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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] |
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ACCELEP>TED DISIBUTION DEMONSTRON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8904100262 DOC.DATE: 89/03/31 NOTARIZED:
YES FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATXON SORENSEN,G.C.
Washington Public Power Supply System RECXP.NAME
'ECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET 05000397 R
SUBJECT:
Application for amend to License NPF-21,revising Tech Spec 3/4.2.6&3/4.2.7.I DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR
~ENCL j SIZE:'l (0+~~~TITLE: OR Submittal:
General Distribution NOTES: RECXPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACRS NRR/DEST/CEB 8H NRR/DEST/ICSB NRR/DEST/RSB 8E NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EXB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 5 5 6 6 1'1 1 1 1 1 1 1 0 1 1 1 1 1 1 RECIPXENT ID CODE/NAME PD5 PD NRR/DEST/ADS 7E NRR/DEST/ES B 8 D NRR/DEST/MTB 9H NRR/DOEA/TSB 11 OC G FILE 01 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1~1 1 1 1 0 1 1 R I NOTE'IO ALL"RIDS" RECIPIEMIS:
PLEASE HELP US'lO REDUCE WASTE!Col'ACT'IHE IXCUNEÃZ (XÃIBDL DESK, BOOM Pl-37 (EXT.20079)IO ELI?GXLTE YOUR NAME FRY DISTRIBUTION LISTS FOR DOCtBKÃIS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 26 c'II WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 March 31, 1989 G02-89-051 Docket No.50-397 U.S.Nuclear, Regulatory Commission Attn: Document Control Desk Nail Station Pl-137 Washington, D.C.20555 Gentlemen:
Subject:
NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS 3/4.2.6, POWER FLOW INSTABILITY AND 3/4.2.7 NEUTRON FLUX NOISE MONITORING IN SUPPORT OF THE SUPPLY SYSTEM RESPONSE TO IEB 88-07, SUPPLEMENT 1
Reference:
2)3)IE Bulletin 88-07, Supplement 1,"Power,, Oscillations in Boiling Hater, Reactors (BWRs)", dated 12/30/88 Letter, G02-89-030, GC Sor ensen (SS)to NRC,"Response to IE Bulletin 88-07, Supplement 1", dated 3/3/89 LetterG02-89-029, GC Sorensen (SS)to NRC,"Request for, Amendment to Technical Specifications Reload License Amendment (Cycle 5)", dated 3/3/89 The response to IEB 88-07, Supplement 1 (reference 1)provided in reference 2 stated in part that the Supply System would submit a proposed technical speci-fication amendment to replace the existing detect-and-suppress technical speci-fications with specifications based on the Advanced Nuclear Fuels (ANF)ANNA Stability Monitoring System.The current specifications require evaluation of neutron signal noise against a baseline noise level.The ANNA system provides a much str onger, faster, more sophisticated means of monitoring the stability of the reactor.core.g904i00262 50QQ397 89033i pDR ADOCK 0 pnc P
~V H s ,l I 4 A'Page Two RE()UEST FOR AMEND.TO TS 3/4.2.6 POWER FLOW INSTABILITY AND 3/4.2.7 NEUTRON FLUX NOISE MONITORING IN SUPPORT OF THE SUPPLY SYSTEM RESPONSE TO IEB 88-07, SUPPLEMENT 1 As described in reference 2, the Supply System has implemented the General Electric Interim Operating Recommendations as requested in reference 1.This implementation includes the definition of Regions A, B and C as defined in the recommendations.
The Supply System proposes a reduction in Region B (a region where operation is prohibited) and a corresponding increase in Region C (a region where operation is allowed under.controlled conditions).
The basis for, this proposal is that the use of the strongermonitoring capabilities represented in the ANNA system compensates for, an enlarged allowable operating region, such that the present safety margin is maintained.
This approach was discussed with L.Phillips and H.Ritchings of your, staff on January 31, 1989.Hence, in accordance with the Code of Federal Regulations, Title 10,'Parts 50.90 and 2.101, the Supply System hereby submits a request for, amendment to the WNP-2 Technical Specifications.
