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| | issue date = 06/06/1995 | | | issue date = 06/06/1995 |
| | title = 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 | | | title = 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 |
| | author name = PARRISH J V | | | author name = Parrish J |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 7 | | | page count = 7 |
| | | project = |
| | | stage = Request |
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| =Text= | | =Text= |
| {{#Wiki_filter:RIORITY 1-CCELERATED RIDS PROCESSING) | | {{#Wiki_filter:RIORITY CCELERATED RIDS PROCESSING) 1-REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSXON NBR:9506140332 DOC.DATE: 95/06/06 NOTARIZED: | | ACCESSXON NBR:9506140332 DOC.DATE: 95/06/06 NOTARIZED: YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| YES FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION PARRISH,J.V. | |
| Washington Public Power Supply System RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET g 05000397 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 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 determininq reactor core operating limits for reload licensing applications,consistent w/GL 88-16.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR J ENCL J SIZE: TITLE: OR Submittal: | | 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 determininq reactor core operating limits for reload licensing applications,consistent w/GL 88-16. |
| General Distribution NOTES: RECIPIENT ID CODE/NAME PD4-2 LA CLIFFORD,J XNTERNAL: ACRS NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT
| | DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL J SIZE: |
| .EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 6 6 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD4-2 PD IUE CEN g 01 DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 Y'OTE TO ALL"RIDS" RECIPI EY'TS: PLEASE HELP US TO REDUCE'O',KSTE!COYTACT'I'IIE DOC!:ifEYTCOYTROL DESK, ROOb,f Pl-37 (EXT.04-UOS3)TO FLDfliATE YOL'R NAifL FROif DISTRIBU'I'IOY, LISTS I:OR DOC!:MEY,'I'S 5'Of: DOY,"I'I:I'.D!
| | NOTES: |
| TOTAL NUMBER OF COPXES REQUIRED: LTTR 18 ENCL 17 | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CLIFFORD,J 1 1 XNTERNAL: ACRS 6 6 IUE CEN g 01 1 1 NRR/DE/EMCB 1 1 DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 |
| @~i WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO.Box 968~3000 George Washington Way~Richland, Washington 99352-0968 | | . EXTERNAL: NOAC NRC PDR 1 1 Y'OTE TO ALL"RIDS" RECIPI EY'TS: |
| ~(509)372-5000 June 6, 1995 G02-95-104 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: | | PLEASE HELP US TO REDUCE 'O',KSTE! COYTACT'I'IIE DOC!:ifEYTCOYTROL DESK, ROOb,f Pl-37 (EXT. 04-UOS3 ) TO FLDfliATEYOL'R NAifLFROif DISTRIBU'I'IOY, LISTS I:OR DOC!:MEY,'I'S 5'Of: DOY,"I'I:I'.D! |
| | TOTAL NUMBER OF COPXES REQUIRED: LTTR 18 ENCL 17 |
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| | @~i WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 June 6, 1995 G02-95-104 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: | | WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENTTO TECHNICAL SPECIFICATIONS: |
| REVISION TO SECTION 6.9.3.2-IMPLEMENTATION OF GENERIC LETTER 88-16 | | REVISION TO SECTION 6.9.3.2 - IMPLEMENTATION OF GENERIC LETTER 88-16 |
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| ==References:== | | ==References:== |
| | : 1) Letter dated October 4, 1988, DM Crutchfield (NRC) to All Power Reactor Licensees and Applicants, "Removal of Cycle-Specific Parameter Limits From Technical Specifications (Generic Letter 88-16)" |
| | : 2) Letter GI2-91-116, dated June 4, 1991, PL Eng (NRC) to GC Sorenson (SS), Issuance of Amendment No. 94 To Facility Operating License No. |
| | NPF-21 For the WPPSS Nuclear Project No. 2 (TAC No. 77311)" |
| | : 3) Letter GI2-92-176, dated June 29, 1992, RR Assa (NRC) to GC Sorenson (SS), "Issuance of Amendment For The Washington Public Power Supply System Nuclear Project No. 2 (TAC No. M82919)" |
