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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17284A9101999-10-13013 October 1999 Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8501999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8471999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level. ML17284A8441999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a. ML17284A8431999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring ML17284A8401999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl ML17292B6441999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6321999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4861998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML17284A8071998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl ML17284A7161998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7051998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17292B3401998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi ML17292B1301997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0261997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line ML17292A9401997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A8631997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7561997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A5491996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl ML17292A5381996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A4081996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage ML17291B2781996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing ML17291B2071996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B0921995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A8421995-06-0606 June 1995 Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles ML17291A8381995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 ML17291A8321995-06-0606 June 1995 Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16 ML17291A7551995-04-25025 April 1995 Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A4791994-10-31031 October 1994 Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4741994-10-31031 October 1994 Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys. ML17291A4201994-09-26026 September 1994 Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis ML17291A3941994-09-18018 September 1994 Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3171994-08-0808 August 1994 Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program. ML17291A2151994-07-12012 July 1994 Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits ML17291A2201994-07-0808 July 1994 Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17290B1711994-05-0606 May 1994 Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication ML17290B1551994-05-0505 May 1994 Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves. ML17290A9631994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing ML17290A9601994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations ML17290A9551994-02-0808 February 1994 Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63 ML17290A9031994-01-13013 January 1994 Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation. ML17290A8961994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements ML17290A8781994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures ML17290A8921994-01-0606 January 1994 Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2 ML17290A8391993-12-20020 December 1993 Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys. ML17290A8181993-12-0606 December 1993 Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys ML17290A8221993-12-0606 December 1993 Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H 1999-07-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17284A9101999-10-13013 October 1999 Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8501999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8471999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level. ML17284A8441999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a. ML17284A8431999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring ML17284A8401999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl ML17292B6441999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6321999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4861998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML17284A8071998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl ML17284A7161998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7051998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17292B3401998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi ML17292B1301997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0261997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line ML17292A9401997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A8631997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7561997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A5491996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl ML17292A5381996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A4081996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage ML17291B2781996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing ML17291B2071996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B0921995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A8421995-06-0606 June 1995 Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles ML17291A8381995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 ML17291A8321995-06-0606 June 1995 Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16 ML17291A7551995-04-25025 April 1995 Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A4791994-10-31031 October 1994 Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4741994-10-31031 October 1994 Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys. ML17291A4201994-09-26026 September 1994 Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis ML17291A3941994-09-18018 September 1994 Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3171994-08-0808 August 1994 Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program. ML17291A2151994-07-12012 July 1994 Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits ML17291A2201994-07-0808 July 1994 Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17290B1711994-05-0606 May 1994 Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication ML17290B1551994-05-0505 May 1994 Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves. ML17290A9631994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing ML17290A9601994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations ML17290A9551994-02-0808 February 1994 Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63 ML17290A9031994-01-13013 January 1994 Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation. ML17290A8961994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements ML17290A8781994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures ML17290A8921994-01-0606 January 1994 Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2 ML17290A8391993-12-20020 December 1993 Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys. ML17290A8181993-12-0606 December 1993 Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys ML17290A8221993-12-0606 December 1993 Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H 1999-07-29
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9010150136 DOC.DATE: 90/10/04 NOTARIZED: YES DOCKET'5 FACIL: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,changing TS 3.3.4 re ATWS recirculation pump trip sys instrumentation.
D DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution
! ENCL Q SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 ENG,,P.L. 2 2 D INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 D NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 S NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 0 1 0 OGC/HDS2 1 0 REG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R
D A
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 21
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Rtchland, Washfngton 99352 October 4, 1990 G02-90-168 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 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION 3.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION
Reference:
Letter, G02-90-110, GC Sorensen (SS) to NRC, "Anticipated Transients Without Scram Design Modifications", dated 6/22/90 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 specification be revised as attached to accommodate new design features implemented during our spring 1990 refueling outage.
In recent discussions between Hs. P. Eng and Hr. H. Lee (NRR) and Messrs P.
Powell and R. Green (SS) with regard to the design information provided by the referenced letter the subject Technical Specification was questioned.
Specifically, the "minimum operable channels per trip system - 1" was identified as possibly allowing a channel, in the new design, to be inoperable indefinitely.
As a result of these discussions the Technical Specification and the new design features were reevaluated resulting in the attached changes being identified.
