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| {{#Wiki_filter:rrREGULATORY ORMATIONDISTRIBUTION SM(RIDS)AOCBSSI'ON NBR8306210160DOC~DATE!83/06/17NOTARIZED~NOFAOIL:5038%St.''Lucie Planti.Unilt2<FloridaPowerLLightCo+AUTH~NAMEAUTHORAFFILIATION UHRIGiRiE, FloridaPower3LightCo,RECIP,NAMERECIPIENT AFFILIATION EISENHUTiD | | {{#Wiki_filter:rr REGULATORY ORMATION DISTRIBUTION S M (RIDS)AOCBSSI'ON NBR 83062 1 0 1 60 DOC~DATE!83/06/17 NOTAR IZED~NO FAOIL:50 38%St.''Lucie Planti.Unilt 2<Flor ida Power L Light Co+AUTH~NAME AUTHOR AFFILIATION UHRIGiRiE, Florida Power 3 Light Co, RECIP, NAME RECIPIENT AFFILIATION EISENHUTiD |
| ~G.DivisionofLicensing | | ~G.Division of Licensing |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application toamendLicenseNPF16revisingTechSpecrequirement forprimaryLsecondary coolantsinsteamgenerator tobegreaterthan100Fwhencoolantpressuregreaterthan200psig,SERencl.DISTRIBUTION "CODE!8001SCOPIESRECEIVED:LTR ENCl'SIZE,-TITLE:Licensing "Submittal: | | Application to amend License NPF 16 revising Tech Spec requirement for primary L secondary coolants in steam generator to be greater than 100 F when coolant pressure greater than 200 psig,SER encl.DISTRIBUTION"CODE!8001S COPIES RECEIVED:LTR ENCl'SIZE,-TITLE: Licensing"Submittal: |
| PSAR/FSAR Amdts8RelatedCorrespondence NOTES:DOCKET¹05000389RECIPIENT IDCODE/NAME A/0LICENSNGLICBR¹3LAINTERNAloElD/HDS2IE/DEPER/KPB 36IE/DEQA/QAB 21NRR/DE/CKB 11NRR/DE/EQB 13NRR/DE/MEB 18NRR/DE/SAB 2ANRR/DE/SGEB 30NRR/DHFS/LQB 32NRR/DL/SSPB NRR/DSI/ASBNRR/DSI/CS8 09NRR/DSI/METB 12NRRDAB22IOQI/MIBEXTERNAL: | | PSAR/FSAR Amdts 8 Related Correspondence NOTES: DOCKET¹05000389 RECIPIENT ID CODE/NAME A/0 LICENSNG LIC BR¹3 LA INTERNAl o ElD/HDS2 IE/DEPER/KPB 36 IE/DEQA/QAB 21 NRR/DE/CKB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2A NRR/DE/SGEB 30 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CS8 09 NRR/DSI/METB 12 NRR D AB 22 I OQ I/MIB EXTERNAL: ACRS 01 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 3 j.1 1 1 2 2 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 0 6-6 1 1 1 1 1 1 RECIPIENT ID CODE/NAME LIC BR¹3 BC NERSESiV~01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DF/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DS I/ICSB 16 NRR/DS I/PSB 19 NRR/DSI/RSB 23 RGN2 BNL(AMDT'S ONLY)FEMA~REP DIV"39 NRC PDR 02 NTIS COPIES L'TTR ENCL 1 0 1 1 1 1 1 1 1 0 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3'TOTAL NUMBER OF COPIES REQUIRED+LTTR 54 ENCl 07 |
| ACRS01DMB/DSS(AMDTS)LPDR03NSIC05COPIESLTTRENCL1010103j.11122111111110111111111106-6111111RECIPIENT IDCODE/NAME LICBR¹3BCNERSESiV~01IEFILEIE/DEPER/IRB 35NRR/DE/AEAB NRR/DF/EHEB NRR/DE/GB 28NRR/DE/MTEB 17NRR/DE/SGEB 25NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB26NRR/DSI/CPB 10NRR/DSI/ICSB16NRR/DSI/PSB19NRR/DSI/RSB 23RGN2BNL(AMDT'S ONLY)FEMA~REPDIV"39NRCPDR02NTISCOPIESL'TTRENCL101111111011221111111111111111133'TOTALNUMBEROFCOPIESREQUIRED+
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| LTTR54ENCl07
| | OX 14000, JUNO BEACH, FL 33408 FLORIDA POWER&LIGHT COMPANY June l7, l983 L-83-349 Office of Nuclear Reactor Regulation |
| >>nhrM<<MM'I,,y.I)J'erf')))h14~Ir<<l>lllI'>>f)M''fI"I')!'l)tf,<<)4rrh]fIfI$..M,,pl-ME,I IIMfr>>>g>)M>fIgg<<Mn>>fe1fhhepilh'n~X'Mi!I,Ir~hi'lli,~Ill)>>1~1>~f>>>>nii>)nrl>>1wm>>a:i3n)fMPILHMQrrfr''Q'>'1>L~Mhli'li~iiI>>')I'Mn'MenI4'Ml))Mi}i7'If'MM'1'1.'Ij(~I)<11<I,.l."<<Ir,4''LO"1)I'IfhI>}'I'e"It>>if4')"IM)III>>>'II'e)>i4')'II>fJIM)fIEg4hh>>1Ieil>>>4ni,'9>>'",llhlli<<InMifflfMI)lf,iillrf>ChefIn,I;''x1Iir,hfIIilIIriI'li<<>>ifknbI),II,M-IIrIIIfrf'hN~IflftA>>',,r'hhfI>4f><<'f,'nlk4IhhIiiI,,lf>>'ili'MM,fii))MMhn>Iflfif>,r"ltgg1Ihf<<Ii>>'IIMIII~i<<IIIl.f"h,lM.e', | |
