|
|---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17284A9101999-10-13013 October 1999
Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes
ML17284A8501999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown.
ML17284A8471999-07-29029 July 1999
Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level.
ML17284A8441999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a.
ML17284A8431999-07-29029 July 1999
Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring
ML17284A8401999-07-29029 July 1999
Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown.
ML17292B6891999-06-0303 June 1999
Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl
ML17292B6441999-04-20020 April 1999
Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630
ML17292B6321999-04-0707 April 1999
Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO
ML17292B4861998-12-17017 December 1998
Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125
ML17284A8071998-11-0909 November 1998
Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl
ML17284A7161998-08-0505 August 1998
Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1
ML17284A7051998-07-17017 July 1998
Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2
ML17292B3401998-04-16016 April 1998
Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi
ML17292B1301997-12-0404 December 1997
Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage
ML17292B0261997-08-14014 August 1997
Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line
ML17292A9401997-07-16016 July 1997
Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing
ML17292A8631997-05-20020 May 1997
Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615
ML17292A7561997-03-22022 March 1997
Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation
ML17292A5491996-10-15015 October 1996
Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl
ML17292A5381996-10-10010 October 1996
Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials
ML17292A4081996-08-0909 August 1996
Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971
GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996
Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage
ML17291B2781996-03-19019 March 1996
Application for Amend to License NPF-21,revising Containment Leakage Testing
ML17291B2071996-01-19019 January 1996
Application for Amend to License NPF-21 Re Primary Containment Leakage Testing
GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995
Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC
ML17291B0921995-10-26026 October 1995
Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys
ML17291A8421995-06-0606 June 1995
Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles
ML17291A8381995-06-0606 June 1995
Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59
ML17291A8321995-06-0606 June 1995
Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16
ML17291A7551995-04-25025 April 1995
Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1
ML17291A4791994-10-31031 October 1994
Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements
ML17291A4741994-10-31031 October 1994
Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys.
ML17291A4201994-09-26026 September 1994
Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis
ML17291A3941994-09-18018 September 1994
Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements
ML17291A3171994-08-0808 August 1994
Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program.
ML17291A2151994-07-12012 July 1994
Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits
ML17291A2201994-07-0808 July 1994
Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances
ML17290B1711994-05-0606 May 1994
Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication
ML17290B1551994-05-0505 May 1994
Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves.
ML17290A9631994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing
ML17290A9601994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations
ML17290A9551994-02-0808 February 1994
Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63
ML17290A9031994-01-13013 January 1994
Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation.
ML17290A8961994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements
ML17290A8781994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures
ML17290A8921994-01-0606 January 1994
Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2
ML17290A8391993-12-20020 December 1993
Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys.
ML17290A8181993-12-0606 December 1993
Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys
ML17290A8221993-12-0606 December 1993
Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H
1999-07-29
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17284A9101999-10-13013 October 1999
Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes
ML17284A8501999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown.
ML17284A8471999-07-29029 July 1999
Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level.
ML17284A8441999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a.
ML17284A8431999-07-29029 July 1999
Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring
ML17284A8401999-07-29029 July 1999
Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown.
ML17292B6891999-06-0303 June 1999
Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl
ML17292B6441999-04-20020 April 1999
Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630
ML17292B6321999-04-0707 April 1999
Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO
ML17292B4861998-12-17017 December 1998
Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125
ML17284A8071998-11-0909 November 1998
Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl
ML17284A7161998-08-0505 August 1998
Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1
ML17284A7051998-07-17017 July 1998
Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2
ML17292B3401998-04-16016 April 1998
Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi
ML17292B1301997-12-0404 December 1997
Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage
ML17292B0261997-08-14014 August 1997
Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line
ML17292A9401997-07-16016 July 1997
Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing
ML17292A8631997-05-20020 May 1997
Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615
ML17292A7561997-03-22022 March 1997
Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation
ML17292A5491996-10-15015 October 1996
Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl
ML17292A5381996-10-10010 October 1996
Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials
ML17292A4081996-08-0909 August 1996
Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971
GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996
Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage
ML17291B2781996-03-19019 March 1996
Application for Amend to License NPF-21,revising Containment Leakage Testing
ML17291B2071996-01-19019 January 1996
Application for Amend to License NPF-21 Re Primary Containment Leakage Testing
GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995
Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC
ML17291B0921995-10-26026 October 1995
Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys
ML17291A8421995-06-0606 June 1995
Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles
ML17291A8381995-06-0606 June 1995
Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59
ML17291A8321995-06-0606 June 1995
Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16
ML17291A7551995-04-25025 April 1995
Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1
ML17291A4791994-10-31031 October 1994
Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements
ML17291A4741994-10-31031 October 1994
Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys.
