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| | issue date = 08/02/1984 | | | issue date = 08/02/1984 |
| | title = Requests Confirmation of CRGR Review Re Specific Uncertainties Conservatively Treated in GE Instrument Setpoint Methodology for Bwrs.Concern Should Be Treated as Generic | | | title = Requests Confirmation of CRGR Review Re Specific Uncertainties Conservatively Treated in GE Instrument Setpoint Methodology for Bwrs.Concern Should Be Treated as Generic |
| | author name = SORENSEN G C | | | author name = Sorensen G |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = SCHWENCER A | | | addressee name = Schwencer A |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000397 | | | docket = 05000397 |
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| {{#Wiki_filter:~a 1 REGULATVR) | | {{#Wiki_filter:1 |
| INFORMATION DISTRIBUTION S'TEt<(RIDS)'CCESSION NBR:8408070333 DOC~DATE: 89/08/02 NOTARIZED; NO DOCKET FACIL:50-397 NPPSS Nuclear Project<Unit?i Nashin'gton Public Powe 05000397 AUTH, NAME AUTHOR AFFILIATION SORENSEN,G AC, Nashington Public Power Supply System RECIP NAME RECIPIENT AFFILIATION SCHNENCERgA | | ~a REGULATVR) INFORMATION DISTRIBUTION S 'TEt< (RIDS) |
| ~Licensing Branch 2 SUBJECT;Requests confirmation of CRGR review re-specific uncertainties conservatively treated in GE instrument setpoint methodology for BNRs,Concern should be treated as generic.DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL SIZE: TITLE;OR Submittal: | | NBR:8408070333 DOC DATE: 89/08/02 |
| General Distribution NOTES'L:12/20/83 05000397 RECIP IENT ID CODE/NAME NRR LB2 BC Ol INTERNAL: ADM-LFMB NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGNS COPIES LTTR ENCL 7 7 1 0 1 1 1 0 1 1 1 RECIPIENT ID CODE/NAME ELD/HDS2 NRR/DL DIR NRR/DS I/METB G 04 COPIES LTTR ENCL 1 0 1 1 1 1 1.1 EXTERNAL: ACRS 09 NRC PDR 02 NTIS 6 6 1 1 1 1 LPDR NSIC 03 05 1 1 1'TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL.23 III Ir Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richland, Washington 99352 (509)372-5000 August 2, 1984 G02-84-445 Docket No.50-397 8408070333 840802 PDR ADOCK 05000397 P PDR Director of Nuclear Reactor Regulation Attention: | | ~ NOTARIZED; NO 'CCESSION DOCKET FACIL:50-397 NPPSS Nuclear Project< Unit ?i Nashin'gton Public Powe 05000397 AUTH, NAME AUTHOR AFFILIATION SORENSEN,G AC, Nashington Public Power Supply System RECIP NAME RECIPIENT AFFILIATION SCHNENCERgA ~ Licensing Branch 2 SUBJECT; Requests confirmation of CRGR review re -specific uncertainties conservatively treated in GE instrument setpoint methodology for BNRs,Concern should be treated as generic. |
| Mr.A.Schwencer, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL SIZE: |
| | TITLE; OR Submittal: General Distribution 05000397 NOTES'L:12/20/83 RECIP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB2 BC Ol 7 7 INTERNAL: ADM-LFMB 1 0 ELD/HDS2 1 0 NRR/DE/MTEB 1 1 NRR/DL DIR 1 1 NRR/DL/ORAB 1 0 NRR/DS I/METB 1 1 NRR/DS I/RAB 1 G 04 1 . 1 RGNS 1 1 EXTERNAL: ACRS 09 6 6 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1' NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL. 23 |
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| ==Dear Mr.Schwencer:== | | III Ir |
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| | Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 8408070333 840802 PDR ADOCK 05000397 August 2, 1984 P PDR G02-84-445 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| | ==Dear Mr. Schwencer:== |
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| ==Subject:== | | ==Subject:== |
| | NUCLEAR PLANT NO. 2 REQUEST FOR CONFIRMATION OF CRGR REVIEW |
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| ==Reference:== | | ==Reference:== |
| | Letter, T. M. Novak (NRC) to J. F. Carolan (PECO) with blind copy to Supply System Docket No. 50-397, "Transmittal of NRC Staff Report on Setpoint Methodology for GE Supplied Protection System Instrumentation", dated May 15, 1984 The reference letter:requested twelve utilities, constructing or operating Boiling Water Reactors, to provide additional confirmatory information to affirm that specific uncertainties have been conservatively treated in the General Electric instrument.setpoint methodology. |
| | The Supply System objects to the manner in which this concern has been brought to the attention of the utilities addressed by the letter. In the latter part of 1982, various utilities received inquiries with regard to instrument setpoint methodology via several routes: formal Requests for Information addressed to a specific docket, informal copies of similar requests for-information, either provided by hand or telecopied to utility employees, approved licensing conditions addressed in staff Safety Evaluation'Reports or proposed licensing conditions. |
