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| {{#Wiki_filter:INDEXLISTOFTABLES{Continued) | | {{#Wiki_filter:INDEX LIST OF TABLES{Continued) |
| $$$$$$$$$$$$'$$$$$'$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$TABLE3.7-1PAGMAXIMUMALLOWABLE LINEARPOWERLEVEL-HIGH TRIPSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURINGOPERA-TIONWITHBOTHSTEAMGENERATORS...................... | | $$$$$$$$$$$$'$$$$$'$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$TABLE 3.7-1 PAG MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS...................... |
| 3/47-24.7-1STEAMLINESAFETYVALVESPERLOOP...SECONDARY COOLANTSYSTEMSPECIFICACTIVITYSAMPLEANDANALYSISPROGRAM.. | | 3/4 7-2 4.7-1 STEAM LINE SAFETY VALVES PER LOOP...SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3/4 7-3 3/4 7-8 4.7-2 3.7-3a 3.7-3b 3.7-4 3.7-5 4.8-1 4.8-2 3.8-1 SNUBBER VISUAL INSPECTION INTERVAL.................... |
| ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3/47-33/47-84.7-23.7-3a3.7-3b3.7-43.7-54.8-14.8-23.8-1SNUBBERVISUALINSPECTION INTERVAL.................... | | 3/4 7-22 ELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~D ELETED...... |
| 3/47-22ELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~DELETED...... | | D FIRE HOSE STATIONS.................................... |
| DFIREHOSESTATIONS....................................
| | 3/4 7-26 3/4 7-27 3/4 7-36 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES........................................ |
| 3/47-263/47-273/47-36MOTOR-OPERATED VALVESTHERMALOVERLOADPROTECTION BYPASSDEVICES........................................ | | 3/4 8-18 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES 3/4 7-38 DIESEL GENERATOR TEST SCHEDULE......".................. |
| 3/48-18YARDFIREHYDRANTSANDASSOCIATED HYDRANTHOSEHOUSES3/47-38DIESELGENERATOR TESTSCHEDULE......".................. | | 3/4 8-8 BATTERY SURVEILLANCE REQUIREMENT...'................... |
| 3/48-8BATTERYSURVEILLANCE REQUIREMENT...'................... | | 3/4 8-12 4.1')-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS ROGRAH~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P 3/4 11-2 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS ROGRAM~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P 3/4 11-8 3.12-1 3.12-2 4.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM......... |
| 3/48-124.1')-1RADIOACTIVE LIQUIDWASTESAMPLINGANDANALYSISROGRAH~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P3/411-24.11-2RADIOACTIVE GASEOUSWASTESAMPLINGANDANALYSISROGRAM~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P3/411-83.12-13.12-24.12-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM......... | | 3/4 12-3 REPORTING LEVELS fOR RADIOACTIVITY CONCENTRATIONS IN FNVIRONHENTAL SAMPLES................................. |
| 3/412-3REPORTING LEVELSfORRADIOACTIVITY CONCENTRATIONS INFNVIRONHENTAL SAMPLES................................. | | 3/4 12-7 DETECTION CAPABILITIES FOR ENVIRONHENTAL SAMPLE B 3/4.2-1 NALYS IS o i~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~A ELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~i'~~~~~D B 3/4..4-1 REACTOR VESSEL TOUGHNESS.............................. |