Specifically, the Supply System is requesting that the subject Technical Specifications be modified, as attached, to reflect the enhanced operating capabilities of the ANNA system over the present detect-and-suppress stability monitoring capabilities.
The proposed Technical Specification changes are intended to be implemented within the framework of the Interim Operating Recommendations.
The recommenda-tions will be modified to the extent that Region C is enlarged, and the ANNA system will support SIL 380 methods for detecting the onset of core insta-bility.The basis for enlargement of Region C is as follows: Those portions of Region B which fall outside a region of 0.9 decay ratio as calculated by Advanced Nuclear.Fuels (ANF)(in support of reload license applications) will be redefined as part of Region C, where oper ation is allowed under.a controlled manner, when fuel preconditioning is required.Those areas below the 100K rodline for which the calculated decay ratio is greater, than 0.9 will remain defined as Region B, where planned operation is prohibited.
For, cycle 5 opera-tion, decay ratio calculations indicate no value.of 0.9 or greater exists for points beneath the 1005 rodline.Therefore this application, which is being made in support of, and subsequent to, the cycle 5 reload license application, provides for, complete replacement of Region B with Region C (as they are currently defined in tHe Interim Operating Recommendations).
For, future cycles in which decay ratio values of 0.9 or greater, are calculated for points below the 1005 rodline, the allowable region will be modified accordingly.
e t Page Three REQUEST FOR AMEND-TO TS 3/4.2.6 POWER FLOW INSTABILITY AND 3/4.2.7 NEUTRON FLUX NOISE MONITORING IN SUPPORT OF THE SUPPLY SYSTEM RESPONSE TO IEB 88"07, SUPPLEMENT 1 Although the proposed changes are to be implemented within the framework of the Interim Operating Recommendations, the Supply System has structured the pro-posed Technical Specifications to be applicable to a viable long-term solution with a minimum number.of addi-tional changes.This solution incorporates a stability monitor, for, maneuvering in conjunction with additional automatic protection for power, operation, and is one of the final solutions currently under, consideration by the BWROG Stability Committee.
The current Technical Specifications incorporate the recommendations of General Electric Service Information Letter, (SIL)No.380 Revision 1 and the Staff's Safety Evaluation Report of GE Topical Report NEDE-24011 amendment 8.The current specifications define a"detect-and-suppress" region.Prior, to entry into this region, a baseline set of neutron signal noise values must be esta-blished.When operating in the region, neutron signal values must periodically be compared to these baseline values.If noise levels exceed baseline levels by a specified amount, action must be taken to exit the region.The basis for, this"detect-and-suppress".approach is that neutron signal noise has been demonstrated to increase as the core decay ratio increases.
The limits for acceptable noise are selected such that action will be taken before the onset of an instability results in limit cycle operation.
A stability monitoring system such as the ANNA system represents a significant improvement in monitoring the stability of a reactor, core.The ANNA system performs a sophisticated noise analysis technique to calculate the decay ratio of each of multiple neutron signals (LPRM and APRM).These calculations are performed automatically, such that peak-to-peak and decay ratio data is presented in near.real-time.
As a result, the ANNA system provides information more rapidly than existing methods, and without the distractions to control room staff imposed by current methods.In addition, the decay ratio informa-tion available through the ANNA system is a primary indicator, of the state of the cor.e stability, whereas the current indicator,, neutron signal noise level, is an indirect, less reliable means.Through use of the ANNA system a much more quantitative measure of the margin to instability exists, i.e.how close the measured decay ratio is to 1.0.This significant improvement in detecting the approach to a region of instability is the justification forthe proposed enlargement of Region-C.The Supply System has reviewed this amendment request per, 10 CFR 50.92 and has determined that it does not represent an unreviewed safety question or, a significant hazar d because it does not:
0'J t4'I 1 et/1~s il Page Four, REQUEST FOR AMEND.TO TS 3/4.2.6 POWER FLOW INSTABILITY AND 3/4.2.7 NEUTRON FLUX NOISE MONITORING IN SUPPORT OF THE SUPPLY SYSTEM RESPONSE TO IEB 88-07, SUPPLEMENT 1 2)Involve a significant increase in the probability or consequences of an accident previously evaluated because, as discussed above, the ANNA system represents a substantial improvement in the capability to detect-and-suppress, such that the present safety margin is preserved for, operation in an expanded Region C.The enlarged Region C represents a region in which operation was allowed for, WNP-2 until recently when the Interim Operating Recommendations were implemented.
