B 3.4-73 Revision No. 3-7

Complete Replacement of the Existing 3.4.15 Bases TRCS Specific Activity

B 3.4.15

BASIES

(conti nued)

Crystal River Unit 3 B 3.4-74 Revision No. -3-7

I Complete Replacement of the Existing 3.4.15 Bases IRCS Specific Activity

B 3.4.15

BA~SES~

ýSURVEILLANCE SR 3.4.15~.1 (contir'dREQUIREMENTS5_________________

_____

Trending the results of thiTs iurVeiillance-aTlows pro6perFremedial action to be taken ~bef~re 'reachi ng the LCOijlimi tunider normal operating condi ti~ons. ~TIe 7 da Frequen~cy,

conides te low probability- of a gross fuel failu~reduring this time.

1 his allows the Su rveilI Iance' 'to' be performed in thoseMODES>, phio to enteffi ng MODEJ1

SR 3.4.15.

,in MODE 4, 'MODE 3, and MODE,2, prior to performi~ng theSR.,,This allows the SUreillance to'I be -prormedIn those'

(conti nued)

Crystal River Unit 3 B 3.4-75 Revision No. -3-7



FEf'FER~ENCE-S -: . £07- CFR-5--0767.ý

2. Sfdnsdrei ew, "U P1an S'e etia-Sou1m5s071 7"Radi76g caConseq uence Analyses Usjng__Altrnative Source Teis"

W3. FSAR Sec-Tio-n 14.22.-27,_ Gneip- uhThir rci ent"

Crystal River Unit 3 B 3.4-76 Revision No. 3-7




LICENSE AMENDMENT REQUEST.#310, REVISION 0

APPLICATION TO ADOPT TECHNICAL SPECIFICATIONSTASK FORCE (TSTF) TRAVELER TSTF-490, REVISION 0,


ATTACHMENT C

PROPOSED IMPROVED TECHNICAL SPECIFICATIONCHANGES

(REVISION BAR FORMAT)

Definitions1.1

1.1 Definitions (continued)

CONTROL RODS

CORE ALTERATION

CORE OPERATING LIMITSREPORT (COLR)

DOSE EQUIVALENT 1-131

DOSE EQUIVALENT XE-133

EFFECTIVE FULL POWERDAY (EFPD)

CONTROL RODS shall be all full length safety andregulating rods that are used to shut down thereactor and control power level during maneuveringoperations.

CORE ALTERATION shall be the movement of any fuel,sources, or other reactivity control components,within the reactor vessel with the vessel headremoved and fuel in the vessel. Suspension ofCORE ALTERATIONS shall not preclude completion ofmovement of a component to a safe position.

The COLR is the unit specific document thatprovides cycle specific parameter limits for thecurrent reload cycle. These cycle specific limitsshall be determined for each reload cycle inaccordance with Specification 5.6.2.18. Plantoperation within these limits is addressed inindividual Specifications.

DOSE EQUIVALENT 1-131 shall be that concentrationof 1-131 (microcuries per gram) that alone wouldproduce the same dose when inhaled as the combinedactivities of iodine isotopes 1-131, 1-132, 1-133,I-134,and I-135 actually present. Thedetermination of DOSE EQUIVALENT 1-131 shall beperformed using Committed Dose Equivalent (CDE) orCommitted Effective Dose- Equivalent (CEDE) doseconversion .factors from Table 2.1 of EPA FederalGuidance Report No. 11.

DOSE EQUIVALENT XE-133 shall be that concentrationof Xe-133 (microcuries per gram) that alone wouldproduce the same acute dose to the whole body asthe combined activities of noble gas nuclidesKr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present.If a specific noble gas nuclide is not detected,it should be assumed to be present at the minimumdetectable activity. The determination of DOSEEQUIVALENT XE-133 shall be performed usingeffective dose conversion factors for airsubmersion listed in Table III.1 of EPA FederalGuidance Report No. 12, 1993, "External Exposureto Radionuclides in Air, Water, and Soil."