| OX14000,JUNOBEACH,FL33408FLORIDAPOWER&LIGHTCOMPANYJunel7,l983L-83-349OfficeofNuclearReactorRegulation
| |
| *Attention: | | *Attention: |
| Mr.DarrellG.Eisenhut, DirectorDivisionofLicensing | | Mr.Darrell G.Eisenhut, Director Division of Licensing.U.S.Nuclear Regulatory Commission Washington, D.C.20555 |
| .U.S.NuclearRegulatory Commission Washington, D.C.20555 | |
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| ==DearMr.Eisenhut:== | | ==Dear Mr.Eisenhut:== |
| | | Re: St.Lucie Unit No.2~Docket No.50-389 Proposed License Amendment Steam Generator Pressure/Temperature Limitation and Administrative/Editorial chan es In accordance with IO CFR 50.90, Florida Power&Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A of Facility Operating License NPF-I 6.This amendment is submitted to revise the requirement for both primary and secondary-coolants in the steam generator to be greater than IOOOF when the pressure in either coolant is greater.than 200 psig.This change is necessary to allow heatup of the primary coolant w'ith fhe Reactor Coolant Pumps.This change is a revision to the like change submitted as part of FPL letter L-83-248 dated.April 20, l 983, and therefore, supercedes that part of the April 20th submittal. |
| Re:St.LucieUnitNo.2~DocketNo.50-389ProposedLicenseAmendment SteamGenerator Pressure/Temperature Limitation andAdministrative/Editorial chanesInaccordance withIOCFR50.90,FloridaPower&LightCompanysubmitsherewiththreesignedoriginals andfortycopiesofarequesttoamendAppendixAofFacilityOperating LicenseNPF-I6.Thisamendment issubmitted torevisetherequirement forbothprimaryandsecondary | | This amendment is also submitted to.make several administrative/editorial changes.These changes have been identified as a result of continuing review of the Technical Specifications by both NRC and FPL.The proposed amendment is described below and shown on the accompanying Technical Specif ication pages.~P3/3 A-1 In the footnote, delete"and 3.I0.6".There is no Special Test Exception 3.I0.6.~33/3 3-13 Change the"5.6" and the"5.35" in Specification 4.7.I.6 b.to"4.2".Pa e 3/4 7-I2 Revise Specification.3.7.2 to apply only to the secondary coolant in the steam generator. |
| -coolants inthesteamgenerator tobegreaterthanIOOOFwhenthepressureineithercoolantisgreater.than200psig.Thischangeisnecessary toallowheatupoftheprimarycoolantw'ithfheReactorCoolantPumps.Thischangeisarevisiontothelikechangesubmitted aspartofFPLletterL-83-248dated.April20,l983,andtherefore, supercedes thatpartoftheApril20thsubmittal. | | Also, change the"275" in Specifications 3.7.2, 3.7.2 a.and 4.7.2 to"200".Pa e 3/4 7-30 Change the"3.7.I I.4 and 3.7.I I.5" in Specification 3.7.I I.I c.to 3.7.I l.4"."3.7.11.3 and Il PEOPLE...SERVING PEOPLE Page 2 Office of Nuclear Reactor Regulation Mr.Darrell G.Eisenhut, Director i Pa e B 3/4 7-4 Change the>>275>>to>>2QQ>>and the>>3Q>>to>>20>>jn BASES 3/4 7 2 Pacae 6-20 Delete the words"first half year" in the first line of the double-asterisk footnote.In accordance with I 0 CFR 50.9I(b)(l), a copy of this proposed license amendment is being forwarded to the State Designee for the State of Florida.In accordance with IO CFR 50.9I(a)(I), we have determined that this amendment does not involve any significant hazards considerations pursuant to IO CFR 50.9I(c)in that the amendment is administrative in nature and therefore does not: I)'nvolve a significant increase in the probability or consequences of an accident previously evaluated; or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)involve a significant reduction in a margin or safety.