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| {{#Wiki_filter:CATEGORY1REGULATOIINFORMATtON DISTRIBUTION jTEM(RODS)ACCESSION NBR:9706170043 DOC.DATS; 97/06/06NOTARIZED: | | {{#Wiki_filter:CATEGORY 1 REGULATOIINFORMATtON DISTRIBUTION jTEM (RODS)ACCESSION NBR:9706170043 DOC.DATS;97/06/06 NOTARIZED: |
| YESDOCKETFAC'IL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPowe05000397AUT~sk.NAMEAUTHORAFFILIATION BEMIS,P.R.
| | YES DOCKET FAC'IL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUT~sk.NAME AUTHOR AFFILIATION BEMIS,P.R. |
| Washington PublicBowerSuppl,ySystemRECIP.NAME RECIPIENT AFFILIA'9(ON DocumentControlBranch(Document ControlDesk) | | Washington Public Bower Suppl,y System RECIP.NAME RECIPIENT AFFILIA'9(ON Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Withdraws requestforamendofSLMCPR.Requested changesto970520ltrincluded&TSpaqe2.0-l,modified toindicatetharSLMCPRforATRIUM-9X fidelappliesonlytoCycle13,'orwarded w/corresponding Bqsespage.DISTRIBUTION CODE'001D COPIESRECEIVED;LTR | | Withdraws request for amend of SLMCPR.Requested changes to 970520 ltr included&TS paqe 2.0-l,modified to indicate thar SLMCPR for ATRIUM-9X fidel applies only to Cycle 13,'orwarded w/corresponding Bqses page.DISTRIBUTION CODE'001D COPIES RECEIVED;LTR |
| ,ENCLSIZE'ITLE: | | , ENCL SIZE'ITLE: |
| ORSubmittal:
| | OR Submittal: |
| GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD4-2LACOLBURNFT COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD4-2PDCOPIESLTTRENCL11INTERNAL:
| | General Distribution NOTES: RECIPIENT ID CODE/NAME PD4-2 LA COLBURNFT COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD4-2 PD COPIES LTTR ENCL 1 1 INTERNAL: ACRS NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC 1 1 1 1 1 1 1 1 1 0 1 1 FILE CENTER RPDE+l.bRB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR'1 1 1 1 1 1 1 1 1 1 D U N NOTE TO ALL"RIDS" RECIPZENTS: |
| ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK{DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 |
| NOAC111111111011FILECENTERRPDE+l.bRB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR'1111111111DUNNOTETOALL"RIDS"RECIPZENTS:
| | 'C t g'g WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richland,, Washington 99352-0968 June 6, 1997 G02-97-115 Docket No.50-397 U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Gentlemen: |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK{DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR14ENCL13
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| 'Ctg'g WASHINGTON PUBLICPOWERSUPPLYSYSTEMP.O.Box968~Richland,, | |
| Washington 99352-0968 June6,1997G02-97-115 DocketNo.50-397U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen: | |
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| ==Subject:== | | ==Subject:== |
| WNP-2OPERATING LICENSENPF-21EXIGENTREQUESTFORAMENDMENT OFSLMCPR-MODIFICATION OFREQUEST | | WNP-2 OPERATING LICENSE NPF-21 EXIGENT REQUEST FOR AMENDMENT OF SLMCPR-MODIFICATION OF REQUEST |
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| ==Reference:== | | ==Reference:== |
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| LetterGO2-97-102 datedMay20,1997,P.R.Bemis(SupplySystem)toNRCDocumentControlDesk,WNP-2Operating LicenseNPF-21ExigentRequestforAmendment:
| | Letter GO2-97-102 dated May 20, 1997, P.R.Bemis (Supply System)to NRC Document Control Desk, WNP-2 Operating License NPF-21 Exigent Request for Amendment: |
