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| {{#Wiki_filter:+CC~~~~GULANAkWAZAK DZQ~Z%VLLRRW(RZQ'~~~ | | {{#Wiki_filter:+CC~~~~GULANAkWAZAKDZQ~Z%VLLRRW(RZQ'~~~ |
| ACCESSION NBR:8809290114 DOC.DATE: 88/09/23 NOTARIZED: | | ACCESSION NBR:8809290114 DOC.DATE: 88/09/23 NOTARIZED: NO DOCKET ¹ |
| NO DOCKET¹'FA'CIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 TH.NAME AUTHOR AFFILIATION ENSEN,G.C. | | 'FA'CIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 TH.NAME AUTHOR AFFILIATION ENSEN,G.C. Washington Public Power Supply System ECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) to NRC 880824 ltr re violations noted in Insp Rept l |
| Washington Public Power Supply System ECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Responds to NRC 880824 ltr re violations noted in Insp Rept 50-397/88-21.Corrective actions: DISTRIBUTION CODE'EOZD COPIES RECEIVED'LTR | | Responds 50-397/88-21.Corrective actions: |
| -ENCL l SIZE'ITLE:
| | DISTRIBUTION CODE'EOZD COPIES RECEIVED'LTR General (50 Dkt)-Insp Rept/Notice of ENCL Response Violation SIZE'ITLE: |
| General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: RECIPIENT ID CODE/NAME PD5 PD INTERNAL: ACRS DEDRO NRR/DLPQ/PEB 11 NRR/DOEA DIR 11 NRR/DREP/RPB 10 NRR/PMAS/ILRB12 OE LXEBERMAN,J RE L 02 RGK FILE 01 RNAL: LPDR NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME SAMWORTH R AEOD NRR MORISSEAUPD NRR/DLPQ/QAB 10 NRR/DREP/EPB 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR DEPT NRC PDR COPIES LTTR ENCL 2 2 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 C II WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 September 23, 1988 G02-88-205 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, D.C.20555 Gentlemen: | | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 PD 1 1 SAMWORTH R 2 2 INTERNAL: ACRS 2 2 AEOD DEDRO 1 1 NRR MORISSEAUPD NRR/DLPQ/PEB 11 1 1 NRR/DLPQ/QAB 10 NRR/DOEA DIR 11 1 1 NRR/DREP/EPB 10 NRR/DREP/RPB 10 2 2 NRR/DRIS DIR 9A NRR/PMAS/ILRB12 1 1 NUDOCS-ABSTRACT OE LXEBERMAN,J 1 1 OGC/HDS2 RE L 02 1 1 RES/DSIR DEPT RGK FILE 01 1 1 RNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 September 23, 1988 G02-88-205 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, D. C. 20555 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT NO.2 LICENSE NO.NPF-21 NRC INSPECTION REPORT 88-21 The Washington Public Power Supply System her eby replies to the Notice of Violation contained in your letter dated August 24, 1988.Our reply, pursuant to the provision of Section 2.201, Title 10, Code of Federal Regulations, consists of this letter and Appendix A (attached). | | NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 NRC INSPECTION REPORT 88-21 The Washington Public Power Supply System her eby replies to the Notice of Violation contained in your letter dated August 24, 1988. Our reply, pursuant to the provision of Section 2.201, Title 10, Code of Federal Regulations, consists of this letter and Appendix A (attached). |
| In Appendix A, each violation is addressed with an explanation of our position regarding validity, corrective action and date of full compliance. | | In Appendix A, each violation is addressed with an explanation of our position regarding validity, corrective action and date of full compliance. |
| Very truly yours, G..Sorensen, Manager Regulatory Programs cc: JB Martin-NRC RV NS Reynolds-BCPZR RB Samworth-NRC DL Williams-BPA, 399 NRC Site Inspector-901A 88092901l4 880923 PDR ADOCK 05000397 6 PNU Appendix A Page 1 of 3 APPENDIX ADuring an NRC inspection conducted on May 30-July 7, 1988, the following violations of NRC requirements were identified. | | Very truly yours, G. . Sorensen, Manager Regulatory Programs cc: JB Martin - NRC RV NS Reynolds - BCPZR RB Samworth - NRC DL Williams - BPA, 399 NRC Site Inspector - 901A 88092901l4 880923 PDR ADOCK 05000397 6 PNU |
| In accordance with the"General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, these violations are listed below: A.Section 3.4.6.1 of the Technical Specifications states in part,"The reactor coolant system temperature and pressure shall be limited..., with: a.A maximum heatup of 100 in any 1-hour period,..." Con)rary to the above.a reactor coolant system heatup of approximately 137 F occurred during a plant startup on June 27, 1988.This is a Severity Level IV Violation (Supplement I).Validit of Violation The Supply System acknowledges the validity of this violation. | | |
| Corrective Ste s Taken/Results Achieved 1.Regarding exceeding the heatup limitation of Plant Technical Specification 3.4.6.1 on June 27, 1988: a)Plant heatup was immediately terminated when determined to be excessive. | | Appendix A Page 1 of 3 APPENDIX A During an NRC inspection conducted on May 30 - July 7, 1988, the following violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, these violations are listed below: |
