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| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONS'roN SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9204200088 DOC.DATE: 92/04/10 NOTARIZED: | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONS 'roN SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| YES DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C. | | ACCESSION NBR:9204200088 DOC.DATE: 92/04/10 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) |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for amend to License NPF-21,revising TSs 3.4.3.1,3.4.3.2,4.4.3.2.1.b,B 3/4.4.3.1&B 3/4.4.3.2,per Generic Ltr 88-01 re NRC position on IGSCC in austenitic stainless steel piping.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR t ENCL j SIZE: l+8 TITLE: OR Submittal: | | Application for amend to License NPF-21,revising TSs 3.4.3.1,3.4.3.2,4.4.3.2.1.b,B 3/4.4.3.1 & B 3/4.4.3.2,per Generic Ltr 88-01 re NRC position on IGSCC in austenitic D stainless steel piping. |
| General Distribution NOTES: D RECIPIENT ID CODE/NAME PD5 LA ENG, P.L.INTERNAL ACRS NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 6 6 1 1 1 1 1 1 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E 0/M@5 EG FILE 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS: | | DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR t ENCL j SIZE: l +8 TITLE: OR Submittal: General Distribution NOTES: |
| D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISPS FOR DOCUMENTS YOU DON'T NEED!TOTAL'NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Bop 968~3000George Washtngton Way~Rtcbland, Wasbfngton 99352-0968
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD5 LA 1 1 PD5 PD 1 1 ENG, P. L. 2 2 D INTERNAL ACRS 6 6 NRR/DET/ECMB 7D 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 0 /M@5 1 0 OGC/HDS1 1 0 EG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC D |
| ~(509)372-5000 April 10, 1992 G02-92-085 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: | | D D |
| | 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 LISPS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL 'NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bop 968 ~ 3000George Washtngton Way ~ Rtcbland, Wasbfngton 99352-0968 ~ (509)372-5000 April 10, 1992 G02-92-085 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01 | | WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01 |
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| ==References:== | | ==References:== |
| | : 1) Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping". |
| | : 2) Letter, G02-89-123, GC Sorensen (SS) to NRC, "Supply System Response to Generic Letter 88-01, Request for Additional Information", dated July 20, 1989 |
| | : 3) Letter, G02-88-164, GC Sorensen (SS) to NRC, "Response to Generic Letter 88-01", dated July 26, 1988 |
| | : 4) Letter, PL Eng (NRC) to GC Sorensen (SS), "Response to GL 88-01, Intergranular Stress Corrosion In Piping (TAC No. 69161)", dated December 28, 1990 |
| | : 5) Letter, G02-92-004, GC Sorensen (SS) to NRC, "Response to NRC SER on Generic Letter 88-01 (TAC No. 69161)", dated January 8, 1992 |
| | : 6) Generic Letter 88-01, Supplement 1, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" 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. Generic Letter 88-01 provides the Staff position concerning implementation of an Inservice Inspection ( ISI) Program for austenitic stainless steel piping susceptible to intergranular stress corrosion cracking (IGSCC). Supplement 1 to the Generic Letter,,issued February 4, 1992, provided some relief"concerning leak"detection instrumentation and surveillances. This |
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| 1)Generic Letter 88-01,"NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping".2)Letter, G02-89-123, GC Sorensen (SS)to NRC,"Supply System Response to Generic Letter 88-01, Request for Additional Information", dated July 20, 1989 3)Letter, G02-88-164, GC Sorensen (SS)to NRC,"Response to Generic Letter 88-01", dated July 26, 1988 4)Letter, PL Eng (NRC)to GC Sorensen (SS),"Response to GL 88-01, Intergranular Stress Corrosion In Piping (TAC No.69161)", dated December 28, 1990 5)Letter, G02-92-004, GC Sorensen (SS)to NRC,"Response to NRC SER on Generic Letter 88-01 (TAC No.69161)", dated January 8, 1992 6)Generic Letter 88-01, Supplement 1,"NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" 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.
| | 'age FOR AMENDMENT TO TECHNICAL SPECIFICATIONS Two'E(UEST IN ACCORDANCE WITH GENERIC LETTER 88-01 letter serves to request those changes to the Technical Specifications to assure the sections related to leak detection are in conformance with the Staff position. As discussed in Reference 5, the Supply System will address changes to the Technical Specifications concerning the ISI Program requirements after the refueling outage scheduled for the Spring of 1992. Changes to the following Technical Specifications are being requested: |
| Generic Letter 88-01 provides the Staff position concerning implementation of an Inservice Inspection (ISI)Program for austenitic stainless steel piping susceptible to intergranular stress corrosion cracking (IGSCC).Supplement 1 to the Generic Letter,,issued February 4, 1992, provided some relief"concerning leak"detection instrumentation and surveillances.
