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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
GORY 1 REGULAT RY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9908060097 DOC.DATE: 99/07/29 NOTARIZED:
YES DOCKET I FACIL:60-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUGER.NAME AUTHOR AFFILIATION WEBRING,R.L.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Application for amend to license NPF-21,revising Tech Specs SR 3.5.2.2,"Condensate Storage Tank Water Level." C DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal:
General Distribution SIZE: A NOTES: RECIPIENT ID CODE/NAME LPD4-2 LA SC COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME CUSHING,J COPIES LTTR ENCL 1 1 E G, 0 INTERNAL: ACRS NRR/DE/EEIB NRR/DSSA/SRXB OGC/RP EXTERNAL: NOAC 1 1 1 1 1 1 1 0 1 1 ILE CENTER 01.DSBA%855l3 NUDOCS-ABSTRACT NRC PDR'1 1 1 1 D 0 E N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OP COPIES REQUIRED: LTTR 12 ENCL 11
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richland, Washington 99352-0968 July 29, 1999 G02-99-144 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 REQUEST I<OR AMENDMENT'ECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANK WATER LEVEL
References:
1)Letter dated November 6, 1998, TF Stetka (NRC)to JV Parrish (SS),"NRC Inspection Report 50-397/98-15 and Notice of Violation" 2)Letter GO2-98-205, dated December 7, 1998, RL Webring (SS)to NRC,"NRC Inspection Report 98-15, Response to Notice of Violation" 3)NRC Administrative Letter 98-10, dated December 29, 1998,"Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety" In accordance with the Code of Federal Regulations, Title 10, Parts 2.101, 50.59 and 50.90, the Washington Public Power Supply System (Supply System)hereby submits a request for amendment to the WNP-2 Operating License.Specifically, the Supply System is requesting a revision to Technical Specification Surveillance Requirement (SR)3.5.2.2.This requirement verifies the adequacy of the water supply in the Condensate Storage Tanks (CSTs)which support operation of the High Pressure Core Spray (HPCS)system during Modes 4 and 5.Current Technical Specification SR 3;5.2.2 requires that CST water level be maintained above 13.25 feet in a single tank or above 7.6 feet"in each tank if the suppression pool level is below its minimum level.It is proposed that the CST water level be maintained above 14.8 feet in a single tank or above 9.1 feet in each tank.0600((9908060097 990729'PDR ADGCK 05000397.P PDR I ,'+w,I fl'I REQUEST FOR AM<221DMENT TECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANK WATER LEVEL.Page2of3 The Main Condensate system (COND)for WNP-2 is described in FSAR Section 9.2.6.The system is designed to store and provide a condensate supply to the Reactor Core Isolation Cooling (RCIC)system, the HPCS system and the Residual Heat Removal (RHR)system.It also supplies water to various other plant systems such as the condenser hotwell and the control rod drive pumps.The system consists of two storage tanks each with a nominal capacity of 400,000 gallons along with pumps, valves, and necessary piping and instrumentation.
A minimum inventory of 135,000 gallons in the condensate storage tanks is reserved for the RCIC and HPCS pumps.This ensures an immediate availability of a sufficient quantity of condensate for emergency core cooling and reactor shutdown.Although a minimum of 135,000 gallons of water is maintained in the CSTs as a source for the RCIC and HPCS pumps, the supply of water in the suppression pool is the safety related source of water for these pumps.Condensate Storage Tank water level is read in the control room on level indicator COND-LI-40A and COND-LI-40B.
