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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
, ACCELERATED DRIBUTION DEMONS~TION SYSTEM.~(~ir~~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESS10N NBR:9003210063 DOC.DATE: 90/03/02 NOTARIZED:
YES DOCKET FACXL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C.
Washington.
Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License NPF-2l,revising TS 3.4.2&Tables 3.3.7.5-1 6 4.3.7.5-1..
DXSTRXBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SXZE: TITLE: OR Submittal:
General Distribution NOTES'EG FIL EXTERNAL: LPDR NSIC 01 RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACRS NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E COPXES LTTR ENCL 1 1 5 5 6 6 1 1 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1'1 1 1 0 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR.27 ENCL 25
~~~v WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 March 2, 1990 G02-90-038 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
Subject:
NUCLEAR PLANT NO.2, OPERATING LICENSE NPF-21 RE(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATION 3.4.2 (SAFETY RELIEF VALVES)AND TABLE 3.3.7.5-1 AND 4.3.7.5-1 (ACCIDENT MONITORING INSTRUMENTATION)
UNDER EMERGENCY CIRCUMSTANCES
Reference:
1)Letter, G02-89-221, GC Sorensen (SS)to NRC,"Request For Amendment To Technical Specification 3.3.7.5 for Safety Relief Valve Position Indication", dated 12/4/89 2)Letter, G02-90-025, GC Sorensen (SS)to NRC, same subject, dated 2/14/90 In accordance with the Code of Federal Regulations, Title 10, Parts 50.90, 2.101, and 50.91(a)(5), the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications on an emergency basis as provided for in the regulations.
Specifically, the Supply System is requesting that notes added to Specification 3.4.2, Safety Relief Valves and to Tables 3.3.7.5-1, Accident Monitoring Instrumentation, and 4.3.7.5-1, Accident Honitoring Instrumentation Surveillance Requirements be revised to allow the acoustic monitor on each SRV to be inoperable until the plant shuts down for its next scheduled refueling outage (see attached).
Action C for Specification 3.4.2, Safety Relief Valve and Action 80.a for Technical Specification Table 3.3.7.5-1, Accident Monitoring Instrumentation, require that the plant be shutdown if an inoperable indicator channel is not restored to operable status within seven (7)days.Due to a recent test failure the environmental qualification bases of the coaxial cables for the acoustic monitors has been invalidated.
Accordingly, the Supply System entered the seven day LCO at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on February 28, 1990.It has been determined that the plant will be required to be shutdown and cooled down in order to replace these cables, unless an amendment is granted to allow the Supply System to continue to operate until the next scheduled outage (R-5, no later than Hay 15, 1990).!90032l0063 900302 PDR ADOCK 05000397 P PDC Page Two REQUEST FOR AMEND TO TS 3.4.2 (SAFETY RELIEF VALVES)AND TABLE 3.3.7.5-1 AND 4.3.7.5-1 (ACCIDENT MONITORING INSTRUMENTATION)
UNDER EMERGENCY CIRCUMSTANCES The cable environmental qualification test failure was recognized during qualification testing of a replacement connector/cable assembly.The original connector had been discontinued.
A replacement connector/cable assembly (using the same cable)was being qualified.
During the long term qualification test, failure indications were observed.On February 27, 1990 a preliminary failure report was provided identifying the cable as having a failure potential when subjected to a LOCA following radiological and thermal aging.The report was reviewed and, it was determined that the acoustic monitors may not provide reliable indication of steam flow under post LOCA conditions.
Under normal operating and shutdown conditions, the cable qualification is acceptable.
However, due to the potential failure under the severe post LOCA conditions, in accordance with the subject Technical Specifications, the LCO was entered on February 28, 1990.As discussed in the references, the Supply System has made modifications to the acoustic monitors and changed procedures to increase the reliability of the monitors.This effort is ongoing.A design change, under consideration, would allow accessibility, without plant shutdown, of the system charge amplifier components pending successful environmental qualification of triaxial cable.Further a Vendor representative site visit has been requested to assist in identifying additional enhancements to system reliability.
