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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 DISTRIBUTION DEMONST$&TION SYSTEM REGULATO INFORMATION DISTR"BUTION STEM (RIDS)
ACCESSION~'NBR:9207200083 DOC.DATE: 92/07/13 NOTARIZED: YES DOCKET 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) l
SUBJECT:
Application for amend to License NPF-21 revising Tech Specs 3/4.6.5.3 re SBGT a 3/4.7.2 concerning CREFS,in ref to NRC Info Notice 87-032, "Deficiencies in Testing of Nuclear-Grade Activated Charcoal," dtd 870710.
DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR ) ENCL + I
+ericSIZE:Ltr 82-33)
TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(G&e NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 DEAN,W. 2 2 INTERNAL LB . HFBll 1 1 OC/LFMB 1 0 REG FILF 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Wasbtngton Way ~ Rtcbland, Wasbtngton 99/524968 ~ l509) 372-5000 July 13, 1992 G02-92-166 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS 3/4.6.5.3, STANDBY GAS TREATMENT, AND 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEMS
Reference:
NRC Information Notice 87-32, "Deficiencies in the Testing of Nuclear-Grade Activated Charcoal," dated July 10, 1987 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. This proposal requests that the subject Technical Specifications- be changed to incorporate improvements in charcoal testing standards. Additionally, minor clarifications and changes are also requested to:
- 1) upgrade the two Technical Specifications so that they accurately reflect the design and capability of the systems, 2) remove potential ambiguities in the required surveillance testing, and 3) editorially correct the Table of Contents to reflect the contents and page numbering of the WNP-2 Technical Specifications.
In support of this request, proposed changes to the Bases section of the Technical Specifications are also included.
The function of the Standby Gas Treatment (SGT) System is to maintain secondary containment at a negative pressure with respect to the environment following a design basis accident and process gaseous releases to limit the thyroid dose and the whole body dose at the site boundary. The Control Room Emergency Filtration (CREF) System functions to process the Control Room makeup air to provide a filtered environment from which the plant can be operated following an uncontrolled release of radioactivity. Both systems use charcoal to adsorb iodine from the processed stream and thereby limit the dose to the thyroid.
Testing programs are required to ensure that the adsorption capability of the charcoal beds is not degraded below design requirements.
'92Oy PDR 92O7i'3 ADO@+ ogooo PDR
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t REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS t
3/4.6.5.3, STANDBY GAS TREATMENT, AND 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEMS Presently both Specifications require verifying charcoal efficiency by testing once per 18 months, every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation, and whenever activities have been performed in any ventilation zone communicating with the train that might degrade charcoal bed efficiency. Required testing is referenced to Regulatory Guide 1.52, revision 2 which references ANSI N510 - 1975. As noted in the reference, deficiencies have been noted in the testing of nuclear-grade activated charcoal. Further, standards that provide more consistent and accurate results over that required by the WNP-2 Technical Specifications have recently been accepted by the industry and Staff. As a result, the Supply System is proposing that the present method of testing be replaced by ASTM D 3803-1989.
The referenced Information Notice noted implementation problems with ASTM D 3803-1979 and followup activity by the Staff and the industry promoted changes in the 1979 standard. As a result, the 1989 version has been improved over the 1979 version and is proposed for use at WNP-2. The use of this standard with nominal relative humidity and temperature values will provide more accurate and consistent results over the testing method presently required by the WNP-2 Technical Specifications. The nominal temperature and relative humidity values bound the expected conditions at the filters under accident conditions. Use of the new standard will therefore provide greater assurance that .the installed charcoal will perform its intended design safety function.
The other changes to these Technical Specifications are proposed to remove ambiguities in both Specifications and reduce unnecessary operating time on the SGT System units.
The second proposed change reduces the SGT 31-day operability test in Surveil-lance Requirement 4.6.5.3.a from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The purpose of a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test was to ensure that the charcoal was periodically dried out. A periodic drying would remove moisture that might naturally occur due to condensation.
Because the WNP-2 SGT units are continually heated there is no opportunity for moisture to build up in the charcoal beds. The SGT units have thermostatically controlled strip heaters that elevate the charcoal inlet plenum temperature to 90'F. This design feature combined with the naturally low humidity of the area assures that the relative humidity of the charcoal remains below 70/. Hence, the need for a frequent drying out as required by the present Technical Specifica-tions is precluded. Further, 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> provides no additional assurance over 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> that the units are operable. An hour provides adequate time for the unit to reach design operating conditions. Elimination of the unnecessarily long run time preserves the equipment. "Main" heaters are specified in the proposed changes to differentiate from the thermostatically controlled strip heaters.