| MinimumCriticalPowerRatioSafetyLimitsThereferenced letterrequestsanexigentchangetotheWNP-2Technical Specifications (Section2.1.1.2)toestablish aninterimsafetylimit(SLMCPR)forSiemensPowerCorporation (SPC)ATRIUM-9X fuel.Inconjunction withtherequested change,areference describing themethodusedtoestablish theinterimsafetylimitwasproposedforinclusion intheCOLRreference list.Subsequent reviewbyNRCstaffhasdetermined thattheinclusion ofthisreference isnotnecessary forTechnical Specifications Section5.6.5.Accordingly, theSupplySystemherebywithdraws itsrequesttoinsertthenewreference inSection5.6.5.sNRCstaffreviewofthereferenced letteralsoidentified thatadditional information isnecessary toclarifytheuseofSPCSLMCPRfromCycle11insubsequent cycles.Therequested changestoAttachment iofthereferenced letterareincludedasAttachment itothisletter.Inaddition, Technical Specification page2.0-1hasbeenmodifiedtoindicatethattheSLMCPRforATRIUM-9X fuelappliesonlytoCycle13.Thisclarifies theintentoftheoriginalchangemadeinthereferenced letter.Attachment 2providestherevisedTechnical Specification page2.0-1andthecorresponding Basespage.'P70bl70043 970bObPDRADOCK05000397PPDR't60944IIIIIIIlllllllillIIIIlllillllIIl'Illllll e
| | Minimum Critical Power Ratio Safety Limits The referenced letter requests an exigent change to the WNP-2 Technical Specifications (Section 2.1.1.2)to establish an interim safety limit (SLMCPR)for Siemens Power Corporation (SPC)ATRIUM-9X fuel.In conjunction with the requested change, a reference describing the method used to establish the interim safety limit was proposed for inclusion in the COLR reference list.Subsequent review by NRC staff has determined that the inclusion of this reference is not necessary for Technical Specifications Section 5.6.5.Accordingly, the Supply System hereby withdraws its request to insert the new reference in Section 5.6.5.s NRC staff review of the referenced letter also identified that additional information is necessary to clarify the use of SPC SLMCPR from Cycle 11 in subsequent cycles.The requested changes to Attachment i of the referenced letter are included as Attachment i to this letter.In addition, Technical Specification page 2.0-1 has been modified to indicate that the SLMCPR for ATRIUM-9X fuel applies only to Cycle 13.This clarifies the intent of the original change made in the referenced letter.Attachment 2 provides the revised Technical Specification page 2.0-1 and the corresponding Bases page.'P70bl70043 970bOb PDR ADOCK 05000397 P PDR't60944 IIIIIIIlllllllillIIIIlllillllIIl'Illllll e |
| EXIGENTREQUESTFRAMENDMENT OFSLMCPRMODIFICATION OFREQUESTPageosThechangesproposedbythisletterdonotalterthepreviousconclusion ofnosignificant hazardsthatwereevaluated inaccordance with10CFR50.92(c) anddocumented inthereferenced letter.Therevisedamendment requesthasalsobeenevaluated againstthecriteriaforidentification oflicensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.
| | EXIGENT REQUEST F R AMENDMENT OF SLMCPR MODIFICATION OF REQUEST Pageos The changes proposed by this letter do not alter the previous conclusion of no significant hazards that were evaluated in accordance with 10CFR50.92(c) and documented in the referenced letter.The revised amendment request has also been evaluated against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. |
| Themodifiedrequestcontinues tomeettheeligibility criteriaforacategorical exclusion assetforthin10CFR51.22(c)(9).
| | The modified request continues to meet the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(c)(9). |
| Therefore, inaccordance with10CFR51.22(b), | | Therefore, in accordance with 10CFR51.22(b), an environmental assessment of the change is not required.This request for modification of the pending exigent Technical Specifications amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.In accordance with 10CFR50.91, the State of Washington has been provided a copy of this letter.Should you have any questions or desire additional information regarding the matter, please contact Mr.P.J.Inserra at (509)377-4147.Respectfully, P.R.Bemis Vice President Nuclear Operations Mail Drop PE23 Attachments CC: EW Merschoff-NRC RIV KE Perkins, Jr.-NRC RIV, Walnut Creek Field Office TG Colburn-NRR NRC Sr.Resident Inspector-927N DL Williams-BPA/399 CR Wallis-EFSEC PD Robinson-Winston&Strawn |
| anenvironmental assessment ofthechangeisnotrequired.
