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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 DISHUBUTION DEMONSHRATION SYSTEM 0 ~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9003130355 DOC.DATE: 90/03/02'OTARIZED YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME . 'UTHOR AFFILIATION SORENSEN,G.C. Washington Public Power 'Supply System RECIP.NAME RECXPXENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License NPF-21,revising Tech Spec 3.8.1.1 to eliminate unnecessary starts.
I" t+3 D' DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR ) ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES
/
RECIPIENT COPIES RECIPIENT COPXES A
ID PD5 LA CODE/NAME SAMWORTH,R LTTR ENCL 1
5 1
5 ID CODE/NAME PD5 PD, 1,1 ENCL'TTR INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H '1 '
1 D NRR/DOEA/OTS B 1 1 1 1 NRR/DST 8E2 1 NRR/DST/SELB 8D NRR/DST/SICB 7E, NRR/DST/SRXB 8E'C/LFMB 1
1 1
1 1
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01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 R
D D
D NOTE TO ALL "RIDS" RECIPIENTS:
S PLEASE HELP US TO REDUCE WASTEl CONTACT THE, DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT." 20079) TO ELIMINATEYOUR NAME FROM DISHUBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPXES REQUIRED: LTTR 27 ENCL ,
25
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 March 2, 1990 G02-90-037 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 3.8.1.1$ AC SOURCES REDUCING EXCESSIVE TESTING OF DIESEL GENERATORS In accordance with the Code of Federal Regulations, Title 10, Part 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 testing of diesel generators (DGs), required by the Actions of Specification 3.8. 1. 1, AC Sources, be revised as attached to eliminate unnecessary starts.
Excessive DG starts is known to reduce the availability and reliability of the DG system. In addition to eliminating unnecessary starts the proposed changes will allow plant resources to focus on restoring equipment to operable status. The present technical specifications requiring a large number of DG starts diverts, to some extent, the attention of the plant staff to restoring failed equipment.
With implementation of the proposed changes DG availability and reliability will be improved and plant resources in the event of equipment failure more focused on returning equipment to operability rather than starting a diesel generator when its operability is not suspect. The changes requested are generally consistent with Technical Specifications approved by the NRC on all the most recently licensed facilities.
Excessive testing has been shown to result in degradation in diesel engines.
This conclusion was stated by the NRC in Generic Letter 84-15, "Proposed Staff Action To Improve and Haintain Diesel Generator Reliability." Horeover, the types of changes proposed by the Supply System are consistent with the types of changes to Action Statements reviewed and approved on the North Anna Power Station, Unit 2 in the NRC SER dated April 25, 1985.
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Page Two RE(UEST FOR ANENDNENT TO TS 3.8. 1.1, AC SOURCES REDUCING EXCESSIVE TESTING OF DIESEL GENERATORS There are four types of changes being requested to the Action Statements for inoperable DGs. Each one is discussed separately. For clarity, the existing Action a. (one offsite circuit, DG-1 or DG-2 inoperable) has been rewritten as Action a. (for one offsite circuit inoperable) and new Actions b. and h. have been added. New Action b. addresses DG-1 or DG-2 inoperable and new Action h.
covers the inoperability of DG-1 and DG-3 or DG-2 and DG-3. The Action h.
inoperability is not addressed by the present Technical Specifications. The proposed new action invokes the same requirements as the present Technical Specifications for DG-1 and DG-2 inoperable. Each of the remaining actions are renumbered to account for the new Action.
- 1. With one offsite circuit inoperable, the required DG start surveillance in Action a. is requested to be assumed to be satisfied if it had been satisfactorily performed within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With an offsite circuit inoperable, additional assurance of DG operability is required due to the greater likelihood of needing the DGs during this period. Currently, this is required regardless of when the previous surveillance was performed. Since assurance of DG operability is greatest immediately following a performance verification, there would appear to be no overriding need to re-perform this test if acceptable assurance operability exists. Twenty-four hours is considered acceptable based on the of competing desires to minimize excessive testing and the need for added assurance of operability. This time frame is also consistent with that approved by the NRC on many dockets.