These level indicators get their signals from level transmitters mounted on the tanks.These instruments are used to monitor tank level during the Mode 4 or 5 surveillance above 13.25 feet (elevation 459 feet 9 inches)in a single tank or above 7.6 feet (elevation 454 feet 1 inch)in each tank.Level switches HPCS-LS-1A and HPCS-LS-1B provide for the change in suction (swap over)from the normal CST water source to the containment suppression pool.This level measurement for these switches is made in a standpipe located in the Reactor Building and some distance from the CSTs.The setpoint for these switches is 448 feet 3 inches.The water level between these elevations (the surveillance level and the swap over level)provides the reserve water volume of 135,000 gallons for use of the HPCS and RCIC Systems as stated in FSAR Section 6.3.2.2.1,"High Pressure Core Spray (HPCS)System Design." The Technical Specification Bases, Section 3.5.2,"ECCS-Shutdown," also state that these levels are equivalent to 135,000 gallons in the CST to ensure that the HPCS system could supply makeup water to the reactor pressure vessel.The Reference 1 inspection identified a problem between the calculation of the level needed to support the 135,000 gallons of reserve water and the setpoint calculations for the HPCS level switches.In 1983 a calculation established the minimum required CST levels of 13.25 feet and 7.6 feet.In 1991, engineering personnel developed an improved estimate of when the automatic transfer (swap over)would occur.This setpoint calculation was performed in 1991 and revised in 1996.The calculation considered the pressure drop in the piping from the CSTs, as well as other factors, to more accurately establish the relationship between the water level in the instrument standpipe and the actual level in the CST.In this calculation, under some flow conditions, the level sensed by the instruments located at the instrument standpipe could differ from the CST level.It was shown the suction transfer could occur sooner than previously estimated.
The HPCS pump suction could automatically transfer from the CSTs to the suppression pool prior to the full 135,000 gallons being supplied to the reactor pressure vessel under some flow conditions.
REQUEST FOR AMENDMENT TECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANI<WATER LEVEL~Page 3 of 3 Calculations have now been revised consistent with the corrective action identified in Reference 2.It is proposed that Technical Specification 3.5.2.2 be modified to have the CST water level be maintained above 14.8 feet in a single tank or above 9.1 feet in each tank consistent with the new calculation.
Administrative controls have been put in place to assure that the water level in the CSTs remains above these new levels.This change is consistent with the Reference 3 NRC Administrative Letter that requires action to correct the Technical Specifications for degraded or nonconforming conditions.
Additional information has been attached to this letter to complete the amendment request.Attachment 1 describes an evaluation of the proposed changes in accordance with 10CFR50.92 and concludes they do not result in a significant hazards consideration.
Attachment 2 provides the Environmental Assessment Applicability Review and notes that the proposed change meets the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22.
Therefore, in accordance with 10CFR51.22, an environmental assessment of the change is not required.Attachment 3 provides marked up pages of the Technical Specifications and the associated bases.Attachment 4 consists of the typed Technical Specification pages as proposed by this amendment.
This request for an amendment has been approved by the WNP-2 Plant Operations Committee and reviewed by the Supply System Corporate Nuclear Safety Review Board.In accordance with 10CFR50.91, the state of Washington has been provided a copy of this letter.Should you have any questions or desire additional information regarding this matter, please contact me or PJ Inserra at (509)377-4147.Respectfully, Webring Vice President, Operations Support/PIO Mail Drop PE08 Attachments cc: EW Merschoff-NRC RIV JS Cushing-NRC NRR NRC Senior Resident Inspector-927N DJ Ross-EFSEC PD Robinson-Winston&Strawn DL Williams-BPA/1399
STATE OF WASHINGTON)
))))COUNTY OF BENTON)Subject;Operating License NPF-21 Request for Amendment Technical Specification SR 3.5.2.2 Condensate Storage Tank Water Level I, RL Webring, being duly sworn, subscribe to and say that I am the Vice President, Operations Support/PIO, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein;that I have the full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief that the statements made in it are true.DATE 7>'9 1999 RL Webring Vice President, Operations Support/PIO On this date personally appeared before me RL Webring, 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 1999 Notary lic in and for the STATE OF WASHINGTON Residing at My Commission expires qi%hl.hlkllllgfg
~(>~l'(~C-~r 1 Ql"~~Z-" s~X>,i'"., A 9ll ti 3 eiklll lao' REQUEST FOR AMENDMENT TECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANK WATER LEVEL~Attachment 1 Page 1 of 3 Evaluation of Significant Hazards Considerations Summary of Proposed Change The Washington Public Power Supply System is requesting a revision to Technical Specification Surveillance Requirement (SR)3.5.2.2.This requirement verifies the adequacy of the water supply in the Condensate Storage Tanks (CSTs)which support operation of the High Pressure Core Spray (HPCS)system during Modes 4 and 5.Technical Specification SR 3.5.2.2 requires that CST water level be maintained above 13.25 feet in a single tank or above 7.6 feet in each'tank if the suppression pool level is below its minimum level.This surveillance requirement is only applicable during Modes 4 and 5.The associated Technical Specification Bases, Section 3.5.2,"ECCS-Shutdown," state that these levels are equivalent to 135,000 gallons which provide assurance of adequate core cooling and water makeup for HPCS during shutdown conditions.