| 3/412-7DETECTION CAPABILITIES FORENVIRONHENTAL SAMPLEB3/4.2-1NALYSISoi~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~AELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~i'~~~~~DB3/4..4-1REACTORVESSELTOUGHNESS.............................. | | 3/4 12-8 B 3/4 2-3 B 3/4 4-9 5.7-1 6.2-1 MINIMUM SHIFT CREW COHPOSITION-TWO UNITS WITH TWO SEPARATE CONTROL ROOMS 6-5 COMPONENT CYCLIC OR TRANSIENT LIMITS.................. |
| 3/412-8B3/42-3B3/44-95.7-16.2-1MINIMUMSHIFTCREWCOHPOSITION-TWO UNITSWITHTWOSEPARATECONTROLROOMS6-5COMPONENT CYCLICORTRANSIENT LIMITS.................. | | 5-5 9406010046 940523 PDR ADDt K 05000389 i PDR,~~" ST.LUCIE-UNIT 2 XXV Amendment No.S,.M 53 |
| 5-59406010046 940523PDRADDtK05000389iPDR,~~"ST.LUCIE-UNIT2XXVAmendment No.S,.M53 | |
| 'I~ | | 'I~ |
| ~~a3/4.7PLANTSYSTBtS3/4.7.1TURBINECYCLESAFETYVALVESLrCrTINGCONDITION FOROPERATION 9.7.1.1AllmainsteamlinecodesafetyvalvesshallbeOPERABLE~cui4 | | ~~a 3/4.7 PLANT SYSTBtS 3/4.7.1 TURBINE CYCLE SAFETY VALVES Lr Cr TING CONDITION FOR OPERATION 9.7.1.1 All main steam line code safety valves shall be OPERABLE~cui4 |
| /R'r.pAPPLICABILITY: | | /R'r.p APPLICABILITY: |
| MODES1,Zand3.ACTION:a.Withbothreactorcoolantloopsandassociated steamgenerators inoperation andwithoneormoremainsteamlinecodesafetyvalvesinoperable, operation inMODES1,2and3mayproceedprovidedthat,within4hours,eithertheinoperable valveisrestoredtoOPERABLEstatusorthePowerLevel-High tripsetpointisreducedperTable3.7-1;otherwise, beinatleastHOTSTANDBYwithinthenext6hoursand'inCOLDSHUTDOWNwithinthefollowing 30hours.b.Theprovisions ofSpecification 3.0.4arenotapplicable.
| | MODES 1, Z and 3.ACTION: a.With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that, within 4 hours, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1;otherwise, be in at least HOT STANDBY within the next 6 hours and'in COLD SHUTDOWN within the following 30 hours.b.The provisions of Specification 3.0.4 are not applicable. |
| SURVEILLANCE REQUIREMENTS 4.7.1.EchminsamliecodesfetyvalshalledemontratedPERA(E,w~thJlifsettngsndoricesizasshowinTab4.7-0inacrdanwigSeionIotheNEBoileandPresureYeselCod,1974dftio.rt4cac/HiXjo~al Jo'der<'y'<rvcwr Ee~~y~d~w~pJo7g~~"">"-~~v~~.-ST.LUGIE-UNIT23/47-1Amendment No8 J''lh VALVENUMBER37-2TABLESTEANLINESAFETYVALVESPERLOOPLIFTSETTING1%ORIFICESI2Ea.e.8202020382048209821082118212.8206820782088213821482158216HeaderAHeaderB820182051000psia1000psia1000psia1000psia1040psia1040psia1040psia1040psia16in.216in.216in.16in.16in.16in.216in.216in. | | SURVEILLANCE REQUIREMENTS 4.7.1.E ch m in s am li e code s fety val shall e demon trated PERA (E, w~thJlif sett ngs nd or ice siz as show in Tab 4.7-0 in ac rdan wig Se ion I o the NE Boile and Pre sure Yes el Cod , 1974 dftio.rt4 cac/HiXjo~al Jo'der<'y'<rvcwr Ee~~y~d~w~pJ o 7g~~"">"-~~v~~.-ST.LUG IE-UNIT 2 3/4 7-1 Amendment No8 J''l h VALVE NUMBER 3 7-2 TABLE STEAN LINE SAFETY VALVES PER LOOP LIFT SETTING 1%ORIFICE SI2E a.e.8202 0203 8204 8209 8210 8211 8212.8206 8207 8208 8213 8214 8215 8216 Header A Header B 8201 8205 1000 psia 1000 psia 1000 psia 1000 psia 1040 psia 1040 psia 1040 psia 1040 psia 16 in.2 16 in.2 16 in.16 in.16 in.16 in.2 16 in.2 16 in. |
| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Administrative ChanetoDeleteASMECodeReference ATTACHMENT 2SAFETYANALYSISIntroduction AchangeisproposedtorevisetheSt.LucieUnit2Technical Specifications Section3/4.7.1.1 tochangethereference to,aspecificeditionoftheASMECodetoareference totestinginaccordance withTechnical Specification 4.0.5andrenumberthesafetyvalvesetpointTable4.7-0toTable3.7-2.Thelistoftablesintheindexisalsorevised.Discussion TheproposedchangetotheSt.LucieUnit2Technical Specifications revisesthespecificreference totheSectionXIoftheASMEBoilerandPressureVesselCode,1974EditiontobesimilartotheUnit1Technical Specification andconsistent withtherevisedStandardTechnical Specifications forCombustion Engineering Plants,NUREG1432.Inaddition, thechangerenumbers thesafetyvalvesetpointtablefromasurveillance tabletoanLimitingCondition forOperation (LCO)table.Surveillance requirement 4.7.1.1currently statesthat,eachmainsteamlinecodesafetyvalveshallbedemonstrated | | St.Lucie Unit 2 Docket No.50-389 Proposed License Amendment Administrative Chan e to Delete ASME Code Reference ATTACHMENT 2 SAFETY ANALYSIS Introduction A change is proposed to revise the St.Lucie Unit 2 Technical Specifications Section 3/4.7.1.1 to change the reference to, a specific edition of the ASME Code to a reference to testing in accordance with Technical Specification 4.0.5 and renumber the safety valve set point Table 4.7-0 to Table 3.7-2.The list of tables in the index is also revised.Discussion The proposed change to the St.Lucie Unit 2 Technical Specifications revises the specific reference to the Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition to be similar to the Unit 1 Technical Specification and consistent with the revised Standard Technical Specifications for Combustion Engineering Plants, NUREG 1432.In addition, the change renumbers the safety valve set point table from a surveillance table to an Limiting Condition for Operation (LCO)table.Surveillance requirement 4.7.1.1 currently states that, each main steam line code safety valve shall be demonstrated OPERABLE, with lift settings and orifice sizes as shown in Table 4.7-0, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition.The Edition of the ASME Code endorsed for the second ten year interval for St.Lucie Unit 2 is the 1986 Edition of the ASME Code.This proposed change relocates the reference to the set point table to Limiting Condition for Operation (LCO)3.7.1.1 and renumbers the table accordingly. |
| : OPERABLE, withliftsettingsandorificesizesasshowninTable4.7-0,inaccordance withSectionXIoftheASMEBoilerandPressureVesselCode,1974Edition.TheEditionoftheASMECodeendorsedforthesecondtenyearintervalforSt.LucieUnit2isthe1986EditionoftheASMECode.Thisproposedchangerelocates thereference tothesetpointtabletoLimitingCondition forOperation (LCO)3.7.1.1andrenumbers thetableaccordingly.
| | This Technical Specification change eliminates the need for future changes to the Technical Specification because Specification 4.0.5 ensures that in-service testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. |
| ThisTechnical Specification changeeliminates theneedforfuturechangestotheTechnical Specification becauseSpecification 4.0.5ensuresthatin-service testingofASMECodeClass1,2and3pumpsandvalveswillbeperformed inaccordance withaperiodically updatedversionofSectionXIoftheASMEBoilerandPressureVesselCodeandAddendaasrequiredby10CFR50.55a.