| b)An Engineering evaluation was performed which concluded that no safety concerns were created by the excessive heatup r ate.c)Plant Procedure 7.4.4.6.1.1,"RPV (Reactor Pressure Vessel)Temperature/Pressure Log," was revised to provide additional guidance on control of Plant heatup and cooldown evolutions. | | A. Section 3.4.6.1 of the Technical Specifications states in part, "The reactor coolant system temperature and pressure shall be limited ..., with: |
| Significant changes made to prevent recurrence of this situation i'nclude:~heatup and cooldown rate is limited to 20 F during each 15 minute period.~heatup and cooldown rate is limited to 80 F per hour. | | : a. A maximum heatup of 100 in any 1-hour period,..." |
| | Con)rary to the above. a reactor coolant system heatup of approximately 137 F occurred during a plant startup on June 27, 1988. |
| | This is a Severity Level IV Violation (Supplement I). |
| | Validit of Violation The Supply System acknowledges the validity of this violation. |
| | Corrective Ste s Taken/Results Achieved |
| | : 1. Regarding exceeding the heatup limitation of Plant Technical Specification 3.4.6.1 on June 27, 1988: |
| | a) Plant heatup was immediately terminated when determined to be excessive. |
| | b) An Engineering evaluation was performed which concluded that no safety concerns were created by the excessive heatup r ate. |
| | c) Plant Procedure 7.4.4.6.1.1, "RPV (Reactor Pressure Vessel) |
| | Temperature/Pressure Log," was revised to provide additional guidance on control of Plant heatup and cooldown evolutions. |
| | Significant changes made to prevent recurrence of this situation i'nclude: |
| | ~ heatup and cooldown rate is limited to 20 F during each 15 minute period. |
| | ~ heatup and cooldown rate is limited to 80 F per hour. |
| | |
| | Appendix A Page 2 of 3 Pressure/Temperature |
| | ~ heatup/cooldown and RPV e Monitoring activities were divided into separ ate sections. |
| | ~ A steam table was provided to convert steam pressure (in PSIG) to temperature. |
| | d) A heatup and cooldown program has been added to the Plant status display on the Control Room Process Computer CRT. The program graphically displays heatup/cooldown in relation to 80 F/hr reference lines. In addition, digital displays indicate projected heatup/cooldown rates based on 15, 30 and 45 minute temperature changes. This information is updated every 60 seconds. Digital displays are also provided for actual hour ly rates. An alar m functi~n is provided for both projected and actual rates when the 80 F/hr limit is exceeded. |
| | : 2. Regarding the followup actions associated with the potential heatup/cooldown problems identified in Plant ()A Surveillance Report 2-88-018, Plant Operations failed to recognize the significance of the issue with regard to preventing recurrence due to lack of rigor and discipline in the initial review process. |
| | Corrective Action to be Taken |
| | : 1. Plant Oper ations Management will emphasize, to the Operations staff, the need for increased awareness and a more effective quality review of Plant gA Surveillance Reports. |
| | : 2. General Operating Procedures, for Plant startup and shutdown evolutions, will )e revised to limit hourly heatup and cooldown rates to a maximum of 80 F. |
| | Date of Full Com liance Although the Supply System is currently in full compliance, further corrective actions will be completed by October 31, 1988. |
| | B. 10CFR50.73.d states in part, "Licensee Event Reports must be ... submitted within 30 days of discovery of a reportable event..." |
| | Contrary to the above, the licensee identified in a ()A surveillance report issued on April 29, 1988 that the Technical Specification heatup and cooldown limits had been exceeded on February 20 and June 19, 1987, and did not issue a licensee event report within 30 days after this discovery. |
| | This is a Severity level IV Violation (Supplement I). |
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| Appendix A Page 2 of 3~heatup/cooldown and RPV Pressure/Temperature e Monitoring activities were divided into separ ate sections.~A steam table was provided to convert steam pressure (in PSIG)to temperature. | | Appendix A Page 3 of 3 Validit of Violation The Supply System acknowledges the validity of this violation. A definite determination that the Technical Specification limit had been exceeded was not provided in the QA Surveillance Report. Plant QA management had mistakenly determined that a Plant QA deficiency (finding) was the appropriate mechanism to initiate the reportability evaluation by the Plant personnel qualified and responsible for that function (e.g. Shift Manager or Plant Technical Compliance group). A Plant Nonconformance Report (NCR) should have been issued in accordance with Plant Procedure (PPM) 1.3.12, "Plant Problems." The purpose of the procedur is to provide instructions for the identification, documentation and disposition of Plant problems, and to ensure that each problem is reviewed for reportability in accordance with regulatory requirements. |