The 135,000 gallons must be available in the CSTs prior to the change of the suction (swap over)of HPCS to the containment suppression pool.A refinement in the setpoint calculations was made for the instruments that initiate the change from CST suction to suppression pool suction.The calculations more accurately establish the relationship between the water level in the CST and the instrument standpipe for the swap over instruments that are located some distance away.In the calculations, during some flow conditions, the level sensed by the instruments located at the instrument standpipe could differ from the CST level.Under these conditions, the suction transfer could occur sooner than previously estimated.
As a result, the HPCS pump suction could automatically transfer from the CSTs to the suppression pool prior to the full 135,000 gallons being supplied to the reactor pressure vessel.To alleviate this condition, the maintained level in the CSTs must be higher.It is requested that Technical Specification SR 3.5.2.2 be changed to require the CST water level be maintained above 14.8 feet in a single tank or above 9.1 feet in each tank.This change would make the Technical Specifications consistent with the supporting plant calculations.
ci4&i kkQ 4 Tis (4 REQUEST FOR AMENDMENT TECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANK WATER LEVEL Attachment 1 Page 2 of 3 No Significant Hazards Consideration Determination The Washington Public Power Supply System has evaluated the proposed change to the Technical Specifications using the criteria established in 10CFR50.92(c) and has determined that it does not represent a significant hazards consideration as described below:~The operation of WNP-2 in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
During Modes 4 and 5 HPCS may be required to provide water to the reactor vessel if the water level decreases.
The revised condensate storage tank allowable levels increase the operating margins by providing an increased water inventory.
The previously evaluated accident involving the loss of decay heat cooling inventory will not have an increase in probability because the inventory of water will be increased with the change being proposed.The consequences of any accident involving the loss of decay heat cooling inventory will not change as the consequences are unaffected by the increased water inventory.
Therefore, operation of WNP-2 in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
~The operation of WNP-2 in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change will not create a new or different kind of accident since it only increases the amount of water held in reserve to support reactor vessel inventory loss.The proposed change does not introduce any credible mechanisms for unacceptable radiation release nor does it require physical modification to the plant.The inventory of water in the CSTs will increase to support any loss of water inventory in the reactor vessel during shutdown.The proposed change modifies the monitored values for CST level.The plant has operated well within the existing allowable values.The increased margin provided by the increased level will assure no new or different kinds of accidents result from the proposed change.Therefore, the operation of WNP-2 in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
1 4 jj REQUEST FOR AMENDMENT TECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANI<WATER LEVEL~Attachment 1 Page 3 of 3~The operation of WNP-2 in accordance with the proposed amendment wB1 not involve a significant reduction in the margin of safety.The proposed amendment increases the allowable value for water level in the CSTs.This results in an increase in the inventory of water available for cooling and inventory control during reactor shutdown.This will result in an increase in the margin of safety.Therefore, operation of WNP-2 in accordance with the proposed amendment will not involve a significant reduction in the margin of safety.
REQUEST FOR AMENDMENT TECHNICAL SPECIFICATION SR 3.5.2.2 CONDENSATE STORAGE TANK WATER LEVEL~Attachment 2 Page 1 of 1 Environmental Assessment Applicability Review The Washington Public Power Supply System has evaluated the proposed amendment against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21.
The proposed change meets the criteria for categorical exclusion as provided for in 10CFR51.22(c)(9).
The change request does not pose a significant hazards consideration nor does it involve an increase in the amounts, or a change in the types, of any effluent that may be released off-site.Furthermore, this proposed request does not involve an increase in individual or cumulative occupational exposure.