| |
| n)*I' | | n)*I' |
| -St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Administrative ChanetoDeleteASMECodeReference ATTACHMENT 3DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Thestandards usedtoarriveatadetermination thatarequestforamendment involvesanosignificant hazardsconsideration areincludedintheCommission sregulation, 10CFR50.92,whichstatesthatnosignificant hazardsconsiderations areinvolvediftheoperation ofthefacilityinaccordance withtheproposedamendment wouldnot(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences of'anaccidentpreviously evaluated. | | -St.Lucie Unit 2 Docket No.50-389 Proposed License Amendment Administrative Chan e to Delete ASME Code Reference ATTACHMENT 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves a no significant hazards consideration are included in the Commission s regulation, 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (1)involve 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 of safety.Each standard is discussed as follows: (1)Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of'an accident previously evaluated. |
| Theproposedamendment doesnotinvolveasignificant, increaseintheprobability orconsequences ofanaccidentpreviously evaluated becausethemainsteamcodesafetyvalveswillcontinuetobetestedinaccordance withcurrentNRCrequirements asimplemented through10CFR50.55a.TheNRCspecifies theASMEcoderequirements
| | The proposed amendment does not involve a significant, increase in the probability or consequences of an accident previously evaluated because the main steam code safety valves will continue to be tested in accordance with current NRC requirements as implemented through 10 CFR 50.55a.The NRC specifies the ASME code requirements |
| 'forafacilitythroughrevisions to10CFR50.55aandthroughthereviewandapprovaloftheplantspecificin-service testingplanforpumpsandvalvesatthebeginning ofeachin-service inspection interval. | | 'for a facility through revisions to 10 CFR 50.55a and through the review and approval of the plant specific in-service testing plan for pumps and valves at the beginning of each in-service inspection interval.The probability or consequences of an accident are not increased because testing of the main steam safety valves is in accordance with the appropriate NRC requirements. |
| Theprobability orconsequences ofanaccidentarenotincreased becausetestingofthemainsteamsafetyvalvesisinaccordance withtheappropriate NRCrequirements.
| | (2)Use of the modified specification would not create the possibility of a new or different, kind of accident from any previously evaluated. |
| (2)Useofthemodifiedspecification wouldnotcreatethepossibility ofanewordifferent, kindofaccidentfromanypreviously evaluated. | | The use of, this modified specification can not create the possibility of a new or different kind of accident from any previously evaluated since there is no physical change to the facility or the set points for the main steam safety valves.The valves will be tested in accordance with current requirements. |
| Theuseof,thismodifiedspecification cannotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated sincethereisnophysicalchangetothefacilityorthesetpointsforthemainsteamsafetyvalves.Thevalveswillbetestedinaccordance withcurrentrequirements.
| | No new failure mode is introduced due to the change because no plant change is being made and main steam safety valve test methods are consistent with the endorsed edition of the ASME Code. |
| Nonewfailuremodeisintroduced duetothechangebecausenoplantchangeisbeingmadeandmainsteamsafetyvalvetestmethodsareconsistent withtheendorsededitionoftheASMECode.
| | t f IE~I t 1" 1'I V"(3)Use of the modified specification would not involve a significant reduction in a margin of safety.The existing technical specification references an outdated version of the ASME Code.This change corrects the reference to Specification 4.0.5 which ensures that in-service testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.Safety valve setpoints or tolerances are not changed by this proposal.Therefore, the modified specification corrects the ASME Code reference and does not involve a significant reduction in a margin of safety.Based on the above, we have determined that the proposed amendment does not (1)involve a significant increase in the probability or consequences of an accident previously evaluated, (2)create the probability of a new or different kind of accident from any previously evaluated, or (3)involve a significant reduction in a margin of safety;and therefore does not involve a significant hazards consideration. |
| tfIE~It1" 1'IV"(3)Useofthemodifiedspecification wouldnotinvolveasignificant reduction inamarginofsafety.Theexistingtechnical specification references anoutdatedversionoftheASMECode.Thischangecorrectsthereference toSpecification 4.0.5whichensuresthatin-service testingofASMECodeClass1,2and3pumpsandvalveswillbeperformed inaccordance withaperiodically updatedversionofSectionXIoftheASMEBoilerandPressureVesselCodeandAddendaasrequiredby10CFR50.55a.Safetyvalvesetpoints ortolerances arenotchangedbythisproposal.