| | 3.4.3.1 Leakage Detection Systems, ACTION Statement 3.4.3.2 Operational Leakage, LCO and ACTION Statement 4.4.3.2.1.b Operational Leakage, Surveillance Requirements B 3/4.4.3.1 Leakage Detection Systems B 3/4.4.3.2 Operational Leakage The changes to the ACTION Statement and Bases for Leakage Detection Systems assure the capability to quantitatively measure UNIDENTIFIED LEAKAGE is maintained as required by Generic Letter 88-01 and its Supplement 1. This includes the addition of a shutdown requirement in the event that containment sump monitoring instrumentation is inoperable for more than 30 days. The changes to the LCO, ACTION Statement, Surveillance Requirement and the Bases for Operational Leakage, assure that the UNIDENTIFIED LEAKAGE limits are in accordance with those in GL 88-01 or NRC approved alternative measures. The LCO has been changed to limit UNIDENTIFIED LEAKAGE to 2 gpm increase within 24 hours rather than a 2 gpm increase in 4 hours. The Surveillance Requirement for monitoring the primary containment sump flow rate has been changed to require the measurement at least once per shift, not to exceed 12 hours, rather than once per 12 hours. |
| This ,9204200088 920410 ,PDR'f,ADOCK 05000397 P'PDR
| | The Supply System has reviewed the changes per 10 CFR 50.92 and provides the following in support of a finding for no significant hazards consideration. |
| 'age Two'E(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01 letter serves to request those changes to the Technical Specifications to assure the sections related to leak detection are in conformance with the Staff position.As discussed in Reference 5, the Supply System will address changes to the Technical Specifications concerning the ISI Program requirements after the refueling outage scheduled for the Spring of 1992.Changes to the following Technical Specifications are being requested: | | These changes are being made in accordance with the generic letter issued by the NRC and represent additional restrictions on the operation of WNP-2. |
| 3.4.3.1 3.4.3.2 4.4.3.2.1.b B 3/4.4.3.1 B 3/4.4.3.2 Leakage Detection Systems, ACTION Statement Operational Leakage, LCO and ACTION Statement Operational Leakage, Surveillance Requirements Leakage Detection Systems Operational Leakage The changes to the ACTION Statement and Bases for Leakage Detection Systems assure the capability to quantitatively measure UNIDENTIFIED LEAKAGE is maintained as required by Generic Letter 88-01 and its Supplement 1.This includes the addition of a shutdown requirement in the event that containment sump monitoring instrumentation is inoperable for more than 30 days.The changes to the LCO, ACTION Statement, Surveillance Requirement and the Bases for Operational Leakage, assure that the UNIDENTIFIED LEAKAGE limits are in accordance with those in GL 88-01 or NRC approved alternative measures.The LCO has been changed to limit UNIDENTIFIED LEAKAGE to 2 gpm increase within 24 hours rather than a 2 gpm increase in 4 hours.The Surveillance Requirement for monitoring the primary containment sump flow rate has been changed to require the measurement at least once per shift, not to exceed 12 hours, rather than once per 12 hours.The Supply System has reviewed the changes per 10 CFR 50.92 and provides the following in support of a finding for no significant hazards consideration. | | : 1) The change to the operational leakage program does not involve a significant increase in the probability of an accident previously evaluated because leakage monitoring is not assumed as the initiator of any analyzed event. In addition, the change does not involve a significant increase in the consequences of an accident as the additional shutdown requirement and the increased surveillance requirements for leak detection may facilitate earlier detection of a failure associated with IGSCC. |
| These changes are being made in accordance with the generic letter issued by the NRC and represent additional restrictions on the operation of WNP-2.1)The change to the operational leakage program does not involve a significant increase in the probability of an accident previously evaluated because leakage monitoring is not assumed as the initiator of any analyzed event.In addition, the change does not involve a significant increase in the consequences of an accident as the additional shutdown requirement and the increased surveillance requirements for leak detection may facilitate earlier detection of a failure associated with IGSCC.2)The changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes do not introduce any new mode of plant operation or require any physical modification to the plant. | | : 2) The changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes do not introduce any new mode of plant operation or require any physical modification to the plant. |
| Page Thr'ee RE(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01 3)There is no reduction in a margin of safety due to these changes because the additional shutdown requirement and the additional surveillances have been established to assure the earliest possible detection of problems with or the need of repair or replacement of piping that may be susceptible to failure due to IGSCC.These changes clearly enhance safety and increase margins, by the implementation of the more restrictive LCO, ACTIONS and Surveillance Requirements.
