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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
REGULATORY FORMATION D I STR I BUT ION SY M I
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ACCESSION NBR: 8602100226 DOC. DATE: 86/Oi/31 NOTARIZED: YES DOCKET 0 FAC IL: 50-397 WPPSS Nuclear Prospect> Unit 2> Washington Public Poee 05000397
- IJTH. NAME AUTHOR AFFILIATION SORENSEN> G. C. Washington Public Paver Supply System RECIP. NAME RECIPIENT AFFILIATION ADENSAM> E. G. BWR ProJect Dir ectorate 3
SUBJECT:
Appliction to amend License NPF-21> requesting exemption from App J Type B 8c C leak rate test schedules (NUREG/CR 4398) revising Tech Spec, Section 4. 6. 1. 2. d.
DISTRIBUTION CODE: AO17D COP IEB RECEIVED: LTR J ENCL i BIIE:
TITLE: OR Submittal: Append J Containment Leak, Rate Testing NOTES 05000397 OL: 12/20/83 RECIPIENT COPIES RECIPIENT COPIES IQ CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL BWR ADTS 1 BWR PD3 PD 01 5 5 BWR EB 1 1 BWR EICSB 1 BWR FOB 1 1 BRADFUTE> J 1 1 BWR PSB 1 BWR RSB 1 1 INTERNAL: ACRS 07 10 10 ADM/LFMB 1 0 ELD/HDS2 08 1 NRR BWR ADTS 1 1 NRR PWR-A ADTS 1 NRR PWH=B ADTS 1 1 NRR/DSRO DIR 1 1 REG FILE 04 1 1 RGN5 1 1 EXTERNAL: 24X LPDR 03 1 1 NRC PDR NSIC 05 1 1 QP, t L.iAW PgP g~ (J>AO~
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Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 January 31, 1986 G02-86-119 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Ms. E. G. Adensam, Project Director BMR Project Directorate No. 3 Division of BMR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Ms. Adensam:
Subject:
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REQUEST FOR EXEMPTION TO APPENDIX J TYPE B 5 C LEAK RATE TEST SCHEDULES AND RELATED TECHNICAL SPECIFICATION AMENDMENT CHANGE SECTION 4.6.1.2.d
Reference:
NUREG/CR-4398, "Cost Analysis of Revisions to 10 CFR Part 50, Appendix J, Leak Tests for Primary and Secondary Containments of Light-Mater-Cooled Nuclear Power Plants", dated September 1985 Type' and C leak rate testing schedules as prescribed by Appendix J, Section III.D are:
"Type B tests, except tests for airlocks, shall be performed during reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than 2 years."
- And, "Type C tests shall be performed during each reactor shutdown for refueling but in no case at intervals greater than 2 years."
The related technical specification states that, "type B and C tests shall be conducted at intervals no greater than 24 months . . .", which is clarified in paragraph 4.6. 1.2.j such that "the provisions of specification 4.0.2 are not applicable to 24 month intervals". 4.0.2 allows a 25%
extension to surveillance intervals which, as stated above, is not permitted.
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E. G. Adensam Page Two January 31, 1986 REQUEST FOR EXEMPTION TO APPENDIX J TYPE B 5 C LEAK RATE TEST SCHEDULES AND RELATED TECH. SPEC. AMENDMENT CHANGE SECTION 4.6. 1.2.d The Supply System, as discussed below, considers that strict compliance to these schedules misdirects resources and imposes an unnecessary burden on plant operations for WNP-2. Accordingly, per 10 CFR 50.90 and 2.101 the Supply System requests the technical specification surveillance requirement be amended as attached and exemptions per 10 CFR 50. 12(a) to Appendix J be granted to allow Type C testing in accordance with the technical specification and to accommodate outage schedules which, due to weather conditions and the unique Pacific Northwest electric generation profile, can produce undue hardship in compliance to a strict two year test schedule.