| | 0 1 I ep l}} |
| Therefore, themodifiedspecification correctstheASMECodereference anddoesnotinvolveasignificant reduction inamarginofsafety.Basedontheabove,wehavedetermined thattheproposedamendment doesnot(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createtheprobability ofanewordifferent kindofaccidentfromanypreviously evaluated, or(3)involveasignificant reduction inamarginofsafety;andtherefore doesnotinvolveasignificant hazardsconsideration. | |
| 01Iepl}}
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Proposed TS Section 3/4.7.1.1,turbine Cycle,Safety Valves, Deleting Ref to 1974 Edition of ASME Code & Referring to Testing in Accordance W/Ts 4.0.5,ISI & IST Spec| ML17228A570 |
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| Site: |
Saint Lucie  |
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| Issue date: |
05/23/1994 |
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| From: |
FLORIDA POWER & LIGHT CO. |
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| To: |
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| Shared Package |
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| ML17228A568 |
List: |
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| References |
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| NUDOCS 9406010046 |
| Download: ML17228A570 (11) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17241A3541999-06-0101 June 1999
Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3451999-05-24024 May 1999
Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks
ML17229B0711999-03-19019 March 1999
Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit
ML17229B0201999-02-23023 February 1999
Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution
ML17229A9551998-12-16016 December 1998
Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9161998-11-25025 November 1998
Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases
ML17229A9251998-11-22022 November 1998
Proposed Tech Specs 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
ML17229A9131998-11-19019 November 1998
Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML20155C3061998-10-29029 October 1998
Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses
ML17229A8441998-08-24024 August 1998
Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal
ML17229A7731998-06-15015 June 1998
Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b
ML17229A7601998-06-0303 June 1998
Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank
ML17229A7511998-05-27027 May 1998
Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A7481998-05-27027 May 1998
Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7441998-05-27027 May 1998
Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A6501998-03-0303 March 1998
Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls
ML17229A5691997-12-31031 December 1997
Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9131997-12-29029 December 1997
Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5491997-12-0101 December 1997
Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion
ML17229A4621997-08-22022 August 1997
Proposed Tech Specs Pages,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 Control Section 6.8
ML17229A4341997-08-0101 August 1997
Proposed Tech Specs,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 & Associated SE
ML17229A3601997-05-29029 May 1997
Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases
ML17229A1831996-12-20020 December 1996
Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings
ML17229A1611996-12-0909 December 1996
Proposed Tech Specs 1.9a Re Core Operating Limits Rept
ML17229A1191996-10-31031 October 1996
Proposed Tech Specs 6.0 Re Administrative Controls
ML17229A1111996-10-30030 October 1996
Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel
ML17229A1091996-10-28028 October 1996
Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1061996-10-28028 October 1996
Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel
ML17228B5641996-07-15015 July 1996
Revised Tech Specs Re Core Alteration Definition
ML17228B5041996-06-0101 June 1996
Proposed Tech Specs Re Thermal Margin & RCS Flow Limits
ML17228B3761996-01-0404 January 1996
Proposed Tech Specs Rectifying Discrepancy for Each St Lucie Unit & Providing Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17228B3361995-11-22022 November 1995
Proposed TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation,Adapting STS for C-E Plants (NUREG-1432) Spec 3.4.15
ML17228B2451995-08-16016 August 1995
Proposed TS 3.6.6.1, Sbvs.