The first change recognizes that, in the new design, channels can be placed in the trip condition without causing an ATWS Recirculation Pump Trip (ATWS-RPT) actuation. The old design did not have this feature. Previously a tripped channel caused an actuation. With the new design tripping a channel performs the intended safety function of the channel. Action paragraph b. is clarified to reflect this design feature by adding the phrase "per Trip Function" and deleting "for one trip function in one trip system". On Table 3.3.4. 1-1 Trip Function is made plural to also reflect this design feature. Additionally, a note has been provided clarifying the intent of the required action of tripping the channel.
The note indicates that tripping the channel is only applicable if placing the 9010150136 901004 PDR ADOCK 05000397 P PDC QOOl l(l
Page Two REQUEST FOR AMENDMENT TO TS 3.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION inoperable channel(s) in trip will not result in a recirculation pump trip. This change also permits operation to continue with the channel(s) in the tripped condition while channel operability is restored. In this condition, with the one-out-of-two-twice logic, half of the logic is satisfied and a valid signal on one of the other two channels will cause a recirculation pump trip. In this way placing an inoperable channel in the tripped condition will not inhibit an ATWS-RPT should an ATWS event occur. These changes achieve consistency with the BWR Standard Technical Specifications being implemented in the Improved Technical Specification Program.
The second change allows the Completion Time for placing inoperable channel(s) in trip to remain 14 days which is consistent with the currently allowed time a channel is allowed to be inoperable before taking further action. With the new logic further action consists of placing the channel in the tripped condition (unless an ATWS-RPT would occur). This change adds an additional required action to verify that one trip system is operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This allows 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to ensure the ATWS-RPT safety function for one pump remains viable. One hour is consistent with the Completion Time allowed by 3.0.3 prior to commencing any compensatory actions. The 14 days is acceptable because the second trip system is fully operable during this period. This is consistent with existing ECCS Technical Specification Completion Times established for conditions when one of several related trains is inoperable (HPCS, RCIC). These required actions assure that the potential for a single failure preventing a recirculation pump trip on a valid signal will be minimized. The changes achieve consistency with the BWR Standard Technical Specifications being implemented in the Improved Technical Specification Program.
The third change, reducing the Completion Time for reaching MODE 2 from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, achieves consistency with APPLICABILITY LCO 3.0.3. This change is consistent with the BWR Standard Technical Specifications being implemented in the Improved Technical Specification Program.
The third change, recommended in the above discussions, recognizes that the "minimum operable channels per trip system" should be changed from 1 to 2. With the new logic, one-out-of-two-twice, and the."MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM" being 1, a channel could conceivably be out of service in the one-out-of-two-twice-logic indefinitely without corrective or compensatory action being implemented. Operation of this system in this manner has never been the intent of the Supply System. To correct this oversight the attached change to Table 3.3.4.1-1 is submitted. This change combined with the revised requirements of LCO action statement 3.3.4. 1 b will ensure that corrective or compensatory actions are implemented upon the discovery of an inoperable channel.
The Supply System has reviewed these changes per 10 CFR 50.92 and provides the following in support of a finding for no significant hazards consideration.
The first change, allowing an inoperable channel to be placed in the tripped condition does not represent not:
a significant hazards consideration because it does
. 'age Three RE(VEST FOR AMENDMENT TO TS 3.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION Involve a significant increase in the probability or consequences of an accident previously evaluated because in the case of the first change the safety function of the channel is implemented by placing the channel in trip. This satisfies one half of the trip logic and ensures that a valid signal received on the other half of the logic will cause a recirculation pump trip. Further, this change does not result in any hardware or operating procedure changes. The ATWS-RPT instrumentation is not assumed in the initiation of any analyzed event. This instrumentation role is in mitigating and thereby limiting the consequences of an ATWS event. This instrumentation actuates to prevent reactor vessel overpressurization and fuel damage in the event of an ATWS. The proposed change to these actions will not allow continuous operation such that a single failure could prevent the instrumentation to actuate when required to mitigate the consequences of an ATWS event. Therefore, this proposed 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 the proposed change introduces no new mode of plant operation nor does it require physical modification to the plant.
- 3) Involve a significant reduction in a margin of safety. No significant reduction in a margin of safety is involved with this change since the required actions have been developed to assure the ATWS-RPT remains capable of mitigating the consequences of an ATWS event. This change also provides a benefit of avoiding an unnecessary plant transient when adequate compensatory measures are available to ensure the instrumen-tation's intended function will be satisfied.