ML17291A4201994-09-26026 September 1994
Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis
ML17291A3941994-09-18018 September 1994
Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements
ML17291A3171994-08-0808 August 1994
Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program.
ML17291A2151994-07-12012 July 1994
Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits
ML17291A2201994-07-0808 July 1994
Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances
ML17290B1711994-05-0606 May 1994
Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication
ML17290B1551994-05-0505 May 1994
Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves.
ML17290A9631994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing
ML17290A9601994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations
ML17290A9551994-02-0808 February 1994
Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63
ML17290A9031994-01-13013 January 1994
Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation.
ML17290A8961994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements
ML17290A8781994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures
ML17290A8921994-01-0606 January 1994
Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2
ML17290A8391993-12-20020 December 1993
Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys.
ML17290A8181993-12-0606 December 1993
Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys
ML17290A8221993-12-0606 December 1993
Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H
1999-07-29
[Table view] |
Text
CATEGORY1REGULRIINPORMATION'DISTRIBUTIOiOYSTEN (RIDE)ACCESSION NBR:9707230291 DOC.DATE:
97/07/16NOTARIZED:
YESDOCKETFACIL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPowe05000397AUTH.NAMEAUTHORAFFILIATION BEMES,P.R.Washington PublicPowerSupplySystemREClP.NAME RECIPIENT AFFILIATION
- Document, ControlBranch(Document ControlDesk)
SUBJECT:
Application foramendtolicenseNPF-21,adding newminreactorvesselpressureversusreactorvesselmetaltemp(P/T)curves,applicable upto12Effective FullPowerYears.Changessupportvesselleaktesting.DISTRIBUTION CODE:BOOIDCOPIESRECEIVED:LTR IENCI,QSIZE:~+TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD4-2LACOLBURNgT COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD4-2PDCOPIESLTTRENCL11INTERNAL:
ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3EXTERNAL:
NOAC111111111011M7NRRDEEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR1111111111NOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR14ENCL13 WASHINGTON PUBLICPOWERSUPPLYSYSTEMP.O.Box968~Richland, Washington 99352-0968 July16,1997G02-97-144 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen:
Subject:
WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TOTECHNICAL SPECIFICATIONS TOSUPPORTVESSELLEAKTESTING
References:
1)LetterGO2-93-180, datedJuly9,1993,J.V.Parrish(SS)toNRC,"RequestforAmendment totheFacilityOperating LicenseandTechnical Specifications toIncreaseLicensedPowerLevelfrom3323MWtto3486MWtwithExtendedLoadLineandaChangeinSafetyReliefValveSetPointTolerance" 2)LetterG02-94-042, datedFebruary17,1994,J.V.Parrish(SS)toNRC,"WNP-2Operating LicenseNPF-21RequesttoAmendTechnical Specifications toSupportHydrostatic Testing"3)LetterGI2-95-099, datedMay2,1995,J.W.Clifford(NRC)toJ.V.Parrish(SS)"Issuance ofAmendment forWashington PublicPowerSupplySystemNuclearProjectNo.2(TACNos.M87076andM88625)"4)LetterGI2-94-148, datedMay27,1994,L.M.Padovan(NRC)toJ.V.Parrish(SS)"Issuance ofAmendment forWashington PublicPowerSupplySystemNuclearProjectNo.2(TACNo.M88839)"RenestforTechnical Secification Amendment TheSupplySystemherebyrequestsanamendment totheWNP-2Technical Specifications inaccordance withTitle10,Parts50.90and2.101oftheCodeofFederalRegulations.