| | A review of the inquiries to date and other documentation applicable to this concern readily, leads to the conclusion that the concern, as expressed by the staff,,is generic. It is the Supply System position that the issue is generic to.all utilities supplied protection system instrumentation by General. Electric and not restricted to the twelve utilities addressed by the reference. |
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| | A. Schwencer Page Two A'ugust 2, 1984 REQUEST FOR CONFIRMATION OF CRGR REVIEW The Supply System has.been unable,to.confirm that this concern has received formal review by the'Committee to Review Generic Requirements (CRGR) and considers the methodology of implementation to date, to be contrary to the policies of the Nuclear Regulatory Commission and in particular the spirit, if not the letter, of the CRGR charter. As stated in revision I to the CRGR charter, the CRGR "has the responsibility to review and recommend to the Executive Director for Operations (EDO} approval or disapproval of requirements to be imposed by the NRC staff on one or more classes of power reactors". Additionally, the CRGR is charged to develop controls to "make sure that requirements in place or to be issued (a} do 'in fact contribute effectively and significantly to the health and safety of the public, and (b) do lead to utilization of both NRC and licensee resources in as optimal a fashion as possible in the overall achievement of protection of public health and safety". The Supply System can not confirm that this concern has been subject to these controls. |
| | The referenced letter states that "the staff considers the Technical Speci-fications for instrument channel setpoint allowable values for licensed GE/BWR plants (and those specifications in preparation for NTOL plants in the licensing review process}, established based on the GE setpoint method-ology developed to date, to.be sufficiently conservative to permi t continued licensing of the NTOL plants and operation of licensed plants until this issue is resolved . . .". This statement confirms the generic applicability of this concern". Additionally the perceived method of implementing this concern on the twelve utilities in question without appropriate CRGR review casts doubt that the concern has -indeed had appropriate analysis. Also no verification exists that implementation of the concern will affect an effective and significant contribution to the health and safety of the public. Based on the significant costs, presented by the NSSS supplier to the utilities in question for obtaining the requested information, without CRGR review it evident that the staff has evaluated the burden placed on the utilities nor the is not consequences on the public, supporting those utilities. |
| | Accordingly, the Supply System requests that confirmation of the CRGR review of this concern, with the attendant information package described in the CRGR charter, be provided. .Additionally, there is no clear indication that this request to over.ten utilities has received an Office of Management and Budget approval per public law: Paper Work Reduction Act of 1980, PL 96-511. |
| | Should you have any questions regarding this request, please contact Mr. |
| | P. L. Powell, Manager, WNP.-2 Licens,ing. |
| | Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/tmh cc: R Auluck - NRC WS Chin - BPA AD Toth - NRC Site V Stello - NRC R Grunseich - LILCO |
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| | 0 Mr. Pat Powell Mr. Dale Holtzscher WPPSS Illinois Power Co. |
| | P. 0 ~ Box 968 500 S. 27th Street Mail Drop 956B Mail Code F-33 Richland, WA 99352 Decatur, IL 62525 Mr. Al Wegele Ms. Eileen Buzzelli Detroit Edison Co. Cleveland Electric Ilium. Co. |
| | 6400 N Dixie Highway |
| | ~ P.O. Box 84 Mail Drop 346 NOC Rm. Py-R 230 Newport, MI 48166 Perry, Ohio 44081 Mr. Neil Coddington Mr. John Price Pennsylvania Power 5 Light Co. Gulf States Utilities Two North Ninth Street P.O. Box 2951 All entown, PA 18101 Beaumont, TX 77704 Mr. John Morin Mr. Gerald Tenenbaum Long Island Lighting Co. Public Service Electric 5 Gas Shoreham Nuclear Power Station 80 Park Plaza P.O. Box 618 T-21' Wading River, NY 11792 Newark, NJ 07101 Mr. Charles Schroeder Hr. Tony Zallnick Commonwealth Edison Co. Niagara Mohawk Power Corp. |