The first exemption requested concerns the discrepancy between Type C testing per Appendix J "each refueling outage" and the technical speci-fication "at intervals no greater than 24 months". As related in previous correspondence, WNP-2 provides power to the Bonneville Power Administration (BPA) grid which is heavily dependent on hydroelectric power generation, in turn impacted by seasonal variation in snow pack and spring runoff in the Pacific Northwest. The spring runoff and subsequent increase in hydro-electric capacity is the most opportune time for WNP-2 refueling. Hence, the BPA directs the Supply System to, refuel on a yearly basis, ideally coinciding with the peak period of hydroelectric capacity. Strict compliance with Appendix J would then require Type C testing on a yearly basis which the Supply System considers to be beyond the original intent of Appendix J and which consumes far more resources than appropriate. Under the special circumstances dictated by the unique electrical generation profile dis-cussed above, the Supply System must commit 100 percent more resources to meet the "each refueling outage" stipulation than the "two year" technical specification statement. The intent of Appendix J statement "in no case at intervals greater than two years", was based on limiting the exposure of components to service conditions between tests to less than two years. The "each refueling outage" also imposed by Appendix J, strictly applied to WNP-2 is beyond the original intent. A strict appli-cation is not necessary to achieve the purpose of the rule.
Granting the proposed exemption is in the best interest of the public.
The committed resources beyond the intent of Appendix J could be better focused on other plant support tasks. The most recent Type B and C test leak rate program conducted at WNP-2 consumed in excess of 5,000 manhours which, using Industry labor rates developed in support of the referenced NUREG, exceeds $ 200,000. Type C testing, as stated in the reference, consumes the majority of the resources used for leak rate testing. This resource could be better focused in support of other plant activities rather than utilized on excessive over testing required by strict compliance to Appendix J.
Additionally, as documented in the reference NUREG, the average exposure for Type B and C testing at BWRs is approximately 7 man-rem with Type C testing again causing the majority of the exposure. Strict compliance with Appendix J and acceptance of this exposure is not in keeping with the WNP-2 as low as reasonably achievable (ALARA) program nor consistent with NRC policies on ALARA.
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E. G. Adensam Page Three January 31, 1986 REQUEST FOR EXEMPTION TO APPENDIX J TYPE B 5 C LEAK RATE TEST SCHEDULES AND RELATED TECH. SPEC. AMENDMENT CHANGE - SECTION 4.6. 1.2.d With this exemption the Supply System intends to yearly test approximately one half of the Type C valves. In a two year cycle all valves would be tested. Additionally, the Supply System has a program which will identify valves approaching excessive leak rates and, depending on leak rate, valve type, and service conditions will schedule these valves for yearly tests until the measured leak rate returns to an acceptable value. However, if this condition. persists despite an improved maintenance program and increased testing, the valve shall be evaluated for modification. This program is similar to that recommended by the referenced NUREG for a Corrective Action Plan (CAP): "halving the test and servicing cycle length to one year, therefore, would seem to be a reasonable approach for a cap (si'c)". This program provides additional assurance that Type C testing at WNP-2 will continue to meet the intent of Appendix J=.
In summary, this proposed exemption is within the intent of Appendix J, does not pose an undue risk to public health and safety, allows more efficient allocation of resources and minimizes exposure in keeping with ALARA programs. The Supply System has determined that this exemption is authorized by law per 10 CFR 50.12.
The remaining technical specification change and Appendix J exemption requests concern the two year interval imposed for both Type B and C tests: "in no case at intervals greater than 2 years". As discussed earlier, the timing for liNP-2 refueling outages is dependent on annual snow melt and spring runoff. For planning purposes the date nominally scheduled for the refueling outage is April 15 of each year. Obviously, depending on the vagaries of weather in the Pacific Northwest, the snow melt, runoff and subsequent hydroelectric capacity can either be delayed or early. It is not anticipated that any outage, if deferred due to weather, would be delayed beyond May 15 of any year. As a result, l<NP-2 can not adhere to the stipulation "in no case at intervals greater than 2 years" and yet provide reliable service to the BPA grid. Given an early snow melt followed by a late spring on a two year cycle conceivable that compliance would cause a shutdown during a period of it is low hydroelectric capacity and urgent need for l<NP-2 power. Forcasting, by BPA, of the precise date for any given refueling outage is not exact and usually can not be fixed with more than a month advance notice. For this reason a yearly-one-time-only request is not practical. For these reasons the Supply System requests that an exemption allowing a 3 month allowance on the Type B and C test interval be granted.