970723029i 9'70716PDRADQCK0500039'7 PPDR,".300."-8 lllllllllilllllllllllllllllllilllllllll
~ggl a4III Page2Amendment toTechnical Specifications toSupportVesselLeakTestingSpecifically, theSupplySystemrequeststheadditionofnewminimumreactorvesselpressureversusreactorvesselmetaltemperature (P/T)curves,applicable upto12Effective FullPowerYears(EFPY).Therequested Technical Specification changesarenecessary tosupportleakandhydrotesting inaccordance withtheAmericanSocietyofMechanical Engineers (ASME)BoilerandPressureVesselCodeSectionXI.Leaktestingisacriticalpathitemduringourannualrefueling outages.Itisanticipated thatthechangedescribed inthisrequestcanreducetheamountoftimespentperforming leaktestingandtherebyenhancepersonnel safetyandoutagescheduleeffectiveness.
Werequest,therefore, thattherequested amendment beissuedintimetosupporttheSpring1998refueling outage(R-13).Issuanceoftherequested amendment onorbeforeMay1,1998,willsupportourschedule.
Detailsoftherequested changearediscussed below.PreviuReufrPrureTmureurveModification Reference 1proposednewP/Tcurvesunderpoweruprateconditions for32EFPY.Thebasisforthe32EFPYcurvesisfoundinReference 1andisnotrepeatedherein.Reference 2proposedhydrostatic testingutilizing an8EFPYcurvethatwasdeveloped usingsubstantially thesamemethodology asthe32EFPYcurve.Thedifference inmethodologies wasidentified onpage4ofReference 2.Thebasisforhydrostatic testingisfoundinReference 2andisnotrepeatedherein.TheReference 1and2requestswereapprovedbytheNRCinReferences 3and4.The12EFPYcurveinthissubmittal wasdeveloped usingthesamemethodology asfollowedinReference 2utilizing a12EFPYtemperature shiftof83.9'.PuroeandUeofPresure/TemeratureCurvePressure/Temperature Curvesbasedon12EFPYofneutronfluenceatpoweruprateconditions areusedonlyforleakandhydrostatic testingconditions duringnon-nuclear heatupoftheReactorPressureVessel.Itispossibletoconductleakandhydrostatic testingusingthe'existing 32EFPYcurve.However,thetestingconducted undertheproposed12EFPYcurveswillresultinagreatermarginforworkerindustrial safetywithnoadverseimpacttothepublichealthandsafety.EnhancedWorkerIndustrial afetMarinDuetothelowertotalfluencelevel,theproposed12EFPYcurvessupportuseofalowerminimumreactormetaltemperature attherequiredtestpressure.
Therequiredminimumtemperature fortestingunderthe12EFPYcurvesis185degreesFahrenheit.
Thisisapproximately 41degreesFahrenheit lowerthanthatwhichwouldberequiredbytestingusingthe32EFPYcurve.
t.fIfII Page3RequestforAmendment toTechnical Specifications SupportVesselLeakTestingSignificantly, then,,the 185degreeFahrenheit reactormetaltemperature corresponds toapproximately a200-210degreeFahrenheit averageReactorCoolantSystemtemperature (depending ontheheat-uprateachievedandthetimespentattheleaktesttemperature andpressure).
Thelowertemperature ofthe12EFPYcurves,therefore, providesagreatermarginofindustrial safetythanwouldbeprovidedusingthe32EFPYcurve.Theenhancedindustrial safetymarginisattributed tolowerreactorwatertemperatures, higherremaining heatsinkcapacity, andavoidance ofsteamflashing.
Themarginofnuclearsafetyisactuallyincreased byuseoftheproposedcurvesduetothelowerallowedtesttemperature whichincreases theavailable heatsinkfortheRCS.Basedontheforegoing, themarginofsafetyfortheplantwillnotbereducedasaresultofimplementing thenew12EFPYP/Tcurves.NoSinificantHazardsConsideration Determination TheSupplySystemhasevaluated theproposedchangepertherequirements of10CFR50.92.Theproposedadditionofthe12EFPYP/Tcurvesfortestingandnon-nuclear heatingdoesnotrepresent asignificant hazardsconsideration becauseitdoesnot:1)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Theproposed12EFPYcurvewasdeveloped usingthesamemethodology asthatusedinthecurrent32EFPYcurveandthe8EFPYcurve.Thismethodology isconsistent withtheguidanceprovidedinRegulatory Guide1.99,Revision2.Assumptions andparameters werethesameasthoseusedinthe8EFPYcurvecalculation.