The third change ensures that the 31-day operability test is done with the heaters "operating" as opposed to "operable." This change removes ambiguity, verifies system operability correctly and has no technical impact on the specifications.
4 ph f
Page Three RE(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS 3/4.6.5.3, STANDBY GAS TREATMENT, AND 3/4.7.2 CONTROL ROON EMERGENCY FILTRATION SYSTEMS The fourth change specifies which flow test of ANSI N510-1980 is to be used to verify flowrate. Both Technical Specifications specify using ANSI N510-1980 to verify flowrate. However there are three measurements of flowrate in the standard, two of which (paragraphs 8.3. 1.6 and 8.3. 1.7) are concerned with verifying flowrate under degraded filter conditions. Because the filter elements have differential pressure alarms to alert the operators of degraded filter conditions and Technical Specification requirements to maintain the pressure drop across HEPA and charcoal banks below specified limits, degraded conditions are not experienced. Hence, the filters are maintained above the conditions anticipated in the standard and there is no need to verify flowrate per these paragraphs (degraded flow conditions). Elimination of these degraded filter tests focuses on exact testing requirements and eliminates superfluous activities that have no contribution toward verifying system operability.
The fifth change clarifies that charcoal removed for disposal need not be tested.
The present Technical Specifications do not differentiate between discarded or "in use" charcoal. The Specifications could be interpreted to include testing both. Under the conditions of proving operability specified in the Technical Specifications, charcoal is discarded before it reaches a state of degradation that would impact the operability of the units. Significant margin exists between the point where charcoal is to be discarded and the point where it has degraded to an extent that would significantly degrade system performance.
Hence, testing discarded charcoal provides no additional knowledge as to the units state of operability. No benefit is derived from testing discarded charcoal.
The sixth change clarifies the heater ratings of the SGT and CREF systems with respect to the manufacturer's ratings. Certified Vendor Information shows that the SGT units are rated at 460 volts and the CREF units are rated at 480 volts.
Again this change has no technical impact but only removes ambiguity from the Specifications.
The last change recognizes the common practice in HVAC design that uses the abbreviation "cfm" whenever "acfm" (actual cfm) is meant. The abbreviation "acfm" is being specified to avoid any possibility that an "scfm" measurement might be required. This specificity is necessary as the design of the CREF units does not provide a method of controlling flow thr ough the CREF units and therefore testing to an exact flow in "scfm" cannot be done. Hence, "acfm" is the appropriate unit. Once more, this change has no technical impact but only removes ambiguity from the Specifications.
The changes requested to the Table of Contents have been added to this request to administratively expedite corrections to the Table of Contents. These changes are strictly editorial and reflect the contents and page numbering (including the impact of the changes on SGT and CREF sections) of the WNP-2 Technical Specifications. No technical impact is represented by these changes. With the approval of the changes to the CREF and SGT specifications these Table of Contents changes will reflect changes to the WNP-2 Technical Specifications that have had appropriate no significant hazards evaluations and environmental assessments categorical exclusion statements submitted. As such, further discussion of these changes with respect to no significant hazards and environmental assessment evaluations is not necessary.
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Page Four, RE(VEST FOR ANENDNENT TO TECHNICAL SPECIFICATIONS 3/4.6.5.3, STANDBY GAS TREATMENT, AND 3/4.7.2 CONTROL ROON EMERGENCY FILTRATION SYSTEMS In summary the following changes to the CREF and SGT specifications are provided for clarification (quotation marks denote the proposed changes):
Surveillance 4.6.5.3.a "main" heaters "operating" Surveillance 4.6.5.3.b.3 verifying flow rate .... in accordance with ANSI N510-1980 "section 8.3. 1(1) through 8.3. 1(5)"
Surveillances 4.6.5.3.b.2 &.3 adding a footnote stating that "Carbon removed for disposal need not be sampled or tested."
Surveillance 4.6.5.3.d.4 heaters dissipate "the equivalent of" 20.7 + 2. 1 kW "at 460 volts"......
Surveillance 4.7.2.b heaters "operating."
Surveillance 4.7.2.c. 1 "using" replaces "and uses" Surveillances 4.7.2.c. 1, 3, 4.7.2.e. 1, 2, 4.7.2.f and g "acfm" replaces cfm Surveillance 4.7.2.c.3 verifying flow rate .... in accordance with ANSI N510-1980 "section 8.3.1(1) through 8.3.1(5)"
Surveillances 4.7.2.c.2 & .3 adding a footnote stating that "Carbon removed for disposal need not be sampled or tested."