The Supply System has been and is continuously working to improve this system.The operability of the accident monitoring instrumentation is based on providing assurance that sufficient information is available on selected plant parameters (e.g., SRV position indication) to monitor and assess important variables following an accident.THI Action Plan Item II.D.3"Direct Indication of Relief and Safety-Valve Position" requires that"reactor coolant system relief and safety valves shall be provided with a positive indication in the control room derived from a reliable valve-position detection device or a reliable indication of flow in the discharge pipe." The Technical Specifications for WNP-2 require two instrumentation channels for providing this information on valve position.One channel utilizes an acoustic monitor.The second channel utilizes thermocouples to detect a temperature increase indicative of flow past the valve.The loss of either or both channels on one or more SRVs does not prevent accurate determination of the position of the associated SRV(s).Further, should an SRV open and remain stuck open, the resulting transient does not represent the same magnitude of challenge to a BWR (such as WNP-2)as does a stuck open pressurizer relief or safety valve on a PWR.As discussed in the safety analysis of this event (WNP-2 FSAR 15.2.4), the operator response to this event is based on a suppression pool temperature alarm not an open alarm from the SRV position indication instruments.
The mitigating actions are to attempt to close the open SRV and establish suppression pool cooling within 20 minutes.As discussed in this analysis, even if the valve fails to close (worst case)the consequences of the event are mild.Hence the failure of an acoustic monitor causing an operator to review other instrumentation (as listed below)to determine which
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Page Three KEOUEST FOR AMEND TO TS 3.4.2 (SAFETY RELIEF VALVES)AND TABLE 3.3.7.5-1 AND 4.3.7.5-1 (ACCIDENT MONITORING INSTRUMENTATION)
UNDER EMERGENCY CIRCUMSTANCES valve is open does not increase the severity of the transient.
The valve can remain open.The loss of position indication for one or more of the eighteen Safety/Relief Valves does not reduce the capability of the SRV to perform its intended function, nor does it prevent accurate determination of the position of the associated SRV.The following mitigating and compensatory factors provide assurance that the valve position can be adequately monitored post LOCA: I)Tail pipe temperature indication is monitored and recorded.While thermocouples are not safety related devices, an increase in temperature would indicate that the valve is open and steam is entering the suppression pool via the tail pipe.Channel checks of the temperature recorder are required to be performed monthly per LCO 3/4.3.7.5.
Until the acoustic monitors are declared operable, the tail pipe temperature surveillance will be performed daily instead of monthly (see proposed change to Table 4.3.7.5-1 attached.)
A control room annunciator is available that alarms on high tail pipe temperature (greater than 250'F).During our most recent down power for final reset of control rods prior to coastdown, the response of each tailpipe thermocouple was observed by the Technical Staff Engineers and Operations.
The sensitivity and response to power change indicates adequate ability to sense relief valve steam flow during plant operation.
An annunciator response procedure addressing the tail pipe temperature alarm will be revised to uniquely identify appr'opriate acti'ons for alarms from the tail pipe temperature monitors.2)Suppression Pool temperature indication is available and is set to alarm at 85'F.An increase in suppression pool temperature would indicate an open SRV.This parameter will be monitored on a daily basis.3)Suppression Pool level indication is available and is set to alarm at+0.5"/-I" of Normal Level (466'3").An increase in suppression pool level would indicate an open SRV.This parameter will be monitored on a daily basis.4)Other plant parameters are affected by an SRV actuation and are available as confirmation.
Examples are main turbine governor valve position indication change, generator output change, main turbine steam flow change, steam/feedwater flow mismatch and the resultant reactor pressure perturbation.
Other indicators provide adequate feedback for ADS (reactor pressure)and SRV operation, and Alternate Shutdown Cooling operation (reactor pres-sure/temperature) if they are required.