This allowance will preclude a requirement to perform successive DG tests within a short time period solely due to the discovery of an inoperable offsite AC circuit. Due to the physical separation and design independence between offsite circuits and the DGs, the discovery of the inoperable offsite circuit will not, itself, lessen the assurance of DG operability obtained by the recent test.
- 2. Each of the Actions associated with inoperable AC sources, except renumbered Action e., requires testing operable DGs. This testing is currently required initially within 2 or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and then repetitively each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. The requested change will require only one DG start test, and allow its performance to be within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (if one DG is required to be tested) or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (if two or three DGs require testing).
The DG start testing is required to provide assurance that the remaining DGs are operable and provide assurance that a generic or common mode failure does not exist with the DGs. As was discussed in the above item, the competing desires to minimize excessive testing and the need for added assurance of operability can be satisfactorily met with a single test within a recent time frame. Continuing to repeat the surveillance for the limited duration of the Action (in all cases < 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) does not provide sufficient increased assurance of operability to warrant the decreased reliability caused by excessive testing.
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Page Three RE(UEST FOR AMENDMENT TO TS 3.8.1.1.,
AC SOURCES REDUCING EXCESSIVE TESTING OF DIESEL GENERATORS The allowance for 8 'ours when testing I DG (new Action e.) and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when testing two or three DGs (new Action a., b., c., d. and f.) is requested to provide more time to prepare for the tests without excessive pressures on the operations staff. In the event of an inoperable AC source, the foremost priority should be directed towards determination and correction of the cause for the inoperability. Although added assurance of the remaining DGs operability and/or verification of no generic problem is warranted, there is no reason to immediately suspect these DGs are not operable. Therefore, a reasonable period of time should be allowed to first assess the known inoperability, then make prudent preparations to perform the required DG surveillances. In the event where two or more DGs require testing, they must be performed sequentially, which accounts for the additional time to complete the surveillances. Relaxing the interval in which the DGs must be tested relieves the plant staff of an immediate priority which can divert resources from other important tasks and allows for more prudent resource and time management decisions to dictate immediate actions. This should also minimize personnel errors which are more prone to occur when under severe time constraints.
- 3. The requirement for operable DG testing when one or more DGs are inoperable (renumbered Actions b., d. and g.) is requested to be excepted inoperability(s) are known to not impact the operability of the other DGs.
if the Many circumstances, including Technical Specifications required surveillances, result in a DG becoming incapable of automatically responding to an accident signal, e.g., intentional lock out of DGs to I) perform preventive maintenance, or 2) air rolls prior to engine starts. Other circumstances can also result in an inoperable DG which obviously have no effect on other DGs. e.g., operational error,- low fuel oil level in the storage or day tank, fuse blown in a control circuit, the administrative declaration of a DG inoperable due to a Technical Specification Action, etc.
Many of these type of inoperabilities can be restored, independently tested, and the DG returned to operable status without that DG being started, while the Technical Specifications would still require the unaffected DGs to be started. This is a clear case of excessive DG testing.
When a DG is inoperable, testing the redundant DGs serves to verify no common mode failure exists which could render all DGs inoperable. The loss of a DG itself does not increase the likelihood o'f an event which would require the remaining DGs as is the case for an inoperable offsite circuit.
Therefore, there is no need to provide added assurance of DG operability above that provided by the normally required surveillances.
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. Page Four ~
REQUEST FOR AMENDMENT TO TS 3.8.1. 1.,
AC SOURCES REDUCING EXCESSIVE TESTING OF DIESEL GENERATORS t
The exception to not perform additional surveillances on DGs when one or more DGs are discovered inoperable "due to any cause other than preplanned preventive maintenance and testing" is allowed on many dockets. The more conservative change proposed by the Supply System recognizes this intent to minimize unnecessary and excessive DG testing, and more generally apply the same intent to a broader range of similar circumstances. This enhancement over previously NRC approved Actions requires assessing the potential for common mode failure irrespective of "preplanned preventive maintenance and testing" in progress. This is intended to avoid potentially inappropriate interpretations which would allow a potential common mode failure, discovered during (or "caused" due to) a planned surveillance test or preventive maintenance, to go undetected on other DGs.