| | P.O. Box 767 300 Erie Boulevard, West One First National Plaza Syracuse, NY 13202 Chicago, IL 6069Q Hr. John Fowler Hr. Dave Foreman Mississippi Power 5 Light,Co. General Electric Co P.O. Box 1640 175 Curtner Avenue Jackson, MS 39205 Hail Drop 682 San Jose, CA 95125 Hr. Roger Boyd Hr. T. E. Tipton KNC, Inc. Atomic Industrial Forum, Inc. |
| | 801 18th Street, NW 7101 Wisconsin Avenue Suite 300 Washington, p.C. 20014 Washington, D.C. 20006 |
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| NUCLEAR PLANT NO.2 REQUEST FOR CONFIRMATION OF CRGR REVIEW Letter, T.M.Novak (NRC)to J.F.Carolan (PECO)with blind copy to Supply System Docket No.50-397,"Transmittal of NRC Staff Report on Setpoint Methodology for GE Supplied Protection System Instrumentation", dated May 15, 1984 The reference letter:requested twelve utilities, constructing or operating Boiling Water Reactors, to provide additional confirmatory information to affirm that specific uncertainties have been conservatively treated in the General Electric instrument.setpoint methodology.
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| The Supply System objects to the manner in which this concern has been brought to the attention of the utilities addressed by the letter.In the latter part of 1982, various utilities received inquiries with regard to instrument setpoint methodology via several routes: formal Requests for Information addressed to a specific docket, informal copies of similar requests for-information, either provided by hand or telecopied to utility employees, approved licensing conditions addressed in staff Safety Evaluation'Reports or proposed licensing conditions.
| | +~1 s}} |
| A review of the inquiries to date and other documentation applicable to this concern readily, leads to the conclusion that the concern, as expressed by the staff,,is generic.It is the Supply System position that the issue is generic to.all utilities supplied protection system instrumentation by General.Electric and not restricted to the twelve utilities addressed by the reference.
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| t~I 1g+'Cs V 4 A.Schwencer Page Two A'ugust 2, 1984 REQUEST FOR CONFIRMATION OF CRGR REVIEW The Supply System has.been unable,to.confirm that this concern has received formal review by the'Committee to Review Generic Requirements (CRGR)and considers the methodology of implementation to date, to be contrary to the policies of the Nuclear Regulatory Commission and in particular the spirit, if not the letter, of the CRGR charter.As stated in revision I to the CRGR charter, the CRGR"has the responsibility to review and recommend to the Executive Director for Operations (EDO}approval or disapproval of requirements to be imposed by the NRC staff on one or more classes of power reactors".
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| Additionally, the CRGR is charged to develop controls to"make sure that requirements in place or to be issued (a}do'in fact contribute effectively and significantly to the health and safety of the public, and (b)do lead to utilization of both NRC and licensee resources in as optimal a fashion as possible in the overall achievement of protection of public health and safety".The Supply System can not confirm that this concern has been subject to these controls.The referenced letter states that"the staff considers the Technical Speci-fications for instrument channel setpoint allowable values for licensed GE/BWR plants (and those specifications in preparation for NTOL plants in the licensing review process}, established based on the GE setpoint method-ology developed to date, to.be sufficiently conservative to permi t continued licensing of the NTOL plants and operation of licensed plants until this issue is resolved...".This statement confirms the generic applicability of this concern".Additionally the perceived method of implementing this concern on the twelve utilities in question without appropriate CRGR review casts doubt that the concern has-indeed had appropriate analysis.Also no verification exists that implementation of the concern will affect an effective and significant contribution to the health and safety of the public.Based on the significant costs, presented by the NSSS supplier to the utilities in question for obtaining the requested information, without CRGR review it is not evident that the staff has evaluated the burden placed on the utilities nor the consequences on the public, supporting those utilities.