IE r~~~a i!)r t I f Page Four REQUEST FOR AHEND TO TS 3.4.2 (SAFETY RELIEF VALVES)AND TABLE 3.3.7.5-1 AND 4.3.7.5-1 (ACCIDENT HONITORING INSTRUHENTATION)
UNDER EHERGENCY CIRCUHSTANCES As the cable failure for these acoustic monitors has only recently been identified, it was not possible for the Supply System to anticipate this event and submit this request in a more timely manner.Based on the above and the following no significant hazards consideration the Supply System requests that the amendment as attached be granted until the next scheduled outage (no later than Hay 15, 1990).Absent this amendment, the Supply System will be required to unnecessarily shutdown by Harch 7, 1990.The Supply System has evaluated this amendment per lOCFR 50.92 and determined that it does not represent a significant hazard because it does not: I)Involve a significant increase in the probability or consequences of an accident previously evaluated because the SRV position indication channels are not assumed to function in the initiation of an analyzed accident.The inoperability of these indication channels does not affect ADS operation of the SRVs.The analysis for an inadvertent opening of an SRV (FSAR Section 15.1.4)assumes the function of these alarm-only instrument channels for the purpose of having the operator assess the need for commencing suppression pool cooling with RHR.'s discussed above, the operator has many diverse indications available to indicate the need For commencing suppression pool cooling as a result of an open SRV and the SRV position indication is not the primary indication.
Loss of an SRV position indication channel will not adversely affect the operator's ability to respond to this event as'assumed in the analysis.The proposed change affects only the operability of the SRV position indication, and does not affect automatic or manual actuation of the SRV.Therefore, this change will not involve a significant increase in the probability or consequences of an accident previously evaluated.
2)Create the possibility of a new or different kind of accident from any accident previously evaluated because SRV operation, including the ADS function, remains unaffected.
No new modes of operation of any equipment result due to this change.Sufficient diverse indication remains available to adequately determine whether an SRV is inadvertently open, therefore this change will not result in a failure to assess the need for suppression pool cooling.This change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
3)Involve a significant reduction in a margin of safety because, as discussed above, the operator has many diverse indications available to indicate the need for commencing suppression pool cooling.Loss of an SRV position indication channel will not adversely affect the operator's ability to respond to this event as assumed in the analysis.The additional surveillances to monitor the suppression pool temperature while operation continues with an inoperable channel will compensate for the loss of position indication channel.Therefore, this change will not involve a significant reduction in the margin of safety.
t 0 a1\V 8 I'i b I)l Page Five RE(VEST FOR AHEND TO TS 3.4.2 (SAFETY RELIEF VALVES)AND TABLE 3.3.7.5-1 AND 4.3.7.5-1 (ACCIDENT HONITORING INSTRUHENTATION)
UNDER EHERGENCY CIRCUHSTANCES The cables will be replaced at the next outage (R-5).As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure.Accordingly, the proposed change meets the eligibility criteria for categorical exclusions et forth in lOCFR 51.22(c)(9) and therefore, per lOCFR 51.22(B), an environmental assessment of the change is not required.This amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee (POC)and the Supply System Corporate Nuclear Safety Review Board (CNSRB).In accordance with lOCFR 50.91 the State of Washington has been provided a copy of this letter.In summary, based on the assertion that no significant hazard is created by the subject relief and that remaining methods are available to satisfy the function of determining valve position, present operation does not represent an undue risk to the health and safety of the public.Absent this amendment, the WNP-2 Plant will be required to shutdown;Very truly yours, G.C.orensen, Hanager Regulatory Programs PLP/bk Attachments CC: JB Hartin-NRC RV NS Reynolds-BCP&R RB Samworth-NRC DL Williams-BPA/399 NRC Site Inspector-901A C'1/f 1 1 CJ STATE OF WASHINGTON
))COUNTY OF BENTON)Req.for Amend to TS 3.4.2 8
Subject:
under emergency circumstances
, i 1990 I, G.C.SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regul atory Pt ogr ams, for the WASHINGTON PUBLIC POWER 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.t DATE G.C.S ENS N, Manager Regulatory Programs On this day personally appeared before me G.C.SORENSEN to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this~day of p),1990.Nota y Pu lac in nd or t e State of Washing on Residing at J Jg