*el~~I The proposed amendment has been reviewed by the St.Lucie Facility Review Croup and the Florida Power&Light Compariy Nuclear Review Board.In that this amendment is administrative in nature, it has been determined to be a Class II amendment, in accordance with IO CFR I 70.22.A check for pl,200.00 will follow short I y.Very truly yours, Robert E.Uhrig Vice President Advanced Systems&Technology REU/R JS/cab Attachments cc: J.P.O'Reilly, Region II Harold F.Reis, Esquire Ulray Clark, Administrator Radiological Health Services Department of Health and Rehabilitative Services I 323 Winewood Boulevard Tallahassee, Florida 3230I Pa e 3/44-I SAFETY EVALUATlON, This change is administrative/editorial, and therefore of no safety concern.P~3/4 7-14 This change is administrative/editorial (the actual valve closure time is 4.2 seconds, not 5.6 seconds or 5.35 seconds), and therefore of no safety conern.Pa e 3/4 7-I2 and B 3/4 7-4 Limiting Condition for Operation 3.7.2 for Technical Specification 3/4.7.2 requires that the temperatures of both primary and secondary coolants in the steam generators shall be greater than l00oF when the pressure of either coolant in the steam generator is greater than 275 psig.Our NSSS vendor has indicated that the 275 psig limit is incorrect and should be 200 psig.Furthermore, our startup procedures call for initial heating of the primary coolant to be performed utilizing pump heat from the reactor coolant pumps (RCP).However, the pump curve received from the vendor indicates that operation of the RCPs within these primary coolant system pressure limits will cause reduction in life of the RCP seals.Since the temperature of the secondary coolant in the steam generator is at ambient, about 80 to 90oF, this Technical Specification would preclude the use of RCPs to heat up the primary coolant without reducing seal life.\4 4~The bases for this Technical Specification is that by placing limits on the pressure and',temperature of both;the primary and secondary coolants, the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.The current limits are based on a steam generator RTNDT of 20oF.However, Technical Specification 3/4.4.9 also contains pressure and temperature limitations for the reactor coolant system (RCS).The bases for these limits is the same as that for Technical Specification 3/4.7.2, i.e., to ensure that the maximum pressure induced stresses do not exceed the maximum allowable fracture toughness stress limits for the RCS pressure retaining components. |
| Thisamendment isalsosubmitted to.makeseveraladministrative/editorial changes.Thesechangeshavebeenidentified asaresultofcontinuing reviewoftheTechnical Specifications bybothNRCandFPL.Theproposedamendment isdescribed belowandshownontheaccompanying Technical Specificationpages.~P3/3A-1Inthefootnote, delete"and3.I0.6".ThereisnoSpecialTestException 3.I0.6.~33/33-13Changethe"5.6"andthe"5.35"inSpecification 4.7.I.6b.to"4.2".Pae3/47-I2ReviseSpecification.3.7.2 toapplyonlytothesecondary coolantinthesteamgenerator.