| | : 4) Letter GI2-92-262, dated October 23, 1992, JW Clifford (NRC) to GC Soren son (SS), "Evaluation of Topical Report WPPSS-FTS-127, |
| | 'Qualification of Core Physics for BWR Design and Analysis'TAC No. |
| | M76783)" |
| | : 5) Letter GI2-93-255, dated October 25, 1993, JW Clifford (NRC) to JV Parrish (SS), "BWR Transient Analysis Model (TAC Nos. M77048 and M81723)" |
| | : 6) Letter GI2-94-308, dated October 12, 1994, JW Clifford (NRC) to JV Parrish (SS), "Approval of Topical Report FTS-131, 'Applications Topical Report For BWR Design and Analysis', For the Washington Public Power Supply System Nuclear Project No. 2 (TAC M81723)" |
| | ,oK 950b140332 950b0b PDR ADOCK 05000397 PDR |
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| 1)Letter dated October 4, 1988, DM Crutchfield (NRC)to All Power Reactor Licensees and Applicants,"Removal of Cycle-Specific Parameter Limits From Technical Specifications (Generic Letter 88-16)" 2)Letter GI2-91-116, dated June 4, 1991, PL Eng (NRC)to GC Sorenson (SS), Issuance of Amendment No.94 To Facility Operating License No.NPF-21 For the WPPSS Nuclear Project No.2 (TAC No.77311)" 3)Letter GI2-92-176, dated June 29, 1992, RR Assa (NRC)to GC Sorenson (SS),"Issuance of Amendment For The Washington Public Power Supply System Nuclear Project No.2 (TAC No.M82919)" 4)Letter GI2-92-262, dated October 23, 1992, JW Clifford (NRC)to GC Soren son (SS),"Evaluation of Topical Report WPPSS-FTS-127,'Qualification of Core Physics for BWR Design and Analysis'TAC No.M76783)" 5)Letter GI2-93-255, dated October 25, 1993, JW Clifford (NRC)to JV Parrish (SS),"BWR Transient Analysis Model (TAC Nos.M77048 and M81723)" 6)950b140332 950b0b PDR ADOCK 05000397 PDR Letter GI2-94-308, dated October 12, 1994, JW Clifford (NRC)to JV Parrish (SS),"Approval of Topical Report FTS-131,'Applications Topical Report For BWR Design and Analysis', For the Washington Public Power Supply System Nuclear Project No.2 (TAC M81723)" ,oK v.~
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| Page 2 REQUEST FOR AMENDME<NT TO TECHNICAL SPE<CIFICATIONS: | | Page 2 REQUEST FOR AMENDME<NT TO TECHNICAL SPE<CIFICATIONS: |
| REVISION TO SE<CTION 6.9.3.2-IMPLEMI<.NTATION OF GENERIC LETTER 88-16 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. | | REVISION TO SE<CTION 6.9.3.2 - IMPLEMI<.NTATIONOF GENERIC LETTER 88-16 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. |
| The proposed amendment, as shown in Attachment 1, would modify Section 6.9.3.2 of the WNP-2 Technical Specifications by adding reference to three topical reports describing analytical methods that may be used in determining reactor core operating limits for reload licensing applications. | | The proposed amendment, as shown in Attachment 1, would modify Section 6.9.3.2 of the WNP-2 Technical Specifications by adding reference to three topical reports describing analytical methods that may be used in determining reactor core operating limits for reload licensing applications. This change is consistent with Reference 1, and similar amendments have been approved by References 2 and 3. The topical reports themselves have been previously approved by NRC by References 4, 5, and 6 as being acceptable for use at WNP-2 in reload licensing applications. |
| This change is consistent with Reference 1, and similar amendments have been approved by References 2 and 3.The topical reports themselves have been previously approved by NRC by References 4, 5, and 6 as being acceptable for use at WNP-2 in reload licensing applications. | | As discussed in Attachment 2, the Supply System has concluded that the proposed change to the WNP-2 Technical Specifications does not involve a significant hazards consideration. In addition, the proposed changes do not create the potential for a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, nor do the changes involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly,'he proposed change meets the eligibility criteria for a categorical exclusion as set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b), |