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| Accordingly, the Supply System requests that confirmation of the CRGR review of this concern, with the attendant information package described in the CRGR charter, be provided..Additionally, there is no clear indication that this request to over.ten utilities has received an Office of Management and Budget approval per public law: Paper Work Reduction Act of 1980, PL 96-511.Should you have any questions regarding this request, please contact Mr.P.L.Powell, Manager, WNP.-2 Licens,ing.
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| Very truly yours, G.C.Sorensen, Manager Regulatory Programs PLP/tmh cc: R Auluck-NRC WS Chin-BPA AD Toth-NRC Site V Stello-NRC R Grunseich-LILCO
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| ~~t~e 4 C lf 0 Mr.Pat Powell WPPSS P.0~Box 968 Mail Drop 956B Richland, WA 99352 Mr.Al Wegele Detroit Edison Co.6400 N~Dixie Highway Mail Drop 346 NOC Newport, MI 48166 Mr.Neil Coddington Pennsylvania Power 5 Light Co.Two North Ninth Street All entown, PA 18101 Mr.John Morin Long Island Lighting Co.Shoreham Nuclear Power Station P.O.Box 618 Wading River, NY 11792 Mr.Charles Schroeder Commonwealth Edison Co.P.O.Box 767 One First National Plaza Chicago, IL 6069Q Hr.John Fowler Mississippi Power 5 Light,Co.P.O.Box 1640 Jackson, MS 39205 Hr.Roger Boyd KNC, Inc.801 18th Street, NW Suite 300 Washington, D.C.20006 Mr.Dale Holtzscher Illinois Power Co.500 S.27th Street Mail Code F-33 Decatur, IL 62525 Ms.Eileen Buzzelli Cleveland Electric Ilium.Co.P.O.Box 84 Rm.Py-R 230 Perry, Ohio 44081 Mr.John Price Gulf States Utilities P.O.Box 2951 Beaumont, TX 77704 Mr.Gerald Tenenbaum Public Service Electric 5 Gas 80 Park Plaza T-21'Newark, NJ 07101 Hr.Tony Zallnick Niagara Mohawk Power Corp.300 Erie Boulevard, West Syracuse, NY 13202 Hr.Dave Foreman General Electric Co 175 Curtner Avenue Hail Drop 682 San Jose, CA 95125 Hr.T.E.Tipton Atomic Industrial Forum, Inc.7101 Wisconsin Avenue Washington, p.C.20014 F 0+~1 s}}
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Letter Sequence Request |
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MONTHYEARML17277B4651984-08-0202 August 1984
Requests Confirmation of CRGR Review Re Specific Uncertainties Conservatively Treated in GE Instrument Setpoint Methodology for Bwrs.Concern Should Be Treated as Generic
Project stage: Request
ML20197J1191984-10-0303 October 1984
Forwards SER on Containment Isolation Dependability by Demonstration of Purge & Vent Valve Operability. Appropriate Tech Specs Should Be Issued to Reflect Limitations of Valve Opening Angles
Project stage: Approval
1984-10-03
[Table View] |
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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
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17286A2801990-08-27027 August 1990
Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d)
ML17286A2671990-08-23023 August 1990
Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors
ML17286A2641990-08-20020 August 1990
Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee
ML17285B4341990-08-20020 August 1990
Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators.