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| As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite.Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR 51.22(c)(9) and therefore, per 10CFR 51.22(b), an environmental assessment of the change is not required.This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC)and the Supply System Corporate Nuclear Safety Review Board (CNSRB).In accordance with 10CFR 50.91, the State of Washington has been provided a copy of this letter.Sincerely, g,~~~G.C.Sorensen, Manager Regulatory Programs (Hail Drop 280)MGE/bI<Attachments CC: JB Martin-NRC RV NS Reynolds-Winston 5 Strawn WM Dean-NRC DL Williams-BPA/399 NRC Site Inspector-901A RG Waldo-EFSEC
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| STATE OF WASHINGTON)
| | Page Thr'ee RE(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01 |
| )COUNTY OF BENTON) | | : 3) There is no reduction in a margin of safety due to these changes because the additional shutdown requirement and the additional surveillances have been established to assure the earliest possible detection of problems with or the need of repair or replacement of piping that may be susceptible to failure due to IGSCC. These changes clearly enhance safety and increase margins, by the implementation of the more restrictive LCO, ACTIONS and Surveillance Requirements. |
| | As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR 51.22(c)(9) and therefore, per 10CFR 51.22(b), an environmental assessment of the change is not required. |
| | This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with 10CFR 50.91, the State of Washington has been provided a copy of this letter. |
| | Sincerely, G. C. |
| | g,~~~ |
| | Sorensen, Manager Regulatory Programs (Hail Drop 280) |
| | MGE/bI< |
| | Attachments CC: JB Martin - NRC RV NS Reynolds - Winston 5 Strawn WM Dean - NRC DL Williams - BPA/399 NRC Site Inspector - 901A RG Waldo - EFSEC |
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| | STATE OF WASHINGTON) |
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| ==Subject:== | | ==Subject:== |
| Re uest for Amend to Tech.S ecs.In Accordance with GL 88-01 I.A.G.HOSLER, 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 the full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.DATE Ape..-~1992 A.G.Hosier, Manager WNP-2 Licensing On this date personally appeared before me A.G.HOSLER, 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. | | Re uest for Amend to Tech. S ecs. |
| GIVEN under my hand and seal this~today of 1992.No ar Public in and fo the STATE OF WASHINGTON Residing at Kennewick Washin ton Hy Commission Expires A ril 28 1994 I rw'Wpplelgr~ll1ii%i}} | | ) In Accordance with GL 88-01 COUNTY OF BENTON ) |
| | I. A. G. HOSLER, 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 the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true. |
| | DATE Ape..- ~ 1992 A. G. Hosier, Manager WNP-2 Licensing On this date personally appeared before me A. G. HOSLER, 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 ~today of 1992. |
| | No ar Public in and fo the STATE OF WASHINGTON Residing at Kennewick Washin ton Hy Commission Expires A ril 28 1994 |
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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
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ACCELERATED DISTRIBUTION DEMONS 'roN SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9204200088 DOC.DATE: 92/04/10 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)
SUBJECT:
Application for amend to License NPF-21,revising TSs 3.4.3.1,3.4.3.2,4.4.3.2.1.b,B 3/4.4.3.1 & B 3/4.4.3.2,per Generic Ltr 88-01 re NRC position on IGSCC in austenitic D stainless steel piping.
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR t ENCL j SIZE: l +8 TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD5 LA 1 1 PD5 PD 1 1 ENG, P. L. 2 2 D INTERNAL ACRS 6 6 NRR/DET/ECMB 7D 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 0 /M@5 1 0 OGC/HDS1 1 0 EG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC D
D D
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 LISPS FOR DOCUMENTS YOU DON'T NEED!
TOTAL 'NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bop 968 ~ 3000George Washtngton Way ~ Rtcbland, Wasbfngton 99352-0968 ~ (509)372-5000 April 10, 1992 G02-92-085 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01
References:
- 1) Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping".