However,fluencevaluesusedinthecalculation werethosefor12EFPY.Useofthe12EFPYcurvesonorbeforeattainment of12EFPYofoperation isequivalent tothepreviously approveduseofthe32EFPYcurvesonorbeforeattainment of32EFPYofoperation.
Therefore, theproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
2)Createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Theproposedchangeintroduces nocrediblemechanism forunacceptable radiation release.Theproposedchangedoesnotrequirephysicalmodification totheplant.The12EFPYcurvesareconsistent withthepreviously approved32and8EFPYcurves.
Page4RequestforAmendment toTechnical Specifications SupportVesselLeakTestingInservice hydrostatic orleaktestingisnotassumedtobeaninitiator ofanalyzedevents.Sinceapprovaloftheproposedamendment willensureadequateprotection ofthereactorpressurevessel,itwillnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.
3)Involveasignificant reduction inamarginofsafety.Theaccidentanalysesfortheplantasdescribed intheFSARarenotaffectedbythisproposedchange.The12EFPYcurvesweredeveloped usingthesamemethodology asthe32and8EFPYcurvesandthusinvolvenoreduction inthemarginofsafetyaspreviously evaluated.
Themarginofsafety,relativetotheavailable heatsinkintheReactorCoolantSystem,isactuallyincreased byuseoftheproposedcurvesduetothelowerallowedtesttemperature.
Therefore, theproposedchangedoesnotinvolveasignificant reduction inamarginofsafety.AmentCateoricalExcluionTheproposedchangemeetstheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).
Theproposedchangedoesnotinvolveasignificant hazardsconsideration, haveapotential forachangeinthetypes,orincreaseintheamount,ofanyeffluents thatmaybereleasedoff-site; orinvolveanincreaseinindividual orcumulative occupational radiation exposure.
Therefore, pertherequirements of10CFR51.22(b),
anenvironmental assessment ofthesechangesisnotrequired.
InernalandCNSRBReviewThisTechnical Specification changehasbeenreviewedandapprovedbytheWNP-2PlantOperations Committee andtheSupplySystemCorporate NuclearSafetyReviewBoard.tateotification Inaccordance with10CFR50.91,theStateofWashington hasbeenprovidedacopyofthisletter.
Page5RequestforAmendment toTechnical Specifications SupportVesselLeakTestingMarkufProedhaneAttachment 1providescopiesoftheimpactedportionoftheexistingTechnical Specifications.
AcleanversionofthechangeasproposedisprovidedasAttachment 2.Inordertobeconsistent withtheImprovedTechnical Specifications thenew12EFPYcurvesrequirethatthefiguresinLCO3.4.11berenumbered.
WehavealsoincludedproposedchangestotheBasesasAttachment 3.Thesechangesareforyourinformation onlyandwillbemadebytheSupplySystemuponreceiptoftheapprovedamendment.
Werequestthirtydaystoimplement theamendment uponnotification ofitsapproval.
Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecallmeorD.A.Swankat(509)377-4563.
- ectfully, P..ailDropPE23)VicePresident, NuclearOperations Attachments CC:EWMershoff-NRCRIVKEPerkins,Jr.-NRCRIV,WCFOTGColburn-NRRCRWallis-EFSECNRCSr.ResidentInspector
-927NDLWilliams-BPA/399PDRobinson-Winston&Strawn
STATEOFWASHINGTON
))COUNTYOFBENTON)
Subject:
RequestforAmendment toTStoSurtVeselLeakTestinI,P.R.BEMIS,beingdulysworn,subscribe toandsaythatIamtheVicePresident, NuclearOperations fortheWASHINGTON PUBLICPOWERSUPPLYSYSTEM,theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthestatements madeinitaretrue.DATE,1997P..is'nt,NuclearOperations Onthisdatepersonally appearedbeforemeP,R.BEMIS,tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledge thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.
G1VBNundermyhandandsealthis~&dayofS1997NotaryublicinanfortheSTATEOFWASHINGTON ResidingatMyCommission Expires
(~gg'LlI'l'elIlf((=e-"~lg~.~~:~~>)))1>iinl~>~
ATTACKVH<2lT 1CurrentTechnical Specification PageswithProposedChanges