ML17228B2421995-08-16016 August 1995
Proposed Ts,Reflecting Relocation of Selected TS Requirements Re Instrumentation & Emergency & Security Plan Review Process,Per GL 93-07
ML17228B1891995-06-21021 June 1995
Proposed Tech Specs Re Safety Injection Tank Surveillances
ML17228B1811995-06-21021 June 1995
Proposed Tech Specs Re Time Allowed to Restore Inoperable LPSI Train to Operable Status
ML17228B1791995-06-21021 June 1995
Proposed Tech Specs Re Extended Allowed Outage Time for EDGs
ML17228B1471995-05-17017 May 1995
Proposed Tech Specs,Extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
ML17228B1441995-05-17017 May 1995
Proposed Tech Specs Re Administrative & Conforming Update
ML17228B0901995-04-0303 April 1995
Proposed Tech Specs Re Incorporation of line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 for Licenses DPR-67 & NPF-16
ML17228B0591995-02-27027 February 1995
Proposed TS Re Sdcs Min Flow Rate Requirements
ML17228B0521995-02-27027 February 1995
Proposed Tech Spec Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relays
ML17228B0331995-02-22022 February 1995
Proposed TS 4.6.1.3,reflecting Deletion of Refs to Automatic Tester for Containment Personnel Air Lock
ML17228A9921995-01-20020 January 1995
Proposed Tech Specs,Relocating Operability Requirements for Incore Detectors to (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillance 4.10.2.2,4.10.4.2 & 4.10.5.2
ML17228A9031994-11-0202 November 1994
Proposed Tech Specs 3/4.6.2.1 & 3/4.6.2.3,adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants
ML17228A8911994-10-27027 October 1994
Proposed Tech Specs,Incorporating Administrative Changes
ML17228A6521994-07-28028 July 1994
Proposed Tech Specs Re LTOP Requirements for Power Operated Relief Valves,Per GL 90-06
ML17228A6591994-07-25025 July 1994
Proposed Tech Specs Implementing Enhancements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SR for Testing During Power Operation.
ML17228A6561994-07-25025 July 1994
Proposed Tech Specs for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants
ML17228A5771994-05-23023 May 1994
Proposed Tech Specs Removing Option That Allows HPCI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability
1999-06-01
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999
Rev 35 to HP-90, Emergency Equipment.
ML17309A9941999-06-17017 June 1999
Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples.
ML17241A3541999-06-0101 June 1999
Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17309A9951999-05-27027 May 1999
Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples.
ML17241A3451999-05-24024 May 1999
Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks
ML17229B0711999-03-19019 March 1999
Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit
ML17229B0441999-03-0202 March 1999
Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr
ML17229B0201999-02-23023 February 1999
Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution
ML17229B0361998-12-22022 December 1998
Rev 20 to Procedure C-200, Odcm.
ML17229A9551998-12-16016 December 1998
Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9161998-11-25025 November 1998
Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases
ML17229A9251998-11-22022 November 1998
Proposed Tech Specs 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
ML17229A9131998-11-19019 November 1998
Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML20155C3061998-10-29029 October 1998
Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses
ML20153G0781998-08-26026 August 1998
Rev 19 to Plstqp, Guard Training & Qualification Plan
ML17229A8441998-08-24024 August 1998
Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal
ML17229A7731998-06-15015 June 1998
Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b
ML17229A7601998-06-0303 June 1998
Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank
ML17229A7441998-05-27027 May 1998
Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A7481998-05-27027 May 1998
Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7511998-05-27027 May 1998
Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A6751998-03-27027 March 1998
Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr
ML17229A6501998-03-0303 March 1998
Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls
ML17229A6381998-02-12012 February 1998
Rev 19 to C-200, Offsite Dose Calculation Manual.
ML17229A6151998-01-12012 January 1998
Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan.
ML17229A6141998-01-12012 January 1998
Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1.
ML17229A5691997-12-31031 December 1997
Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9131997-12-29029 December 1997
Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5851997-12-12012 December 1997
Rev 0 to ADM-29.01, IST Program for Pumps & Valves.
ML17229A5491997-12-0101 December 1997
Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion
ML17309A9171997-11-26026 November 1997
Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis.
ML17229A5931997-09-26026 September 1997
Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures.
ML17229A5921997-09-18018 September 1997
Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening.
ML20211Q5841997-09-10010 September 1997
Rev 18 to Training & Qualification Plan
ML17229A4621997-08-22022 August 1997
Proposed Tech Specs Pages,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 Control Section 6.8
ML17229A4341997-08-0101 August 1997
Proposed Tech Specs,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 & Associated SE
ML17309A8951997-06-11011 June 1997
Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project.