As discussed above, operation in this region was allowed provided detect-and-suppress noise monitoring requirements were satisfied.
No instability events have been detected during oper ation at WNP-2.Recently, a portion of this region became prohibited from planned operation through adoption of the Interim Operat-ing Recommendations.
These Interim Operation Recommendations were made in response to GE calculations which showed, particularly for the later classes of GE plants, less margin to the MCPR safety limit may exist than was previously evaluated for, a certain class of limit cycle instability events.These recommendations were made in order to provide assurance that plants would not enter a region of unstable operation and experience limit cycle events which could violate the safety limit.The use of the ANNA system provides greatly improved ability to detect the approach to a region of instability.
It is the Supply System's judgement that this improved detection capability more than compensates forthe enlargement of Region C such that the present safety margin is preserved and in fact increased.
Hence, the probability or consequences of previously evaluated accidents are not increased by this change.Create the possibility of a new or, different kind of accident from any accident previously evaluated because the design basis function, to detect-and-suppress core instability events, remains the same and is enhanced by the ANNA system.The enlargement of the allowable operating region does not introduce any new or.different kind of accident, either stability or.non-stability related.Enlargement of the region does necessitate justification that the probability of occurrence of an insta-bility event is not increased.
This issue has been addressed above.The ANNA system is very similar, to the current method in terms of the equip-ment employed to monitor, the core.Both systems involve use of computer software.The ANNA system therefore does not introduce any new failure modes over.existing detect-and-suppress methods.In fact, the specific manner, in which WNP-2 is implementing ANNA will reduce the risk of postu-lated computer, failures, in that completion of an operability surveillance is required prior, to entry into the region.In addition, the ANNA system automatically provides a warning in the event of a failure.Hence a new or, different kind of accident due to implementation of ANNA and enlarge-ment of Region C is not credible.
Page Five RE()UEST FOR AMEND TO TS 3/4.2.6 POWER FLOW INSTABILITY AND 3/4.2.7 NEUTRON FLUX.NOISE MONITORING IN SUPPORT OF THE SUPPLY SYSTEM RESPONSE TO IEB 88"07, SUPPLEMENT 1 3)Involve a significant reduction in a margin of safety because as discussed above, the implementation of ANNA provides improved detection capability which more than compensates for, the enlargement of Region C.Hence, there is no reduction in the margin of safety due to this proposal.As discussed above, the Supply System consider:s 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.cummulative occupational radiation exposure.Accor-dingly, the proposed change meets the eligibility criter ia for categorical exclusion set forth in 10CFR 51.22(c)(9) and therefore, per 10CFR 51.22(b), an environmental assessment of the change is not required.This Technical Specification change 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 10CFR 50.91, the State of Washington has been provided a copy of this letter.Very truly yours, G.C.Sorensen, Manager Regulatory Programs PLP/bk Attachments cc: C Eschels-EFSEC JB Martin-NRC RV NS Reynolds-BCP8R RB Samworth-NRC DL Williams-BPA/399 NRC Site Inspector.
-901A X ,A a STATE OF WASHINGTON
))COUNTY OF BENTON)
Subject:
uo r%Akeeo/+~/Y E 4~Z/Sf.E.7 I, G.C.SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, 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.DATE 9/N CW, 1989 G.C.SOfPNSEN, 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~s day of ,1989.Ws"sask Notar u s a d r e State of Washington Residing at My commission ex ires 7/14/91.
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