EFPD shall be the ratio of the number of hoursof production of a given THERMAL POWER to24 hours, multiplied by the ratio of the givenTHERMAL POWER to the RTP. One EFPD is equivalentto the thermal energy produced by operating the

(continued)

Crystal River Unit 3 1.1-3 Amendment No.


3.4 REACTOR COOLANT SYSTEM (RCS)

3.4.15 RCS Specific Activity

LCO 3.4.15 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133specific activity shall be within limits.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS


A. DOSE EQUIVALENT 1-131 --------- NOTE----------not within limit. LCO 3.0.4.c isý applicabl-e.

A.1 ýVerify DOSE' Once per 4 hoursEQUIVALENT 1-131 < 21PCi/g.

AND

A.2 Restore DOSE 48 hoursEQUIVALENT 1-131 towithin limit.

B. DOSE EQUIVALENT ------------- NOTE-----------XE-133 not within LCO 3.0.4.c is applicable.limit.

B.1 Restore DOSE 48 hoursEQUIVALENT XE-133 towithin limit.

(conti nued)



ACTIONS (continued)


C. Required Action and C.1 Be in MODE 3. 6 hoursassociated CompletionTime of Condition A ANDor B not met.

OR C.2 Be in MODE 5. 36 hours

DOSE EQUIVALENT 1-131> 21 pCi/g.

SURVEILLANCE REQUIREMENTS


SR 3.4.15.1 ------------------- NOTE ------------------Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 daysXE-133 specific activity < 646 pCi/g.

SR 3.4.1'5.2 ------------------- NOTE------------------Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days1-131 specific activity < 0.35 pCi/g.

AND

Between 2 and6 hours afterTHERMAL POWERchange of > 15%RTP within a1 hour period

I



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RCS Specific Acti vi tyB 3.4.15

B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.15 RCS Specific Activity

BASES

BACKGROUND The maximum dose that an individual at the exclusion areaboundary can receive for 2 hours following an accident, or atthe low population zone outer boundary for the radiologicalrelease duration, is specified in 10 CFR 50.67 (Ref. 1). Dosesto control room operators must be limited per GDC 19. Thelimits on specific activity ensure that the offsite and controlroom doses are appropriately limited during analyzed transientsand accidents.

The RCS specific activity LCO limits the allowableconcentration level of radionuclides in the reactor coolant.The LCO limits are established to minimize the doseconsequences in the event of a steam line break (SLB) or steamgenerator tube rupture (SGTR) accident.

The LCO contains specific activity limits for both DOSEEQUIVALENT 1-131 and DOSE EQUIVALENT XE-133. The allowablelevels are intended to ensure that offsite and control roomdoses meet the appropriate acceptance criteria in the StandardReview Plan (Ref. 2).

APPLICABLESAFETY ANALYSES

The LCO limits on the specific activity of the reactorcoolant ensure that the resulting offsite and control roomdoses meet the appropriate SRP acceptance criteriafollowing a SLB or SGTR accident. The safety analyses(Refs. 3 and 4) assume the specific activity of the reactorcoolant is at the LCO limits, and an existing reactorcoolant steam generator (SG) tube leakage rate of 1.0 gpmexists. The safety analyses assume the specific activityof the secondary coolant is at its limit of 4.5E-4 pCi/gDOSE EQUIVALENT 1-131 from LCO 3.7.16, "Secondary SpecificActivity."

The analyses for the SLB and SGTR accidents establish theacceptance limits for RCS specific activity. Reference tothese analyses is used to assess changes to the unit thatcould affect RCS specific activity, as they relate to theacceptance limits.

(continued)

Crystal River Unit 3 B 3.4-71 Revision No.