Also the second change, allowing the 14 days Completion Time before placing inoperable channel(s) in the tripped condition and the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowed to verify the operability of an ATWS-RPT trip system do not represent a significant hazards consideration because they do not:
Involve a significant increase in the probability or consequences of an accident previously evaluated. This change does not result in any hardware or operating procedure changes. The ATWS-RPT instrumentation is not assumed in the initiation of any analyzed event. The instrumenta-tion's role is in mitigating and thereby limiting the consequences of an ATWS event. This instrumentation actuates to aid in protecting the fuel cladding in the event of an ATWS transient. The proposed change to the actions will not allow continuous operation such that a single failure will preclude ATWS-RPT actuation in order to mitigate the consequences of
,the transient. Therefore, the proposed 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 the proposed change introduces no new mode of plant operation nor does it require physical modification to the plant.
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Page Four REQUEST FOR AMENDMENT TO TS 3.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION
- 3) Involve a significant reduction in a margin of safety. No significant reduction in a margin of safety is involved with this change since the required actions have been developed to assure the ATWS-RPT remains capable of mitigating the consequences of the ATWS transient. This change also provides a benefit through the potential avoidance of an unnecessary plant transient by providing adequate time to take compensatory measures to ensure the instrumentation's intended function is satisfied.
The third change reducing the time allowed to reach startup from 8 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, does not represent a significant hazards consideration because it does not:
I) Involve a significant increase in the probability or consequences of an accident previously evaluated. The imposition of a more stringent requirement to this Technical Specification'ill not alter in any way a previously evaluated accident. Hovement to startup within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is recognized by LCO 3.0.3 as an acceptable time duration.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. The imposition of a more stringent requirement will not result in a new or different kind of accident than those previously evaluated.
- 3) Involve a significant reduction in a margin of safety. the imposition of a more stringent time requirement increases the margin of plant safety by decreasing the amount of time allowed to remain in an action statement.
The plant is returned quicker to a mode in which the action statement does not apply. Hence with a shorter duration the probability of an event occurring during the LCO interval is decreased and the margin of safety is enhanced.
The fourth change, increasing the "minimum operable channels per trip system" from one to two recognizes the new design and ensures that corrective or compensatory action will be commenced in a timely manner. This change does not represent a significant hazards consideration because it does not:
I) Involve a significant increase in the probability or consequences of an accident previously evaluated. This change imposes a more stringent requirement on the operation of WNP-2. It ensures action will be taken to restore the system to a safety condition (channel tripped or operable) in a timely manner. As discussed in the significant hazards discussion on the first change the ATWS-RPT instrumentation is not assumed in the initiation of any analyzed event. The instrumentation acts to mitigate and thereby limit the consequences of an ATWS event. This change will ensure the system will be able to respond to a valid trip signal on one channel when the other channel is inoperable. As such, this change enhances the system ability to respond and mitigate'the consequences of an ATWS event. At the same time this change combined with the new design does not increase the vulnerability of the plant to a spurious signal actuation. The previous design actuated on a single signal thereby being
.. Page Five REQUEST FOR AMENDMENT TO TS 3.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION vulnerable to a spurious actuation. In the new design with the inoperable channel in a tripped position the same vulnerability is present. However, this vulnerability only exists when the system is degraded. Hence the overall probability of a spurious actuation is reduced by the new design and the probability of a spurious signal actuation with channel(s) inoperable in accordance with the proposed action is the same as that that existed at all times with the old design. Therefore, the probability of a previously evaluated accident is not increased.
- 2) Create the possibility of a new or difference kind of accident from any previously evaluated because the proposed change introduces no new mode of plant operation nor does it require physical modifications to the plant.
- 3) Involve a significant reduction in a margin of safety because as discussed above the change ensures the system will be restored or put in a safe condition in a timely manner. As such, safe operation is assured and the margin of safety is not jeopardized.
As discussed above, the Supply System considers that these changes do 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 do they involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, these proposed changes meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and therefore, per 10 CFR 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: JB Hartin - NRC RV NS Reynolds - BCP8R PL Eng - NRC DL Williams - BPA/399 NRC Site Inspector - 901A CR Wallis - EFSEC
Request for Amend to TS 3.3.4 STATE OF WASHINGTON) ATWS Recir. Pump Trip System
)
COUNTY OF BENTON )
I, A. G. Hosier,, being duly sworn, subscribe to and say that I am the Manager, WNP-2 Licensing, 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.
This document contains Safeguards Information and must be protected in accordance with 10CFR 73.21.
OATE: l~/ ~
, 1990 CW~
A. G. Hosier, Manager WNP-2 Licensing On this day personally appeared before me A. G. Hosier, 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 , 1990.
otary Pu ic in n or t e STATE OF WASHINGTON Residing at My commission expires 4 28 94
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