IR 05000397/19900141990-08-10010 August 1990
Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised
ML17285B4171990-08-10010 August 1990
Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised
ML17285B4041990-08-0202 August 1990
Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns
ML17285B3981990-07-30030 July 1990
Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys
ML17285B3991990-07-27027 July 1990
Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs
ML17285B3711990-07-12012 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed
ML17285B3761990-07-12012 July 1990
Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring
ML17285B3781990-07-11011 July 1990
Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur
ML17285B3841990-07-10010 July 1990
Forwards Util 1990 Emergency Exercise Scenario.W/O Encl
ML17285B3661990-07-0505 July 1990
Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager
ML17285B3641990-06-29029 June 1990
Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ
ML17285B3571990-06-28028 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions.
ML20055D2391990-06-28028 June 1990
Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21)
ML17285B3501990-06-22022 June 1990
Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed
ML17285B3511990-06-20020 June 1990
Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval
ML17285B3441990-06-20020 June 1990
Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead
ML17285B3451990-06-19019 June 1990
Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions
ML17285B3431990-06-18018 June 1990
Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601
ML17285B3461990-06-15015 June 1990
Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle
ML17285B3301990-06-12012 June 1990
Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty Dtd 900521
ML17285B3251990-06-0707 June 1990
Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701
ML17285B2931990-05-29029 May 1990
Responds to NRC 900426 Ltr Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons
ML17285B2861990-05-22022 May 1990
Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991
ML17285B2881990-05-11011 May 1990
Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util 900329 Ltr.W/O Encl
ML17285B2471990-05-0101 May 1990
Advises That No Changes to Tech Specs Required as Stated in 891130 Ltr in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS
ML17285B2741990-04-26026 April 1990
Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered
ML17285B2321990-04-25025 April 1990
Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-17
ML17285B2121990-04-19019 April 1990
Responds to Fire Protection Issues Identified in 900201 Notice of Violation.Corrective Actions:Major Hardware Changes Implemented & Independent Consultant Will Be Employed to Review Fire Protection Program
ML17285B2221990-04-16016 April 1990
Forwards Status Rept for Commitments Made in 891130 Ltr Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed
ML17285B1881990-04-11011 April 1990
Responds to NRC 900312 Ltr Re Violations Noted in Insp Rept 50-397/90-01.Corrective Actions:Complete Job & Task Analysis Completed for Health Physics Technician Training Program & New Program Will Include Training on Fundamentals
ML17285B1821990-04-0505 April 1990
Requests Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii) & (IV) to Allow Delayed Submittal of NRC Form-474, Simulation Facility Certification & to Administer Simulation Test as Upgraded,Respectively
ML17285B1741990-04-0505 April 1990
Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21
ML20012F6141990-04-0404 April 1990
Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML17285B2041990-03-29029 March 1990
Requests Review of Encl Topical Rept WPPSS-FTS-127,Rev 0, Qualification of Core Physics Methods for BWR Design & Analysis. Upon Rept Approval,Tech Spec Changes (Per Generic Ltr 88-16) Scheduled for Jan 1992
ML17285B1421990-03-29029 March 1990
Forwards Revised Schedule for Plant Equipment Setpoint Methodology Program Plan.Methodology Revised to Incorporate Latest ISA Std Draft.Setpoint Program Design Team for FY90 Onsite,Trained & Began Work on 900312
ML17285B1381990-03-29029 March 1990
Forwards Concluding Rept of Results Requested by Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment. Air Quality Testing Performed to Date Reveals Steadily Improving Results
ML17285B1131990-03-28028 March 1990