Where the inoperability of DG-3 (previously Action c.) required the starting of DG-1 and DG-2 within 4 hours, the renumbered Action d. no longer requires this action. As described in the WNP-2 FSAR Chapter 8.3, DG-3 shares no commonality with DG-1 and DG-2. DG's 1 and 2 are dual drive units while DG-3 is a single drive unit all of which utilize the same basic diesel engine. A concern for common mode failure of the engines is not reasonable given the operating and maintenance history to date. Once assembled, the divergence of the designs, maintenance schedules, and operating requirements and history removes common mode practices and failures from concern. Assembly and support system designs. are different and no support systems are shared. As such a failure of DG-3 cannot imply common mode failure concerns with DG-1 and DG-2. Therefore tests of DG-1 or DG-2 in response to a failure of DG-3 is again a clear case of excessive testing.
The Supply System has evaluated this amendment request per 10CFR 50.92 and determined that it does not represent a significant hazard because it does not:
Involve a significant increase in the probability or consequences of an accident previously evaluated.
Loss of offsite power is analyzed as an event and is assumed to occur coincident with design basis accidents. The requirements for operability, routine testing and special testing of the offsite AC sources, when operating with inoperable equipment, have not been modified and therefore the reliability of the offsite circuits remains unaffected. The DG system functions to mitigate accident consequences, it is not assumed to be involved in the initiation of any design basis event. therefore, the changes to Actions involving increased testing of DGs will not increase the probability of a design basis event previously evaluated.
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. Page Five RE/VEST FOR AHENDHENT TO TS 3.8.1.1, AC SOURCES REDUCING EXCESSIVE TESTING OF DIESEL GENERATORS The function of the AC sources to mitigate the consequences of an analyzed event is based on supplying sufficient power to equipment assumed to function during an accident. The proposed change does not propose any hardware changes such as changes to load capability or to the required loads assumed in analyzed accidents. The requested changes will affect the need to perform surveillance procedures so as to enhance DG reliability by reducing the number of starts required. Therefore, the consequences of an accident previously evaluated is not increased.
Additionally, the ability of the plant to mitigate accidents is enhanced by allowing plant staff to direct their attention and resources to restoring inoperable equipment to service rather than immediately requiring attention to be focused on equipment whose operability is not suspect (i.e. DG starting). The time and resource used in starting the DG under the present technical specifications can be used to restore failed equipment and thereby return the plant to an optimum condition.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
The design function and operation of the DG system and the offsite power
,system is not affected by this change. There are no new modes of operation introduced. The reliability of the DG system to provide an emergency source of power is not reduced as no hardware changes are proposed and the proposed changes are enhancements to DG reliability and plant staff response capability. Therefore, there is no possibility of a new or different kind of accident being introduced due to this change.
- 3) Involve a significant reduction in a margin of safety.
The margin of safety associated with operation with inoperable AC sources is based on probabilities of a design basis event occurring, and the availability and reliability of the remaining operable sources. As discussed above, the probability of an event is not increased due to this requested change. The allowed outage times and -minimum required systems and components is not affected by this change. The availability and reliability is being enhanced by the reduction in required DG starts. Therefore, the margin of safety is not reduced by the change.
t RE(UEST FOR AMENDMENT TO TS 3.8. l. l.,
AC SOURCES REDUCING EXCESSIVE TESTING OF DIESEL GENERATORS t
The possibility of an undetected DG failure existing concurrent with the inoperability of one or more AC sources is the basis for the requirement to test remaining operable DGs. This requirement is assumed to be satisfied in this change request, provided it was performed within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This recent performance provides adequate assurance of the DG operability without unduly imposing excessive DG tests. The perceived gain in safety from re-demonstrating the operability of the remaining DGs is offset by the recent assurance of operability and the increase in the margin of safety by reducing tests starts.
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 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/bI<
Attachments cc: JB Martin - NRC RV NS Reynolds - BCP8R RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A C Eschels - EFSEC
STATE OF WASHINGTON)
Subject:
Re uest for Amendment to
. S. 3.8.1. , AC ources COUNTY OF BENTON ) Reducing Excessive Testing of Diesel Generators I, G. CD 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 A g/5'4, 1990 G. C. S ensen, 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.
GIVEII under my hand and seal this ~if day of,N . 1990.
otary lic sn an or e STATE OF WASHINGTON r
sails r rsrrr Residing at Yiy commission expires 7 14 91 "r ~ e+
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