ML17229A3601997-05-29029 May 1997
Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases
ML17229A2981997-03-0606 March 1997
Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A.
ML17229A1831996-12-20020 December 1996
Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings
ML17229A1611996-12-0909 December 1996
Proposed Tech Specs 1.9a Re Core Operating Limits Rept
ML17229A1191996-10-31031 October 1996
Proposed Tech Specs 6.0 Re Administrative Controls
ML17229A1111996-10-30030 October 1996
Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel
ML17229A1061996-10-28028 October 1996
Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel
ML17229A1091996-10-28028 October 1996
Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A0951996-10-24024 October 1996
Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage.
ML17229A0861996-10-18018 October 1996
Startup Physics Testing Rept. W/961018 Ltr
ML17229A2441996-09-23023 September 1996
Rev 18 to Offsite Dose Calculation Manual (Odcm).
ML17228B5641996-07-15015 July 1996
Revised Tech Specs Re Core Alteration Definition
ML17229A0961996-06-12012 June 1996
Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination.
1999-06-30
[Table view] |
Text
INDEX LIST OF TABLES{Continued)
$$$$$$$$$$$$'$$$$$'$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$TABLE 3.7-1 PAG MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS......................
3/4 7-2 4.7-1 STEAM LINE SAFETY VALVES PER LOOP...SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3/4 7-3 3/4 7-8 4.7-2 3.7-3a 3.7-3b 3.7-4 3.7-5 4.8-1 4.8-2 3.8-1 SNUBBER VISUAL INSPECTION INTERVAL....................
3/4 7-22 ELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~D ELETED......
D FIRE HOSE STATIONS....................................
3/4 7-26 3/4 7-27 3/4 7-36 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES........................................
3/4 8-18 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES 3/4 7-38 DIESEL GENERATOR TEST SCHEDULE......"..................
3/4 8-8 BATTERY SURVEILLANCE REQUIREMENT...'...................
3/4 8-12 4.1')-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS ROGRAH~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P 3/4 11-2 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS ROGRAM~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P 3/4 11-8 3.12-1 3.12-2 4.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.........
3/4 12-3 REPORTING LEVELS fOR RADIOACTIVITY CONCENTRATIONS IN FNVIRONHENTAL SAMPLES.................................
3/4 12-7 DETECTION CAPABILITIES FOR ENVIRONHENTAL SAMPLE B 3/4.2-1 NALYS IS o i~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~A ELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~i'~~~~~D B 3/4..4-1 REACTOR VESSEL TOUGHNESS..............................
3/4 12-8 B 3/4 2-3 B 3/4 4-9 5.7-1 6.2-1 MINIMUM SHIFT CREW COHPOSITION-TWO UNITS WITH TWO SEPARATE CONTROL ROOMS 6-5 COMPONENT CYCLIC OR TRANSIENT LIMITS..................
5-5 9406010046 940523 PDR ADDt K 05000389 i PDR,~~" ST.LUCIE-UNIT 2 XXV Amendment No.S,.M 53
'I~
~~a 3/4.7 PLANT SYSTBtS 3/4.7.1 TURBINE CYCLE SAFETY VALVES Lr Cr TING CONDITION FOR OPERATION 9.7.1.1 All main steam line code safety valves shall be OPERABLE~cui4
/R'r.p APPLICABILITY:
MODES 1, Z and 3.ACTION: a.With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1;otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and'in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.b.The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.E ch m in s am li e code s fety val shall e demon trated PERA (E, w~thJlif sett ngs nd or ice siz as show in Tab 4.7-0 in ac rdan wig Se ion I o the NE Boile and Pre sure Yes el Cod , 1974 dftio.rt4 cac/HiXjo~al Jo'der<'y'<rvcwr Ee~~y~d~w~pJ o 7g~~"">"-~~v~~.-ST.LUG IE-UNIT 2 3/4 7-1 Amendment No8 Jl h VALVE NUMBER 3 7-2 TABLE STEAN LINE SAFETY VALVES PER LOOP LIFT SETTING 1%ORIFICE SI2E a.e.8202 0203 8204 8209 8210 8211 8212.8206 8207 8208 8213 8214 8215 8216 Header A Header B 8201 8205 1000 psia 1000 psia 1000 psia 1000 psia 1040 psia 1040 psia 1040 psia 1040 psia 16 in.2 16 in.2 16 in.16 in.16 in.16 in.2 16 in.2 16 in.