| | Bases 3/4.4.9 states that these curves were developed assuming the maximum RTNDT for all RCS pressure-retaining materials, with the exception of the reactor pressure vessel, of 50oF.Therefore, the pressure/temperature curves for Technical Specification 3/44.9 are appropriate for use for the primary coolant in the steam generator as well, since they are based on a more conservative basis (higher RTNDT)than those in Technical Specification 3/4.7.2.The pressure temperature limits in Technical Specification 3/4.7.2 are clearly more conservative and restrictive than required.Due to the potential problems of the RCP seals being operated at the low pressure currently required, the existing limits of 3/4.7.2 may cause the system to be operated in a condition less safe than desired.Based on the above, it is our determination that removal of the pressure temperature limits for the primary coolant from Technical Specification 3/4.7.2 does not pose a risk to health and safety of the public.This is due to the fact that the secondary pressure boundary remains protected by this Technical'pecification and that the primary pressure boundary is protected by'echnical Specification |
| Also,changethe"275"inSpecifications 3.7.2,3.7.2a.and4.7.2to"200".Pae3/47-30Changethe"3.7.II.4and3.7.II.5"inSpecification 3.7.II.Ic.to3.7.Il.4"."3.7.11.3 andIlPEOPLE... | | ~3/4.4.9.Our NSSS vendor concu'rs with this conclusion. |
| SERVINGPEOPLE Page2OfficeofNuclearReactorRegulation Mr.DarrellG.Eisenhut, DirectoriPaeB3/47-4Changethe>>275>>to>>2QQ>>andthe>>3Q>>to>>20>>jnBASES3/472Pacae6-20Deletethewords"firsthalfyear"inthefirstlineofthedouble-asteriskfootnote.
| | SAFETY EVALUATION (continued) |
| Inaccordance withI0CFR50.9I(b)(l),
| | Pa e 3/4 7-30 Ths change is administrative/editorial, and therefore of no safety concern.Pacee 6-20 This change is administrative/editorial, and therefore of no safety concern.}} |
| acopyofthisproposedlicenseamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Inaccordance withIOCFR50.9I(a)(I),
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| wehavedetermined thatthisamendment doesnotinvolveanysignificant hazardsconsiderations pursuanttoIOCFR50.9I(c)inthattheamendment isadministrative innatureandtherefore doesnot:I)'nvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3)involveasignificant reduction inamarginorsafety.*el~~ITheproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewCroupandtheFloridaPower&LightCompariyNuclearReviewBoard.Inthatthisamendment isadministrative innature,ithasbeendetermined tobeaClassIIamendment, inaccordance withIOCFRI70.22.Acheckforpl,200.00 willfollowshortIy.Verytrulyyours,RobertE.UhrigVicePresident AdvancedSystems&Technology REU/RJS/cabAttachments cc:J.P.O'Reilly, RegionIIHaroldF.Reis,EsquireUlrayClark,Administrator Radiological HealthServicesDepartment ofHealthandRehabilitative ServicesI323WinewoodBoulevard Tallahassee, Florida3230I Pae3/44-ISAFETYEVALUATlON, Thischangeisadministrative/editorial, andtherefore ofnosafetyconcern.P~3/47-14Thischangeisadministrative/editorial (theactualvalveclosuretimeis4.2seconds,not5.6secondsor5.35seconds),
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| andtherefore ofnosafetyconern.Pae3/47-I2andB3/47-4LimitingCondition forOperation 3.7.2forTechnical Specification 3/4.7.2requiresthatthetemperatures ofbothprimaryandsecondary coolantsinthesteamgenerators shallbegreaterthanl00oFwhenthepressureofeithercoolantinthesteamgenerator isgreaterthan275psig.OurNSSSvendorhasindicated thatthe275psiglimitisincorrect andshouldbe200psig.Furthermore, ourstartupprocedures callforinitialheatingoftheprimarycoolanttobeperformed utilizing pumpheatfromthereactorcoolantpumps(RCP).However,thepumpcurvereceivedfromthevendorindicates thatoperation oftheRCPswithintheseprimarycoolantsystempressurelimitswillcausereduction inlifeoftheRCPseals.Sincethetemperature ofthesecondary coolantinthesteamgenerator isatambient,about80to90oF,thisTechnical Specification wouldprecludetheuseofRCPstoheatuptheprimarycoolantwithoutreducingseallife.\44~ThebasesforthisTechnical Specification isthatbyplacinglimitsonthepressureand',temperature ofboth;theprimaryandsecondary
| |
| : coolants, thepressureinducedstressesinthesteamgenerators donotexceedthemaximumallowable fracturetoughness stresslimits.Thecurrentlimitsarebasedonasteamgenerator RTNDTof20oF.However,Technical Specification 3/4.4.9alsocontainspressureandtemperature limitations forthereactorcoolantsystem(RCS).ThebasesfortheselimitsisthesameasthatforTechnical Specification 3/4.7.2,i.e.,toensurethatthemaximumpressureinducedstressesdonotexceedthemaximumallowable fracturetoughness stresslimitsfortheRCSpressureretaining components.