| | , STATE OF WASHINGTON) |
| Thisrequestformodification ofthependingexigentTechnical Specifications amendment requesthasbeenreviewedandapprovedbytheWNP-2PlantOperations Committee andtheSupplySystemCorporate NuclearSafetyReviewBoard.Inaccordance with10CFR50.91, theStateofWashington hasbeenprovidedacopyofthisletter.Shouldyouhaveanyquestions ordesireadditional information regarding thematter,pleasecontactMr.P.J.Inserraat(509)377-4147.
| | )COUNTY OF BENTON) |
| Respectfully, P.R.BemisVicePresident NuclearOperations MailDropPE23Attachments CC:EWMerschoff | |
| -NRCRIVKEPerkins,Jr.-NRCRIV,WalnutCreekFieldOfficeTGColburn-NRRNRCSr.ResidentInspector | |
| -927NDLWilliams-BPA/399CRWallis-EFSECPDRobinson-Winston&Strawn | |
| ,STATEOFWASHINGTON) | |
| )COUNTYOFBENTON) | |
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| ==Subject:== | | ==Subject:== |
| RequestforMcxBfication ofAmendment toTSMCPRafeLimiI,G.O.SMITH,beingdulysworn,subscribe toandsaythatIamtheActingVicePresident, NuclearOperations fortheWASHINGTON PUBLICPOWERSUPPLYSYSTEM,theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthestatements madeinitaretrue.DATE,1997G.O.SnuthActingVicePresident, NuclearOperations Onthisdatepersonally appearedbeforemeG.O.Smith,tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledged thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.
| | Request for McxBfication of Amendment to TS MCPR afe Limi I, G.O.SMITH, being duly sworn, subscribe to and say that I am the Acting Vice President, 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 , 1997 G.O.Snuth Acting Vice President, Nuclear Operations On this date personally appeared before me G.O.Smith, 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. |
| GIVENundermyhandandsealthis~dayof1997NotaryPublicmandfortheSTATEOFWASHINGTON byrResidingatMyCommission Expires EXIGENTREQUESTFORAMENDMENT OFSLMCPRMODIFICATION OFREQUESTAttachment 1'agelof1ATTACHMi22IT 1Submittal ofAdditional Information Page1ofAttachment 1ofthedocumentreferenced belowisrevisedbyinserting thefollowing textasnewparagraph 2:Cycle13willbecomprised of112freshABBassemblies, 104once-burned ABBassemblies, and548oftheatleasttwiceburnedATRIUM-9X assemblies.
| | GIVEN under my hand and seal this~day of 1997 Notary Public m and for the STATE OF WASHINGTON by r Residing at My Commission Expires EXIGENT REQUEST FOR AMENDMENT OF SLMCPR MODIFICATION OF REQUEST Attachment 1'agelof 1 ATTACHMi22IT 1 Submittal of Additional Information Page 1 of Attachment 1 of the document referenced below is revised by inserting the following text as new paragraph 2: Cycle 13 will be comprised of 112 fresh ABB assemblies, 104 once-burned ABB assemblies, and 548 of the at least twice burned ATRIUM-9X assemblies. |
| TheNRCapprovedABBmethodology (i.e.,COLRReference 11:CENPD-300-P-A) assumesthatthesafetylimitMCPR(SLMCPR)forthenon-ABBresidentfuelisunchanged fromthelastcycleforwhichitwasevaluated byitssupplier.