St.Lucie Unit 2 Docket No.50-389 Proposed License Amendment Administrative Chan e to Delete ASME Code Reference ATTACHMENT 2 SAFETY ANALYSIS Introduction A change is proposed to revise the St.Lucie Unit 2 Technical Specifications Section 3/4.7.1.1 to change the reference to, a specific edition of the ASME Code to a reference to testing in accordance with Technical Specification 4.0.5 and renumber the safety valve set point Table 4.7-0 to Table 3.7-2.The list of tables in the index is also revised.Discussion The proposed change to the St.Lucie Unit 2 Technical Specifications revises the specific reference to the Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition to be similar to the Unit 1 Technical Specification and consistent with the revised Standard Technical Specifications for Combustion Engineering Plants, NUREG 1432.In addition, the change renumbers the safety valve set point table from a surveillance table to an Limiting Condition for Operation (LCO)table.Surveillance requirement 4.7.1.1 currently states that, each main steam line code safety valve shall be demonstrated OPERABLE, with lift settings and orifice sizes as shown in Table 4.7-0, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition.The Edition of the ASME Code endorsed for the second ten year interval for St.Lucie Unit 2 is the 1986 Edition of the ASME Code.This proposed change relocates the reference to the set point table to Limiting Condition for Operation (LCO)3.7.1.1 and renumbers the table accordingly.
This Technical Specification change eliminates the need for future changes to the Technical Specification because Specification 4.0.5 ensures that in-service testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.
n)*I'
-St.Lucie Unit 2 Docket No.50-389 Proposed License Amendment Administrative Chan e to Delete ASME Code Reference ATTACHMENT 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves a no significant hazards consideration are included in the Commission s regulation, 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (1)involve 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 of safety.Each standard is discussed as follows: (1)Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of'an accident previously evaluated.
The proposed amendment does not involve a significant, increase in the probability or consequences of an accident previously evaluated because the main steam code safety valves will continue to be tested in accordance with current NRC requirements as implemented through 10 CFR 50.55a.The NRC specifies the ASME code requirements
'for a facility through revisions to 10 CFR 50.55a and through the review and approval of the plant specific in-service testing plan for pumps and valves at the beginning of each in-service inspection interval.The probability or consequences of an accident are not increased because testing of the main steam safety valves is in accordance with the appropriate NRC requirements.
(2)Use of the modified specification would not create the possibility of a new or different, kind of accident from any previously evaluated.
The use of, this modified specification can not create the possibility of a new or different kind of accident from any previously evaluated since there is no physical change to the facility or the set points for the main steam safety valves.The valves will be tested in accordance with current requirements.
No new failure mode is introduced due to the change because no plant change is being made and main steam safety valve test methods are consistent with the endorsed edition of the ASME Code.
t f IE~I t 1" 1'I V"(3)Use of the modified specification would not involve a significant reduction in a margin of safety.The existing technical specification references an outdated version of the ASME Code.This change corrects the reference to Specification 4.0.5 which ensures that in-service testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.Safety valve setpoints or tolerances are not changed by this proposal.Therefore, the modified specification corrects the ASME Code reference and does not involve a significant reduction in a margin of safety.Based on the above, we have determined that the proposed amendment does not (1)involve a significant increase in the probability or consequences of an accident previously evaluated, (2)create the probability of a new or different kind of accident from any previously evaluated, or (3)involve a significant reduction in a margin of safety;and therefore does not involve a significant hazards consideration.
0 1 I ep l