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| Bases3/4.4.9statesthatthesecurvesweredeveloped assumingthemaximumRTNDTforallRCSpressure-retaining materials, withtheexception ofthereactorpressurevessel,of50oF.Therefore, thepressure/temperature curvesforTechnical Specification 3/44.9areappropriate forusefortheprimarycoolantinthesteamgenerator aswell,sincetheyarebasedonamoreconservative basis(higherRTNDT)thanthoseinTechnical Specification 3/4.7.2.Thepressuretemperature limitsinTechnical Specification 3/4.7.2areclearlymoreconservative andrestrictive thanrequired.
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| Duetothepotential problemsoftheRCPsealsbeingoperatedatthelowpressurecurrently
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| : required, theexistinglimitsof3/4.7.2maycausethesystemtobeoperatedinacondition lesssafethandesired.Basedontheabove,itisourdetermination thatremovalofthepressuretemperature limitsfortheprimarycoolantfromTechnical Specification 3/4.7.2doesnotposearisktohealthandsafetyofthepublic.Thisisduetothefactthatthesecondary pressureboundaryremainsprotected bythisTechnical'pecification andthattheprimarypressureboundaryisprotected by'echnical Specification
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| ~3/4.4.9.OurNSSSvendorconcu'rswiththisconclusion. | |
| SAFETYEVALUATION (continued)
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| Pae3/47-30Thschangeisadministrative/editorial, andtherefore ofnosafetyconcern.Pacee6-20Thischangeisadministrative/editorial, andtherefore ofnosafetyconcern.}}
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17241A4441999-08-18018 August 1999
Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld
ML17241A3521999-06-0101 June 1999
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3431999-05-24024 May 1999
Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements
ML17229B0181999-02-23023 February 1999
Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution.
ML17229A9541998-12-16016 December 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9221998-11-22022 November 1998
Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9111998-11-19019 November 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML17229A8421998-08-24024 August 1998
Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
ML17229A7581998-06-0303 June 1998
Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1
ML17229A7461998-05-27027 May 1998
Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7491998-05-27027 May 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A7421998-05-27027 May 1998
Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A6481998-03-0303 March 1998
Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
ML17309A9161997-12-31031 December 1997
Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9111997-12-29029 December 1997
Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5471997-12-0101 December 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement
ML17229A4601997-08-22022 August 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising Specification 4.0.5,Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Controls Section
ML17229A4321997-08-0101 August 1997
Application for Amend to License NPF-16,extending semi- Annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996
ML17229A4211997-07-22022 July 1997
Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
ML17229A3581997-05-29029 May 1997
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases
ML17229A1811996-12-20020 December 1996
Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17229A1591996-12-0909 December 1996
Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values
ML17229A1171996-10-31031 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs
ML17339A0431996-10-30030 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
ML17229A1071996-10-28028 October 1996
Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1041996-10-28028 October 1996
Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17228B5621996-07-15015 July 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition
ML17228B5021996-06-0101 June 1996
Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl
ML17228B3741996-01-0404 January 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17228B3341995-11-22022 November 1995
Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities
ML17228B2861995-10-0505 October 1995
Application for Amends to Licenses DPR-67 & NPF-16,removing SR Re Dune & Mangrove Surveys from TS
ML17228B2401995-08-16016 August 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Selected TS Requirements Re Instrumentation,Per Final Policy Statement on TS Improvements & Relocating TS Re Emergency & Security Plan Review Process Per GL 93-07
ML17228B2431995-08-16016 August 1995
Application for Amend to License NPF-16,modifying Spec 3.6.6.1, Sbvs to More Effectively Address Design Functions Performed by Sbvs for Shield Bldg & Fuel Handling Bldg,Per NUREG-1432
ML17228B1871995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Revise Action Statements & Certain Surveillances of TS 3/4.5.1 Re Safety Injection Tanks
ML17228B1771995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Extend Allowed Outage Time for Inoperable EDGs
ML17309A7921995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Allow Up to Seven Days to Restore an Inoperable LPSI Train to Operable Status
ML17228B1451995-05-17017 May 1995
Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
ML17228B1421995-05-17017 May 1995
Application for Amends to Licenses DPR-67 & NPF-16 Re Administrative & Conforming Update
ML17228B0881995-04-0303 April 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Incorporate line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2
ML17228B0571995-02-27027 February 1995
Application for Amend to License NPF-16,modifying Surveillance Requirement 4.9.8.1 & 4.9.8.2 to Allow Reduction in Required Min Shutdown Cooling Flow Rate Under Certain Conditions During Operational Mode 6
ML17228B0501995-02-27027 February 1995
Application for Amend to License NPF-16,revising TS Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relay
ML17228B0311995-02-22022 February 1995
Application for Amends to Licenses DPR-67 & NPF-16,deleting Refs to Automatic Tester for Containment Personnel Air Lock from TS 4.6.1.3
ML17228A9901995-01-20020 January 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Operability Requirements for Incore Detectors (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillances
ML17352B0001995-01-17017 January 1995
Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl
ML17228A9011994-11-0202 November 1994
Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants
ML17309A7511994-10-27027 October 1994
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Encl Administrative Changes
ML17228A6501994-07-28028 July 1994
Application for Amends to Licenses DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements Similar to LTOP Requirements Recommended by NRC Via GL 90-06,in Accordance W/Resolution of Generic Issue 94
ML17228A6571994-07-25025 July 1994
Application for Amends to Licenses DPR-67 & NPF-16,revising Ts,Implementing Enhancements Recommended by GL 93-05 Re line-item TS Improvements to Reduce SR for Testing During Power Operation.