| | The NRC approved ABB methodology (i.e., COLR Reference 11: CENPD-300-P-A) assumes that the safety limit MCPR (SLMCPR)for the non-ABB resident fuel is unchanged from the last cycle for which it was evaluated by its supplier.The A'INDIUM-9X fuel was last evaluated by SPC in Cycle ll.Accordingly, a new ATRIUM-9X SLMCPR for Cycle 11 has been determined by SPC (Reference 3)using the changes to the additive constant uncertainty discussed below.The SPC determined SLMCPR will be applied by ABB to Cycle 13 and future cycles that use the ATRIUM-9X fuel. |
| TheA'INDIUM-9X fuelwaslastevaluated bySPCinCyclell.Accordingly, anewATRIUM-9X SLMCPRforCycle11hasbeendetermined bySPC(Reference 3)usingthechangestotheadditiveconstantuncertainty discussed below.TheSPCdetermined SLMCPRwillbeappliedbyABBtoCycle13andfuturecyclesthatusetheATRIUM-9X fuel.
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| ==Reference:== | | ==Reference:== |
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| LetterGO2-97-102 datedMay20,1997,P.R.Bemis(SupplySystem)toNRCDocumentControlDesk,WNP-2Operating LicenseNPF-21ExigentRequestforAmendment:
| | Letter GO2-97-102 dated May 20, 1997, P.R.Bemis (Supply System)to NRC Document Control Desk, WNP-2 Operating License NPF-21 Exigent Request for Amendment: |
| MinimumCriticalPowerRatioSafetyLimits.}}
| | Minimum Critical Power Ratio Safety Limits.}} |
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|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999
Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required
ML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML20206U4501999-05-19019 May 1999
Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
ML20196K6961999-03-30030 March 1999
Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p)
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML20204F0261999-03-19019 March 1999
Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML17292B5991999-03-16016 March 1999
Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3)
ML17292B5911999-03-16016 March 1999
Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5901999-03-11011 March 1999
Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted
ML17292B5681999-03-0101 March 1999
Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1
ML17292B5651999-02-22022 February 1999
Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint
ML17292B5581999-02-0404 February 1999
Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999
1999-09-09
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CATEGORY 1 REGULATOIINFORMATtON DISTRIBUTION jTEM (RODS)ACCESSION NBR:9706170043 DOC.DATS;97/06/06 NOTARIZED:
YES DOCKET FAC'IL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUT~sk.NAME AUTHOR AFFILIATION BEMIS,P.R.
Washington Public Bower Suppl,y System RECIP.NAME RECIPIENT AFFILIA'9(ON Document Control Branch (Document Control Desk)
SUBJECT:
Withdraws request for amend of SLMCPR.Requested changes to 970520 ltr included&TS paqe 2.0-l,modified to indicate thar SLMCPR for ATRIUM-9X fidel applies only to Cycle 13,'orwarded w/corresponding Bqses page.DISTRIBUTION CODE'001D COPIES RECEIVED;LTR
, ENCL SIZE'ITLE:
OR Submittal:
General Distribution NOTES: RECIPIENT ID CODE/NAME PD4-2 LA COLBURNFT COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD4-2 PD COPIES LTTR ENCL 1 1 INTERNAL: ACRS NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC 1 1 1 1 1 1 1 1 1 0 1 1 FILE CENTER RPDE+l.bRB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR'1 1 1 1 1 1 1 1 1 1 D U N NOTE TO ALL"RIDS" RECIPZENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK{DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
'C t g'g WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richland,, Washington 99352-0968 June 6, 1997 G02-97-115 Docket No.50-397 U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Gentlemen:
Subject:
WNP-2 OPERATING LICENSE NPF-21 EXIGENT REQUEST FOR AMENDMENT OF SLMCPR-MODIFICATION OF REQUEST
Reference:
Letter GO2-97-102 dated May 20, 1997, P.R.Bemis (Supply System)to NRC Document Control Desk, WNP-2 Operating License NPF-21 Exigent Request for Amendment:
Minimum Critical Power Ratio Safety Limits The referenced letter requests an exigent change to the WNP-2 Technical Specifications (Section 2.1.1.2)to establish an interim safety limit (SLMCPR)for Siemens Power Corporation (SPC)ATRIUM-9X fuel.In conjunction with the requested change, a reference describing the method used to establish the interim safety limit was proposed for inclusion in the COLR reference list.Subsequent review by NRC staff has determined that the inclusion of this reference is not necessary for Technical Specifications Section 5.6.5.Accordingly, the Supply System hereby withdraws its request to insert the new reference in Section 5.6.5.s NRC staff review of the referenced letter also identified that additional information is necessary to clarify the use of SPC SLMCPR from Cycle 11 in subsequent cycles.The requested changes to Attachment i of the referenced letter are included as Attachment i to this letter.In addition, Technical Specification page 2.0-1 has been modified to indicate that the SLMCPR for ATRIUM-9X fuel applies only to Cycle 13.This clarifies the intent of the original change made in the referenced letter.Attachment 2 provides the revised Technical Specification page 2.0-1 and the corresponding Bases page.'P70bl70043 970bOb PDR ADOCK 05000397 P PDR't60944 IIIIIIIlllllllillIIIIlllillllIIl'Illllll e
EXIGENT REQUEST F R AMENDMENT OF SLMCPR MODIFICATION OF REQUEST Pageos The changes proposed by this letter do not alter the previous conclusion of no significant hazards that were evaluated in accordance with 10CFR50.92(c) and documented in the referenced letter.The revised amendment request has also been evaluated against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21.
The modified request continues to meet the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(c)(9).
Therefore, in accordance with 10CFR51.22(b), an environmental assessment of the change is not required.This request for modification of the pending exigent Technical Specifications amendment request has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.In accordance with 10CFR50.91, the State of Washington has been provided a copy of this letter.Should you have any questions or desire additional information regarding the matter, please contact Mr.P.J.Inserra at (509)377-4147.Respectfully, P.R.Bemis Vice President Nuclear Operations Mail Drop PE23 Attachments CC: EW Merschoff-NRC RIV KE Perkins, Jr.-NRC RIV, Walnut Creek Field Office TG Colburn-NRR NRC Sr.Resident Inspector-927N DL Williams-BPA/399 CR Wallis-EFSEC PD Robinson-Winston&Strawn
, STATE OF WASHINGTON)
)COUNTY OF BENTON)
Subject:
Request for McxBfication of Amendment to TS MCPR afe Limi I, G.O.SMITH, being duly sworn, subscribe to and say that I am the Acting Vice President, 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 , 1997 G.O.Snuth Acting Vice President, Nuclear Operations On this date personally appeared before me G.O.Smith, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this~day of 1997 Notary Public m and for the STATE OF WASHINGTON by r Residing at My Commission Expires EXIGENT REQUEST FOR AMENDMENT OF SLMCPR MODIFICATION OF REQUEST Attachment 1'agelof 1 ATTACHMi22IT 1 Submittal of Additional Information Page 1 of Attachment 1 of the document referenced below is revised by inserting the following text as new paragraph 2: Cycle 13 will be comprised of 112 fresh ABB assemblies, 104 once-burned ABB assemblies, and 548 of the at least twice burned ATRIUM-9X assemblies.
The NRC approved ABB methodology (i.e., COLR Reference 11: CENPD-300-P-A) assumes that the safety limit MCPR (SLMCPR)for the non-ABB resident fuel is unchanged from the last cycle for which it was evaluated by its supplier.The A'INDIUM-9X fuel was last evaluated by SPC in Cycle ll.Accordingly, a new ATRIUM-9X SLMCPR for Cycle 11 has been determined by SPC (Reference 3)using the changes to the additive constant uncertainty discussed below.The SPC determined SLMCPR will be applied by ABB to Cycle 13 and future cycles that use the ATRIUM-9X fuel.
Reference:
Letter GO2-97-102 dated May 20, 1997, P.R.Bemis (Supply System)to NRC Document Control Desk, WNP-2 Operating License NPF-21 Exigent Request for Amendment:
Minimum Critical Power Ratio Safety Limits.