Advises of Release of Subchannel Thermal Hydraulic Computer Code & Requests Review of VIPRE-01 Mod-02 & Issuance of SER for PWR & BWR Applications.Bwr Qualification Analyses Completed & Rept on BWR Applications Encl
ML17285B1331990-03-23023 March 1990
Responds to NRC 900221 Ltr Re Violations Noted in Insp Rept 50-397/89-40.Corrective Actions:Plant Procedure 10.25.63, Emergency Lighting Insp in Process of Being Expanded to Provide Instructions & Check Sheets to Ensure Uniform Insps
ML17285B1311990-03-21021 March 1990
Forwards Proposed Bases Change Re 891129 Request for Amend to Tech Spec Table 4.3.6.1, Srm/Irm Detector Not-Full-In Functional Test. Bases Change Describes Special Circumstances Re Test Exception
ML17285B1291990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in LWRs & Generic Ltr 89-21 Re Status of Implementation of Usis.Tech Specs Adequate to Verify Operability of Overfill Protection Sys
ML17285B1171990-03-19019 March 1990
Suppls 900102 Response Re Implementation of fitness-for-duty Program at Facility.All Items Identified as Incomplete as of 900103 Completed at End of Jan 1990
ML17285B1121990-03-15015 March 1990
Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement
ML17285B0931990-03-0202 March 1990
Forwards Supplementary Info Re 900214 Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Address Failed Safety/Relief Valve Position Indicators
ML17285B0741990-03-0202 March 1990
Responds to NRC 900201 Ltr Re Violations Noted in Insp Rept 50-397/89-30.Corrective Action:Plant Personnel Currently in Process of Making Improvements to Plant Operations Procedure Writers Guide
ML17285B0861990-03-0101 March 1990
Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01
ML17285B0581990-02-26026 February 1990
Forwards Washington Nuclear Plant-2 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989 & Amend 7 to Odcm.
1990-08-27
[Table view] |
Text
1
~a REGULATVR) INFORMATION DISTRIBUTION S 'TEt< (RIDS)
NBR:8408070333 DOC DATE: 89/08/02
~ NOTARIZED; NO 'CCESSION DOCKET FACIL:50-397 NPPSS Nuclear Project< Unit ?i Nashin'gton Public Powe 05000397 AUTH, NAME AUTHOR AFFILIATION SORENSEN,G AC, Nashington Public Power Supply System RECIP NAME RECIPIENT AFFILIATION SCHNENCERgA ~ Licensing Branch 2 SUBJECT; Requests confirmation of CRGR review re -specific uncertainties conservatively treated in GE instrument setpoint methodology for BNRs,Concern should be treated as generic.
DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL SIZE:
TITLE; OR Submittal: General Distribution 05000397 NOTES'L:12/20/83 RECIP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB2 BC Ol 7 7 INTERNAL: ADM-LFMB 1 0 ELD/HDS2 1 0 NRR/DE/MTEB 1 1 NRR/DL DIR 1 1 NRR/DL/ORAB 1 0 NRR/DS I/METB 1 1 NRR/DS I/RAB 1 G 04 1 . 1 RGNS 1 1 EXTERNAL: ACRS 09 6 6 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1' NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL. 23
III Ir
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 8408070333 840802 PDR ADOCK 05000397 August 2, 1984 P PDR G02-84-445 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PLANT NO. 2 REQUEST FOR CONFIRMATION OF CRGR REVIEW
Reference:
Letter, T. M. Novak (NRC) to J. F. Carolan (PECO) with blind copy to Supply System Docket No. 50-397, "Transmittal of NRC Staff Report on Setpoint Methodology for GE Supplied Protection System Instrumentation", dated May 15, 1984 The reference letter:requested twelve utilities, constructing or operating Boiling Water Reactors, to provide additional confirmatory information to affirm that specific uncertainties have been conservatively treated in the General Electric instrument.setpoint methodology.
The Supply System objects to the manner in which this concern has been brought to the attention of the utilities addressed by the letter. In the latter part of 1982, various utilities received inquiries with regard to instrument setpoint methodology via several routes: formal Requests for Information addressed to a specific docket, informal copies of similar requests for-information, either provided by hand or telecopied to utility employees, approved licensing conditions addressed in staff Safety Evaluation'Reports or proposed licensing conditions.
A review of the inquiries to date and other documentation applicable to this concern readily, leads to the conclusion that the concern, as expressed by the staff,,is generic. It is the Supply System position that the issue is generic to.all utilities supplied protection system instrumentation by General. Electric and not restricted to the twelve utilities addressed by the reference.