- 2) Letter, G02-89-123, GC Sorensen (SS) to NRC, "Supply System Response to Generic Letter 88-01, Request for Additional Information", dated July 20, 1989
- 3) Letter, G02-88-164, GC Sorensen (SS) to NRC, "Response to Generic Letter 88-01", dated July 26, 1988
- 4) Letter, PL Eng (NRC) to GC Sorensen (SS), "Response to GL 88-01, Intergranular Stress Corrosion In Piping (TAC No. 69161)", dated December 28, 1990
- 5) Letter, G02-92-004, GC Sorensen (SS) to NRC, "Response to NRC SER on Generic Letter 88-01 (TAC No. 69161)", dated January 8, 1992
- 6) Generic Letter 88-01, Supplement 1, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" 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. Generic Letter 88-01 provides the Staff position concerning implementation of an Inservice Inspection ( ISI) Program for austenitic stainless steel piping susceptible to intergranular stress corrosion cracking (IGSCC). Supplement 1 to the Generic Letter,,issued February 4, 1992, provided some relief"concerning leak"detection instrumentation and surveillances. This
,9204200088 920410
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05000397 P PDR
'age FOR AMENDMENT TO TECHNICAL SPECIFICATIONS Two'E(UEST IN ACCORDANCE WITH GENERIC LETTER 88-01 letter serves to request those changes to the Technical Specifications to assure the sections related to leak detection are in conformance with the Staff position. As discussed in Reference 5, the Supply System will address changes to the Technical Specifications concerning the ISI Program requirements after the refueling outage scheduled for the Spring of 1992. Changes to the following Technical Specifications are being requested:
3.4.3.1 Leakage Detection Systems, ACTION Statement 3.4.3.2 Operational Leakage, LCO and ACTION Statement 4.4.3.2.1.b Operational Leakage, Surveillance Requirements B 3/4.4.3.1 Leakage Detection Systems B 3/4.4.3.2 Operational Leakage The changes to the ACTION Statement and Bases for Leakage Detection Systems assure the capability to quantitatively measure UNIDENTIFIED LEAKAGE is maintained as required by Generic Letter 88-01 and its Supplement 1. This includes the addition of a shutdown requirement in the event that containment sump monitoring instrumentation is inoperable for more than 30 days. The changes to the LCO, ACTION Statement, Surveillance Requirement and the Bases for Operational Leakage, assure that the UNIDENTIFIED LEAKAGE limits are in accordance with those in GL 88-01 or NRC approved alternative measures. The LCO has been changed to limit UNIDENTIFIED LEAKAGE to 2 gpm increase within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than a 2 gpm increase in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The Surveillance Requirement for monitoring the primary containment sump flow rate has been changed to require the measurement at least once per shift, not to exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, rather than once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The Supply System has reviewed the changes per 10 CFR 50.92 and provides the following in support of a finding for no significant hazards consideration.
These changes are being made in accordance with the generic letter issued by the NRC and represent additional restrictions on the operation of WNP-2.
- 1) The change to the operational leakage program does not involve a significant increase in the probability of an accident previously evaluated because leakage monitoring is not assumed as the initiator of any analyzed event. In addition, the change does not involve a significant increase in the consequences of an accident as the additional shutdown requirement and the increased surveillance requirements for leak detection may facilitate earlier detection of a failure associated with IGSCC.
- 2) The changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes do not introduce any new mode of plant operation or require any physical modification to the plant.
Page Thr'ee RE(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS IN ACCORDANCE WITH GENERIC LETTER 88-01
- 3) There is no reduction in a margin of safety due to these changes because the additional shutdown requirement and the additional surveillances have been established to assure the earliest possible detection of problems with or the need of repair or replacement of piping that may be susceptible to failure due to IGSCC. These changes clearly enhance safety and increase margins, by the implementation of the more restrictive LCO, ACTIONS and Surveillance Requirements.
As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR 51.22(c)(9) and therefore, per 10CFR 51.22(b), an environmental assessment of the change is not required.
This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with 10CFR 50.91, the State of Washington has been provided a copy of this letter.
Sincerely, G. C.
g,~~~
Sorensen, Manager Regulatory Programs (Hail Drop 280)
MGE/bI<
Attachments CC: JB Martin - NRC RV NS Reynolds - Winston 5 Strawn WM Dean - NRC DL Williams - BPA/399 NRC Site Inspector - 901A RG Waldo - EFSEC
STATE OF WASHINGTON)
Subject:
Re uest for Amend to Tech. S ecs.
) In Accordance with GL 88-01 COUNTY OF BENTON )
I. A. G. HOSLER, 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 the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.
DATE Ape..- ~ 1992 A. G. Hosier, Manager WNP-2 Licensing On this date personally appeared before me A. G. HOSLER, 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 ~today of 1992.
No ar Public in and fo the STATE OF WASHINGTON Residing at Kennewick Washin ton Hy Commission Expires A ril 28 1994
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