Surveillance 4.7.2.e.3 heaters dissipate "the equivalent of" 5.0 +
0.5 kW "at 480 volts"......
These changes provide clarification so that ambiguity is removed from the Technical Specifications and precise system operability can be verified. As such, these changes represent enhancements to the Technical Specifications.
The Supply System has evaluated the remaining two proposed changes (the new standard and the reduction in SGT surveillance run time from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) per 10CFR 50.92 and determined that they do not represent a significant hazard.
The change to a more consistent and accurate method of charcoal testing provides more assurance of system operability for the SGT and CREF systems. Hence, plant safety is enhanced by this change. The reduction in SGT run time to prove operability removes unnecessary run time that is redundant to the SGT design.
As stated above, the additional changes remove ambiguities and more accurately reflect system capability and design. In summary, incorporating these changes does not represent a significant hazard because it does not:
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REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS STANDBY GAS TREATMENT, AND 3/4.7.2 3/4.6.5.3, CONTROL ROOM EMERGENCY FILTRATION SYSTEMS Involve a significant increase in the probability or consequences of an accident previously evaluated because the proposed method of testing will provide more consistent and accurate measurement of charcoal adsorption capability, over that presently required by the WNP-2 Technical Specifica-tions. The SGT and CREF systems are mitigating systems that cannot, of themselves, initiate an accident. Because the proposed test standard will provide greater assurance of charcoal operability this change enhances the mitigation of an accident. As a result, the proposed change to the new standard has no impact on the probability or consequences of a previously evaluated accident.
The change in SGT surveillance operability run time to I hour from 10 hours does not involve a significant increase in the probability or consequences of an accident previously evaluated because the intent of the surveillance (assurance that the charcoal beds are not degraded due to moisture buildup) is satisfied by system design. The thermostatically controlled heaters assure that excessive moisture adsorption will not occur. Hence, a "drying out" run of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is redundant to the system design. The consequences of a previously evaluated accident are therefore not increased because charcoal efficiency is maintained by the system design.
Because the remaining changes have no technical impact on the SGT or CREF systems but remove ambiguity from the surveillance testing and system design capabilities they also do not represent a significant increase in the probability or consequences of a previously evaluated accident. As stated above, the systems are mitigative and do not contribute to the initiation of an accident. Further, the mitigative capabilities are not changed as a result of the clarifications. Hence these changes do not represent a significant increase in the probability or consequences of a previously evaluated accident.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because operation and testing of the systems remain the same. No new modes of operation result due to this change.
Therefore, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Involve a significant reduction in a margin of safety because the margin of safety presently provided by the current Technical Specifications is enhanced by a more consistent and accurate testing method. Therefore, this change does not involve a reduction in a margin of safety.
Reducing the SGT operability run time merely removes a requirement imposed on the units that is already accomplished by SGT design. Hence, reduction from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to I hour has no effect on the function of the system, by design the carbon will remain free of excessive moisture degradation.
Therefore, this change also does not involve a reduction in a margin of safety.
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RE(VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS 3/4.6.5.3, STANDBY GAS TREATMENT, AND 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEMS The remaining changes remove ambiguity and clarify the design requirements of the systems. As such, these changes ensure that the system will continually be evaluated to the same requirements. Therefore the possibility of misapplying the Technical Specifications is reduced.
Accordingly, these additional changes do not represent an impact to a margin of safety.
As, discussed above, the Supply System considers that these changes do not involve a significant hazards consideration. Nor, considering the enhancement to charcoal testing consistency and accuracy, do these changes involve 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, the proposed changes meet 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 these changes is not required.
This Technical Specification change request has been. reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.
Sincerely, G. C. S rensen, Manager Regulatory Programs (Mail Drop 280)
PLP/bk Attachments cc: RG Waldo - EFSEC JB Martin - NRC RV NS Reynolds - Winston L Strawn NRC Site Inspector - 901A R Assa - NRC DL Williams - BPA/399
STATE OF WASHINGTON )
Subject:
REQUEST FOR AMENDMENTTO
) TECH SPECS 3/4.6.5.3 AND COUNTY OF BENTON ) 3/4.7.2 I, G. C. SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.
o~vs , 1992 G. C. Soreg en, Manager Regulatory Programs On this date personally, appeared before me G. C. SORENSEN, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this l0 day of 1992.
Notary Public in and for the STATE OF WASHINGTON My Commission Expires Februa 2 1
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