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A. Schwencer Page Two A'ugust 2, 1984 REQUEST FOR CONFIRMATION OF CRGR REVIEW The Supply System has.been unable,to.confirm that this concern has received formal review by the'Committee to Review Generic Requirements (CRGR) and considers the methodology of implementation to date, to be contrary to the policies of the Nuclear Regulatory Commission and in particular the spirit, if not the letter, of the CRGR charter. As stated in revision I to the CRGR charter, the CRGR "has the responsibility to review and recommend to the Executive Director for Operations (EDO} approval or disapproval of requirements to be imposed by the NRC staff on one or more classes of power reactors". Additionally, the CRGR is charged to develop controls to "make sure that requirements in place or to be issued (a} do 'in fact contribute effectively and significantly to the health and safety of the public, and (b) do lead to utilization of both NRC and licensee resources in as optimal a fashion as possible in the overall achievement of protection of public health and safety". The Supply System can not confirm that this concern has been subject to these controls.
The referenced letter states that "the staff considers the Technical Speci-fications for instrument channel setpoint allowable values for licensed GE/BWR plants (and those specifications in preparation for NTOL plants in the licensing review process}, established based on the GE setpoint method-ology developed to date, to.be sufficiently conservative to permi t continued licensing of the NTOL plants and operation of licensed plants until this issue is resolved . . .". This statement confirms the generic applicability of this concern". Additionally the perceived method of implementing this concern on the twelve utilities in question without appropriate CRGR review casts doubt that the concern has -indeed had appropriate analysis. Also no verification exists that implementation of the concern will affect an effective and significant contribution to the health and safety of the public. Based on the significant costs, presented by the NSSS supplier to the utilities in question for obtaining the requested information, without CRGR review it evident that the staff has evaluated the burden placed on the utilities nor the is not consequences on the public, supporting those utilities.
Accordingly, the Supply System requests that confirmation of the CRGR review of this concern, with the attendant information package described in the CRGR charter, be provided. .Additionally, there is no clear indication that this request to over.ten utilities has received an Office of Management and Budget approval per public law: Paper Work Reduction Act of 1980, PL 96-511.
Should you have any questions regarding this request, please contact Mr.
P. L. Powell, Manager, WNP.-2 Licens,ing.
Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/tmh cc: R Auluck - NRC WS Chin - BPA AD Toth - NRC Site V Stello - NRC R Grunseich - LILCO
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0 Mr. Pat Powell Mr. Dale Holtzscher WPPSS Illinois Power Co.
P. 0 ~ Box 968 500 S. 27th Street Mail Drop 956B Mail Code F-33 Richland, WA 99352 Decatur, IL 62525 Mr. Al Wegele Ms. Eileen Buzzelli Detroit Edison Co. Cleveland Electric Ilium. Co.
6400 N Dixie Highway
~ P.O. Box 84 Mail Drop 346 NOC Rm. Py-R 230 Newport, MI 48166 Perry, Ohio 44081 Mr. Neil Coddington Mr. John Price Pennsylvania Power 5 Light Co. Gulf States Utilities Two North Ninth Street P.O. Box 2951 All entown, PA 18101 Beaumont, TX 77704 Mr. John Morin Mr. Gerald Tenenbaum Long Island Lighting Co. Public Service Electric 5 Gas Shoreham Nuclear Power Station 80 Park Plaza P.O. Box 618 T-21' Wading River, NY 11792 Newark, NJ 07101 Mr. Charles Schroeder Hr. Tony Zallnick Commonwealth Edison Co. Niagara Mohawk Power Corp.
P.O. Box 767 300 Erie Boulevard, West One First National Plaza Syracuse, NY 13202 Chicago, IL 6069Q Hr. John Fowler Hr. Dave Foreman Mississippi Power 5 Light,Co. General Electric Co P.O. Box 1640 175 Curtner Avenue Jackson, MS 39205 Hail Drop 682 San Jose, CA 95125 Hr. Roger Boyd Hr. T. E. Tipton KNC, Inc. Atomic Industrial Forum, Inc.
801 18th Street, NW 7101 Wisconsin Avenue Suite 300 Washington, p.C. 20014 Washington, D.C. 20006
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