BASES

APPLICABLESAFETY ANALYSES(continued)

The safety analyses consider two cases of reactorcoolant iodine specific activity. One case assumesspecific activity at 0.35 pCi/g DOSE EQUIVALENT 1-131 witha concurrent large iodine spike that increases the rate ofrelease of iodine from the fuel rods containing claddingdefects to the primary coolant immediately after a SLB (bya factor of 500), or SGTR (by a factor of 335),respectively. The second case assumes the initial reactorcoolant iodine activity at 21.0 pCi/g DOSE EQUIVALENT 1-131due to an iodine spike caused by a reactor or an RCStransient priorto the accident. In both cases, the noblegas specific activity is assumed to be 646 pCi/g DOSEEQUIVALENT XE-133.

The SGTR analysis assumes a rise in pressure in theruptured SG causes radioactively contaminated steam todischarge to the atmosphere through the atmospheric dumpvalves or the main steam safety valves. The atmosphericdischarge stops when the turbine bypass to the condenserremoves the excess energy to rapidly reduce the RCSpressure and close the valves. The unaffected SG removescore decay heat by venting steam until the cooldown endsand the Decay Heat Removal (DHR) system is placed inservice.

The SLB radiological analysis. assumes that offsite power islost at the same time as the pipe break occurs outsideContainment. The affected .SG blows down completely andsteam is vented directly to the atmosphere. The unaffectedSG removes core decay heat iby venting steam to theatmosphereunt'il the cooldown:ends and the DHR system isplaced in service.

Operation with iodine specific activity levels greater thanthe LCO limit is permissible, if the activity levels do notexceed 21.0 pCi/g for more than 48 hours.

The limits on RCS specific activity are also used forestablishing standardization in radiation shielding andplant personnel radiation protection practices.

RCS specific activity satisfies Criterion 2 of 10 CFR50.36(c) (2) (ii).

LCO The iodine specific activity in the reactor coolant islimited to 0.35 pCi/g DOSE EQUIVALENT 1-131, and the noblegas specific activity in the reactor coolant is limited to646 pCi/g DOSE EQUIVALENT XE-133. The limits on specificactivity ensure that offsite and control room doses willmeet the appropriate SRP acceptance criteria (Ref. 2).

The SLB and SGTR accident analyses (Refs. 3 and 4) show

(conti nued)



BASES

LCO that the calculated doses are within acceptable limits.(continued) Violation of the LCO may result in reactor coolant

radioactivity levels that could, in the event of a SLB orSGTR, lead to doses that exceed the SRP acceptance criteria(Ref. 2).

APPLICABILITY In MODES 1, 2, 3, and 4, operation within the LCO limitsfor DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 isnecessary to limit the potential consequences of a SLB orSGTR to within the SRP acceptance criteria (Ref. 2).

In MODES 5 and 6, the steam generators are not being usedfor decay heat removal, the RCS and steam generators aredepressurized, and primary to secondary leakage is minimal.Therefore, the monitoring of RCS specific activity is notrequi red.

ACTIONS A.1 and A.2

With the DOSE EQUIVALENT 1-131 greater than the LCO limit,samples at intervals of 4 hours must be taken todemonstrate that the specific activity is < 21.0 pCi/g.The Completion Time of 4 hours is required to obtain andanalyze a sample. Sampling is continued every 4 hours toprovide a trend.

The DOSE EQUIVALENT 1-131 must be restored to within limitwithin 48 hours. The Completion Time of 48 hours isacceptable since it is expected that, if there were aniodine spike, the normal coolant iodine concentration wouldbe restored within this time period. Also, there is a lowprobability of a SLB or SGTR occurring during this timeperiod.

A Note permits the use of the provisions of LCO 3.0.4.c.This allowance permits entry into the applicable MODE(S),relying on Required Actions A.1 and A.2 while the DOSEEQUIVALENT 1-131 LCO limit is not met. This allowance isacceptable due to the significant conservatism incorporatedinto the specific activity limit, the low probability of anevent which is limiting due to exceeding this limit, andthe ability to restore transient-specific activityexcursions while the plant remains at, or proceeds to,power operation.