| As discussed in Attachment 2, the Supply System has concluded that the proposed change to the WNP-2 Technical Specifications does not involve a significant hazards consideration. | | an environmental assessment of the change is not required. |
| In addition, the proposed changes do not create the potential for a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, nor do the changes involve a significant increase in individual or cumulative occupational radiation exposure.Accordingly,'he proposed change meets the eligibility criteria for a categorical exclusion as set forth in 10 CFR 51.22(c)(9). | | This Technical Specification amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. |
| Therefore, in accordance with 10 CFR 51.22(b), an environmental assessment of the change is not required.This Technical Specification amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.The State of Washington has been provided a copy of this letter in accordance with 10 CFR 50.91.Should you have any questions or desire additional information regarding this matter, please call me or Mr.D.A.Swank at (509)377-4563, J.V.Parrish (Mail Drop 1023)Vice-President, Nuclear Operations CJF/ml Attachments CC: LJ Callan-NRC RIV KE Perkins Jr.-NRC RIV, Walnut Creek Field Office NS Reynolds-Winston&, Strawn JW Clifford-NRC FS Adair-EFSEC DL Williams-BPA/399 NRC Resident Inspector-927N | | The State of Washington has been provided a copy of this letter in accordance with 10 CFR 50.91. |
| )pi>$lewi IC~4.~-~1<<) | | Should you have any questions or desire additional information regarding this matter, please call me or Mr. D. A. Swank at (509) 377-4563, J. V. Parrish (Mail Drop 1023) |
| STATE OF WASHINGTON | | Vice-President, Nuclear Operations CJF/ml Attachments CC: LJ Callan - NRC RIV KE Perkins Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston &, Strawn JW Clifford - NRC FS Adair - EFSEC DL Williams - BPA/399 NRC Resident Inspector - 927N |
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| ==Subject:== | | ==Subject:== |
| Request for Amendment to TS to add references to Section 6.9.3.2 I, J.V.Parrish, being duly sworn, subscribe to and say that I am the Vice-President of Nuclear Operations 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 , 1995 J.V arrish, Vice-President for Nuclear Operations On this day personally appeared before me J.V.PARRISH, 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. | | Request for Amendment to TS to add references to Section 6.9.3.2 |
| GIVEN under my hand and seal this ay f 1995...:., Notary Pu in a f9 th STATE OF WASHINGTON Residing at My Commission Expires 0 f I'4 I" f f;,I, It I f fS N}} | | ) |
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| | COUNTY OF BENTON ) |
| | I, J.V. Parrish, being duly sworn, subscribe to and say that I am the Vice-President of Nuclear Operations 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 , 1995 J. V arrish, Vice-President for Nuclear Operations On this day personally appeared before me J.V. PARRISH, 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 ay f 1995 ...:., |
| | Notary Pu in a f9 th STATE OF WASHINGTON Residing at My Commission Expires |
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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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Text
RIORITY CCELERATED RIDS PROCESSING) 1-REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSXON NBR:9506140332 DOC.DATE: 95/06/06 NOTARIZED: YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
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 determininq reactor core operating limits for reload licensing applications,consistent w/GL 88-16.
DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL J SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CLIFFORD,J 1 1 XNTERNAL: ACRS 6 6 IUE CEN g 01 1 1 NRR/DE/EMCB 1 1 DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0
. EXTERNAL: NOAC NRC PDR 1 1 Y'OTE TO ALL"RIDS" RECIPI EY'TS:
PLEASE HELP US TO REDUCE 'O',KSTE! COYTACT'I'IIE DOC!:ifEYTCOYTROL DESK, ROOb,f Pl-37 (EXT. 04-UOS3 ) TO FLDfliATEYOL'R NAifLFROif DISTRIBU'I'IOY, LISTS I:OR DOC!:MEY,'I'S 5'Of: DOY,"I'I:I'.D!