ML17228A6541994-07-25025 July 1994
Application for Amend to License NPF-16,proposing TS Upgrading TS 3/4.7.1.6 for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants
ML17228A5751994-05-23023 May 1994
Application for Amend to License DPR-67,revising TS 3.5.2 for ECCS by Removing Option That Allows HPSI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability
1999-08-18
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17241A4441999-08-18018 August 1999
Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld
ML17241A3521999-06-0101 June 1999
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3431999-05-24024 May 1999
Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements
ML17229B0181999-02-23023 February 1999
Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution.
ML17229A9541998-12-16016 December 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9221998-11-22022 November 1998
Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9111998-11-19019 November 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML17229A8421998-08-24024 August 1998
Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
ML17229A7581998-06-0303 June 1998
Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1
ML17229A7461998-05-27027 May 1998
Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7491998-05-27027 May 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A7421998-05-27027 May 1998
Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A6481998-03-0303 March 1998
Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
ML17309A9161997-12-31031 December 1997
Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9111997-12-29029 December 1997
Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5471997-12-0101 December 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement
ML17229A4601997-08-22022 August 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising Specification 4.0.5,Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Controls Section
ML17229A4321997-08-0101 August 1997
Application for Amend to License NPF-16,extending semi- Annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996
ML17229A4211997-07-22022 July 1997
Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
ML17229A3581997-05-29029 May 1997
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases
ML17229A1811996-12-20020 December 1996
Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17229A1591996-12-0909 December 1996
Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values
ML17229A1171996-10-31031 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs
ML17339A0431996-10-30030 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
ML17229A1071996-10-28028 October 1996
Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1041996-10-28028 October 1996
Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17228B5621996-07-15015 July 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition
ML17228B5021996-06-0101 June 1996
Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl
ML17228B3741996-01-0404 January 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17228B3341995-11-22022 November 1995
Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities
ML17228B2861995-10-0505 October 1995
Application for Amends to Licenses DPR-67 & NPF-16,removing SR Re Dune & Mangrove Surveys from TS
ML17228B2401995-08-16016 August 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Selected TS Requirements Re Instrumentation,Per Final Policy Statement on TS Improvements & Relocating TS Re Emergency & Security Plan Review Process Per GL 93-07
ML17228B2431995-08-16016 August 1995
Application for Amend to License NPF-16,modifying Spec 3.6.6.1, Sbvs to More Effectively Address Design Functions Performed by Sbvs for Shield Bldg & Fuel Handling Bldg,Per NUREG-1432
ML17228B1871995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Revise Action Statements & Certain Surveillances of TS 3/4.5.1 Re Safety Injection Tanks
ML17228B1771995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Extend Allowed Outage Time for Inoperable EDGs
ML17309A7921995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Allow Up to Seven Days to Restore an Inoperable LPSI Train to Operable Status
ML17228B1451995-05-17017 May 1995
Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
ML17228B1421995-05-17017 May 1995
Application for Amends to Licenses DPR-67 & NPF-16 Re Administrative & Conforming Update
ML17228B0881995-04-0303 April 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Incorporate line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2
ML17228B0571995-02-27027 February 1995
Application for Amend to License NPF-16,modifying Surveillance Requirement 4.9.8.1 & 4.9.8.2 to Allow Reduction in Required Min Shutdown Cooling Flow Rate Under Certain Conditions During Operational Mode 6
ML17228B0501995-02-27027 February 1995
Application for Amend to License NPF-16,revising TS Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relay
ML17228B0311995-02-22022 February 1995
Application for Amends to Licenses DPR-67 & NPF-16,deleting Refs to Automatic Tester for Containment Personnel Air Lock from TS 4.6.1.3
ML17228A9901995-01-20020 January 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Operability Requirements for Incore Detectors (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillances
ML17352B0001995-01-17017 January 1995
Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl
ML17228A9011994-11-0202 November 1994
Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants
ML17309A7511994-10-27027 October 1994
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Encl Administrative Changes
ML17228A6501994-07-28028 July 1994
Application for Amends to Licenses DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements Similar to LTOP Requirements Recommended by NRC Via GL 90-06,in Accordance W/Resolution of Generic Issue 94
ML17228A6571994-07-25025 July 1994
Application for Amends to Licenses DPR-67 & NPF-16,revising Ts,Implementing Enhancements Recommended by GL 93-05 Re line-item TS Improvements to Reduce SR for Testing During Power Operation.