Obviously the scenario provided: an early spring followed by a late spring on a two year cycle, can be reversed and over the forty year life of the plant will be offset resulting in an average two year cycle. From this standpoint the intent of Appendix J to limit the exposure of components to service conditions between tests to less than two years is met over the life of the plant. Additionally, each outage (nominally two months) will be a period in which the components are not exposed to service conditions and as such will provide additional assurance for any specific
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E. G. Adensam Page Four January 31, 1986 REQUEST FOR EXEMPTION TO APPENDIX J TYPE B 5 C LEAK RATE TEST SCHEDULES AND RELATED TECH. SPEC. AMENDMENT CHANGE - SECTION 4.6.1.2.d test interval that actual exposure to service conditions is indeed less than two years. Thus, the proposed exemption is in keeping with this intent of Appendix J. Additionally, since the two year interval is maintained, this exemption does not represent an increase in risk to public health and safety.
In reality, strict compliance with Appendix J and subsequent shutdown at a period of high demand for power under the special circumstances described above is contrary to the public interest. Additionally, the intent of Appendix J as described in the exemption request for TVA (Federal Register posting Volume 49, No. 160, dated August 16, 1984) was that valves be tested at refueling outages and not to require a shutdown solely for local leak rate testing. This exemption request is in keeping with this intent of Appendix J in that it allows operation to continue to the most opportune time for refueling without forcing an outage and stays within the 2 year exposure limit imposed by Appendix J.
In summary, the Supply System considers this exemption request for a 3 month allowance to the 24 month Type B 8 C testing to be authorized by law, within the intent of Appendix J, does not represent an undue risk, avoids unnecessary plant shutdowns at periods of greatest need and is otherwise in the public interest.
llith regard to the proposed technical specification change (attached),
the Supply System has reviewed this request per 10 CFR 50.59 and 50.92 and has determined that 'it does not represerit an unreviewed safety question or significant hazard and does not:
Involve a signi.ficant i.ncrease,in the probability or consequences of an accident previously evaluated because', as discussed above, the proposed change maintains operation within the bounds intended by Appendix J. No increase in probability or conse-quences of an accident previously evaluated is represented by this proposal.
- 2) Create the possibility of a new or different kind of accident than previously evaluated because no new designs or plant operating modes are introduced by this amendment.
- 3) Involve a significant reduction in a margin of safety because, as discussed above, operation is maintained with the original intent of Appendix J. No threat to a safety margin is represented in this change.
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E. G. Adensam Page Five January 31, 1986 REQUEST FOR EXEMPTION TO APPENDIX J TYPE B 5 C LEAK RATE TEST SCHEDULES AND RELATED TECH. SPEC. AMENDMENT CHANGE - SECTION 4.6. 1.2.d This technical specification change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.
In accordance with 10 CFR 170.21, an application fee of One hundred fifty dollars ($ 150.00) accompanies this request. In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.
With a refueling outage scheduled for April 15, 1986, the Supply System desires to obtain this requested change and exemptions prior to commencing the outage. The potentially large expenditure of manpower, resources, and exposure represented by complete Type B and C testing requires a considerable amount of planning, scheduling and resource allocation. Contingency plans are being developed; however, any expedited processing of this request will be beneficial to the resource allocation and scheduling presently underway in support of the April refueling outage. Should you require any further information or assistance to aid in evaluating this request, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.
Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/tmh Attachments cc: JO Bradfute - NRC C Eschels - EFSEC JB Martin - NRC RV E Revell - BPA Reynolds - BLCP&R NS NRC,Site Inspector
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e EXEMPTION REQUEST - APPENDIX J TYPE B & C LEAK RATE TEST SCHEDULES STATE OF MASHINGTON )
Subject:
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County of Benton )
I, G. C. SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the MASHINGTON PUBLIC POMER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
GATE 5/ cJ ~ , 1986 or sen, an ager Regulato y Programs On this day personally appeared before me G. C. Sorensen to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this&/ day of 0 , 1986.
Notary u ic in a or t e F State of Mashington r r Resldlng at /g/
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