TOTAL NUMBER OF COPXES REQUIRED: LTTR 18 ENCL 17
@~i WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 June 6, 1995 G02-95-104 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 AMENDMENTTO TECHNICAL SPECIFICATIONS:
REVISION TO SECTION 6.9.3.2 - IMPLEMENTATION OF GENERIC LETTER 88-16
References:
- 1) Letter dated October 4, 1988, DM Crutchfield (NRC) to All Power Reactor Licensees and Applicants, "Removal of Cycle-Specific Parameter Limits From Technical Specifications (Generic Letter 88-16)"
- 2) Letter GI2-91-116, dated June 4, 1991, PL Eng (NRC) to GC Sorenson (SS), Issuance of Amendment No. 94 To Facility Operating License No.
NPF-21 For the WPPSS Nuclear Project No. 2 (TAC No. 77311)"
- 3) Letter GI2-92-176, dated June 29, 1992, RR Assa (NRC) to GC Sorenson (SS), "Issuance of Amendment For The Washington Public Power Supply System Nuclear Project No. 2 (TAC No. M82919)"
- 4) Letter GI2-92-262, dated October 23, 1992, JW Clifford (NRC) to GC Soren son (SS), "Evaluation of Topical Report WPPSS-FTS-127,
'Qualification of Core Physics for BWR Design and Analysis'TAC No.
M76783)"
- 5) Letter GI2-93-255, dated October 25, 1993, JW Clifford (NRC) to JV Parrish (SS), "BWR Transient Analysis Model (TAC Nos. M77048 and M81723)"
- 6) Letter GI2-94-308, dated October 12, 1994, JW Clifford (NRC) to JV Parrish (SS), "Approval of Topical Report FTS-131, 'Applications Topical Report For BWR Design and Analysis', For the Washington Public Power Supply System Nuclear Project No. 2 (TAC M81723)"
,oK 950b140332 950b0b PDR ADOCK 05000397 PDR
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Page 2 REQUEST FOR AMENDME<NT TO TECHNICAL SPE<CIFICATIONS:
REVISION TO SE<CTION 6.9.3.2 - IMPLEMI<.NTATIONOF GENERIC LETTER 88-16 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.
The proposed amendment, as shown in Attachment 1, would modify Section 6.9.3.2 of the WNP-2 Technical Specifications by adding reference to three topical reports describing analytical methods that may be used in determining reactor core operating limits for reload licensing applications. This change is consistent with Reference 1, and similar amendments have been approved by References 2 and 3. The topical reports themselves have been previously approved by NRC by References 4, 5, and 6 as being acceptable for use at WNP-2 in reload licensing applications.
As discussed in Attachment 2, the Supply System has concluded that the proposed change to the WNP-2 Technical Specifications does not involve a significant hazards consideration. In addition, the proposed changes do not create the potential for a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, nor do the changes involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly,'he proposed change meets the eligibility criteria for a categorical exclusion as set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b),
an environmental assessment of the change is not required.
This Technical Specification amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.
The State of Washington has been provided a copy of this letter in accordance with 10 CFR 50.91.
Should you have any questions or desire additional information regarding this matter, please call me or Mr. D. A. Swank at (509) 377-4563, J. V. Parrish (Mail Drop 1023)
Vice-President, Nuclear Operations CJF/ml Attachments CC: LJ Callan - NRC RIV KE Perkins Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston &, Strawn JW Clifford - NRC FS Adair - EFSEC DL Williams - BPA/399 NRC Resident Inspector - 927N
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STATE OF WASHINGTON )
Subject:
Request for Amendment to TS to add references to Section 6.9.3.2
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COUNTY OF BENTON )
I, J.V. Parrish, being duly sworn, subscribe to and say that I am the Vice-President of Nuclear Operations 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 , 1995 J. V arrish, Vice-President for Nuclear Operations On this day personally appeared before me J.V. PARRISH, 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 ay f 1995 ...:.,
Notary Pu in a f9 th STATE OF WASHINGTON Residing at My Commission Expires
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