ML17228A6541994-07-25025 July 1994
Application for Amend to License NPF-16,proposing TS Upgrading TS 3/4.7.1.6 for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants
ML17228A5751994-05-23023 May 1994
Application for Amend to License DPR-67,revising TS 3.5.2 for ECCS by Removing Option That Allows HPSI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability
1999-08-18
[Table view] |
Text
rr REGULATORY ORMATION DISTRIBUTION S M (RIDS)AOCBSSI'ON NBR 83062 1 0 1 60 DOC~DATE!83/06/17 NOTAR IZED~NO FAOIL:50 38%St.Lucie Planti.Unilt 2<Flor ida Power L Light Co+AUTH~NAME AUTHOR AFFILIATION UHRIGiRiE, Florida Power 3 Light Co, RECIP, NAME RECIPIENT AFFILIATION EISENHUTiD
~G.Division of Licensing
SUBJECT:
Application to amend License NPF 16 revising Tech Spec requirement for primary L secondary coolants in steam generator to be greater than 100 F when coolant pressure greater than 200 psig,SER encl.DISTRIBUTION"CODE!8001S COPIES RECEIVED:LTR ENCl'SIZE,-TITLE: Licensing"Submittal:
PSAR/FSAR Amdts 8 Related Correspondence NOTES: DOCKET¹05000389 RECIPIENT ID CODE/NAME A/0 LICENSNG LIC BR¹3 LA INTERNAl o ElD/HDS2 IE/DEPER/KPB 36 IE/DEQA/QAB 21 NRR/DE/CKB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2A NRR/DE/SGEB 30 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CS8 09 NRR/DSI/METB 12 NRR D AB 22 I OQ I/MIB EXTERNAL: ACRS 01 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 3 j.1 1 1 2 2 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 0 6-6 1 1 1 1 1 1 RECIPIENT ID CODE/NAME LIC BR¹3 BC NERSESiV~01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DF/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DS I/ICSB 16 NRR/DS I/PSB 19 NRR/DSI/RSB 23 RGN2 BNL(AMDT'S ONLY)FEMA~REP DIV"39 NRC PDR 02 NTIS COPIES L'TTR ENCL 1 0 1 1 1 1 1 1 1 0 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3'TOTAL NUMBER OF COPIES REQUIRED+LTTR 54 ENCl 07
>>n hr M<<MM'I,, y.I)J'er f')))h 1 4~I r<<l>l ll I'>>f)Mf I"I')!'l)t f ,<<)4 r rh]f If I$..M,,pl-ME,I I I Mfr>>>g>)M>f I gg<<M n>>fe1 fhhepilh'n~X'Mi!I, I r~hi'l li,~I ll)>>1~1>~f>>>>ni i>)nrl>>1 w m>>a:i 3n)fM PILHMQ rr f rQ'>'1>L~Mhli'li~ii I>>')I'M n'Men I 4'Ml))Mi}i 7'If'MM'1'1.'I j(~I)<1 1<I,.l."<<Ir, 4LO"1)I'If h I>}'I'e"It>>if 4')"IM)I I I>>>'I I'e)>i 4')'I I>f JIM)f I Eg 4 hh>>1I eil>>>4 ni,'9>>'", ll hll i<Chef In, I;x1I ir ,hf I I il II r iI'li<<>>i f knb I), I I, M-II r I I I f r f'h N~I fl ft A>>',,r'hhfI>4 f><<'f ,'nl k 4 I hh I ii I,, lf>>'ili'MM, f ii))MMhn>If lf if>, r"lt gg 1 I hf<>'I IM III~i<>275>>to>>2QQ>>and the>>3Q>>to>>20>>jn BASES 3/4 7 2 Pacae 6-20 Delete the words"first half year" in the first line of the double-asterisk footnote.In accordance with I 0 CFR 50.9I(b)(l), a copy of this proposed license amendment is being forwarded to the State Designee for the State of Florida.In accordance with IO CFR 50.9I(a)(I), we have determined that this amendment does not involve any significant hazards considerations pursuant to IO CFR 50.9I(c)in that the amendment is administrative in nature and therefore does not: I)'nvolve a significant increase in the probability or consequences of an accident previously evaluated; or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)involve a significant reduction in a margin or safety.