(continued)



BASES

ACTIONS B.1(continued)

With the DOSE EQUIVALENT XE-133 greater than the LCO limit,DOSE EQUIVALENT XE-133 must be restored to within limitwithin 48 hours. The allowed Completion Time of 48 hoursis acceptable since it is expected that, if there were anoble gas spike, the normal coolant noble gas concentrationwould be restored within this time period. Also, there isa low probability of a SLB or SGTR occurring during thistime period.

A Note permits the use of the provisions of LCO 3.0.4.c.This allowance permits entry into the applicable MODES(S),relying on Required Action B.1 while the DOSE EQUIVALENTXE-133 LCO limit is not met. This allowance is acceptabledue to the significant conservatism incorporated into thespecific activity limit, the low probability of an eventwhich is limiting due to exceeding this limit, and theability to restore transient-specific activity excursionswhile the plant remains at, or proceeds to, poweroperation.

C.1 and C.2

If the Required Action and associated Completion Time ofCondition A or B is not met, or if the DOSE EQUIVALENT1-131 is > 21.0 pCi/g, the reactor must be brought to MODE3 within 6 hours and MODE 5 within 36 hours. The allowedCompletion Times are reasonable, based on operatingexperience, to reach the required plant conditions fromfull power conditions in an orderly manner and withoutchallenging plant systems.

SURVEILLANCE SR 3.4.15.1REQUIREMENTS

SR 3.4.15.1 requires performing a gamma isotopic analysisas a measure of the noble gas specific activity of thereactor coolant at least once every 7 days. Thismeasurement is the sum of the degassed gamma activities andthe gaseous gamma activities in the sample taken. ThisSurveillance provides an indication of any increase in thenoble gas specific activity.

(continued)



BASES

SURVEILLANCE SR 3.4.15.1 (continued)REQUIREMENTS

Trending the results of this Surveillance allows properremedial action to be taken before reaching the LCO limitunder normal operating conditions. The 7 day Frequencyconsiders the low probability of a gross fuel failureduring this time.

Due to the inherent difficulty in detecting Kr-85 in areactor coolant sample due to masking from radioisotopeswith similar decay energies, such as F-18 and 1-134, it isacceptable to include the minimum detectable activity forKr-85 in the SR 3.4.15.1 calculation. If a specific noblegas nuclide listed in the definition of DOSE EQUIVALENTXE-133 is not detected, it should be assumed to be presentat the minimum detectable activity.

A Note modifies the SR to allow entry into and operation inMODE 4, MODE 3, and MODE 2 prior to performing the SR.This allows the Surveillance to be performed in thoseMODES, prior to entering MODE 1.

SR 3.4.15.2

This Surveillance is performed to ensure iodine specificactivity remains within the LCO limit during normaloperation and following fast power changes when iodinespiking is more apt to occur. The 14 day Frequency isadequate to trend changes in the iodine activity level,considering noble gas activity is monitored every 7 days.The Frequency, between 2 and 6 hours after a power change> 15% RTP within a 1 hour period, is established becausethe iodine levels peak during this time following iodinespike initiation; samples at other times would provideinaccurate results.

The Note modifies this SR to allow entry into and operationin MODE 4, MODE 3, and MODE 2 prior to performing the SR.This allows the Surveillance to be performed in thoseMODES, prior to entering MODE 1.

(continued)


RCS Specific Acti vi tyB 3.4.15

BASES

REFERENCES 1. 10 CFR 50.67.

2. Standard Review Plan Section 15.0.1,"Radiological Consequence Analyses UsingAlternative Source Terms."

3. FSAR Section 14.2.2.1, "Steam Line FailureAccident."

4. FSAR Section 14.2.2.2, "Steam Generator TubeRupture Accident."


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