*el~~I The proposed amendment has been reviewed by the St.Lucie Facility Review Croup and the Florida Power&Light Compariy Nuclear Review Board.In that this amendment is administrative in nature, it has been determined to be a Class II amendment, in accordance with IO CFR I 70.22.A check for pl,200.00 will follow short I y.Very truly yours, Robert E.Uhrig Vice President Advanced Systems&Technology REU/R JS/cab Attachments cc: J.P.O'Reilly, Region II Harold F.Reis, Esquire Ulray Clark, Administrator Radiological Health Services Department of Health and Rehabilitative Services I 323 Winewood Boulevard Tallahassee, Florida 3230I Pa e 3/44-I SAFETY EVALUATlON, This change is administrative/editorial, and therefore of no safety concern.P~3/4 7-14 This change is administrative/editorial (the actual valve closure time is 4.2 seconds, not 5.6 seconds or 5.35 seconds), and therefore of no safety conern.Pa e 3/4 7-I2 and B 3/4 7-4 Limiting Condition for Operation 3.7.2 for Technical Specification 3/4.7.2 requires that the temperatures of both primary and secondary coolants in the steam generators shall be greater than l00oF when the pressure of either coolant in the steam generator is greater than 275 psig.Our NSSS vendor has indicated that the 275 psig limit is incorrect and should be 200 psig.Furthermore, our startup procedures call for initial heating of the primary coolant to be performed utilizing pump heat from the reactor coolant pumps (RCP).However, the pump curve received from the vendor indicates that operation of the RCPs within these primary coolant system pressure limits will cause reduction in life of the RCP seals.Since the temperature of the secondary coolant in the steam generator is at ambient, about 80 to 90oF, this Technical Specification would preclude the use of RCPs to heat up the primary coolant without reducing seal life.\4 4~The bases for this Technical Specification is that by placing limits on the pressure and',temperature of both;the primary and secondary coolants, the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.The current limits are based on a steam generator RTNDT of 20oF.However, Technical Specification 3/4.4.9 also contains pressure and temperature limitations for the reactor coolant system (RCS).The bases for these limits is the same as that for Technical Specification 3/4.7.2, i.e., to ensure that the maximum pressure induced stresses do not exceed the maximum allowable fracture toughness stress limits for the RCS pressure retaining components.
Bases 3/4.4.9 states that these curves were developed assuming the maximum RTNDT for all RCS pressure-retaining materials, with the exception of the reactor pressure vessel, of 50oF.Therefore, the pressure/temperature curves for Technical Specification 3/44.9 are appropriate for use for the primary coolant in the steam generator as well, since they are based on a more conservative basis (higher RTNDT)than those in Technical Specification 3/4.7.2.The pressure temperature limits in Technical Specification 3/4.7.2 are clearly more conservative and restrictive than required.Due to the potential problems of the RCP seals being operated at the low pressure currently required, the existing limits of 3/4.7.2 may cause the system to be operated in a condition less safe than desired.Based on the above, it is our determination that removal of the pressure temperature limits for the primary coolant from Technical Specification 3/4.7.2 does not pose a risk to health and safety of the public.This is due to the fact that the secondary pressure boundary remains protected by this Technical'pecification and that the primary pressure boundary is protected by'echnical Specification
~3/4.4.9.Our NSSS vendor concu'rs with this conclusion.
SAFETY EVALUATION (continued)
Pa e 3/4 7-30 Ths change is administrative/editorial, and therefore of no safety concern.Pacee 6-20 This change is administrative/editorial, and therefore of no safety concern.