| d)A heatup and cooldown program has been added to the Plant status display on the Control Room Process Computer CRT.The program graphically displays heatup/cooldown in relation to 80 F/hr reference lines.In addition, digital displays indicate projected heatup/cooldown rates based on 15, 30 and 45 minute temperature changes.This information is updated every 60 seconds.Digital displays are also provided for actual hour ly rates.An alar m functi~n is provided for both projected and actual rates when the 80 F/hr limit is exceeded.2.Regarding the followup actions associated with the potential heatup/cooldown problems identified in Plant ()A Surveillance Report 2-88-018, Plant Operations failed to recognize the significance of the issue with regard to preventing recurrence due to lack of rigor and discipline in the initial review process.Corrective Action to be Taken 1.Plant Oper ations Management will emphasize, to the Operations staff, the need for increased awareness and a more effective quality review of Plant gA Surveillance Reports.2.General Operating Procedures, for Plant startup and shutdown evolutions, will)e revised to limit hourly heatup and cooldown rates to a maximum of 80 F.Date of Full Com liance Although the Supply System is currently in full compliance, further corrective actions will be completed by October 31, 1988.B.10CFR50.73.d states in part,"Licensee Event Reports must be...submitted within 30 days of discovery of a reportable event..." Contrary to the above, the licensee identified in a ()A surveillance report issued on April 29, 1988 that the Technical Specification heatup and cooldown limits had been exceeded on February 20 and June 19, 1987, and did not issue a licensee event report within 30 days after this discovery.
| | The Plant Operations Department, during the initial review of the Plant QA Surveillance Report, also failed to recognize the potential Technical Specification violation and; therefore, the reportability of the situation. |
| This is a Severity level IV Violation (Supplement I).
| | Corrective Ste s Taken/Results Achieved |
| Appendix A Page 3 of 3 Validit of Violation The Supply System acknowledges the validity of this violation.
| | : 1. On July 5, 1988 an NCR was written by the Plant QA organization which documented the situation that the QA Surveillance Report had identified three examples where the heatup/cooldown rates may have been exceeded. The Plant Technical Compliance Group was aware of the NCR and recognized the need to perform a reportability evaluation. However, due to the workload associated with scheduled commitments, the group was unable to evaluate the situation in a timely manner (the situation was determined to be reportable on August 23, 1988). |
| A definite determination that the Technical Specification limit had been exceeded was not provided in the QA Surveillance Report.Plant QA management had mistakenly determined that a Plant QA deficiency (finding)was the appropriate mechanism to initiate the reportability evaluation by the Plant personnel qualified and responsible for that function (e.g.Shift Manager or Plant Technical Compliance group).A Plant Nonconformance Report (NCR)should have been issued in accordance with Plant Procedure (PPM)1.3.12,"Plant Problems." The purpose of the procedur is to provide instructions for the identification, documentation and disposition of Plant problems, and to ensure that each problem is reviewed for reportability in accordance with regulatory requirements. | | : 2. Licensee Event Report 88-028 is currently being prepar ed and will be submitted to the NRC in accordance with the requirements of 10CFR50.73. |
| The Plant Operations Department, during the initial review of the Plant QA Surveillance Report, also failed to recognize the potential Technical Specification violation and;therefore, the reportability of the situation. | | Corrective Action to be Taken |
| Corrective Ste s Taken/Results Achieved 1.On July 5, 1988 an NCR was written by the Plant QA organization which documented the situation that the QA Surveillance Report had identified three examples where the heatup/cooldown rates may have been exceeded.The Plant Technical Compliance Group was aware of the NCR and recognized the need to perform a reportability evaluation. | | : 1. Plant QA Procedure PQA-03, "Conduct of QA Surveillances," will be revised to provide direction to evaluate deficiencies (findings) against PPM 1.3.12 to determine if an NCR is required. |
| However, due to the workload associated with scheduled commitments, the group was unable to evaluate the situation in a timely manner (the situation was determined to be reportable on August 23, 1988).2.Licensee Event Report 88-028 is currently being prepar ed and will be submitted to the NRC in accordance with the requirements of 10CFR50.73. | | : 2. Plant Licensing and Assurance Engineers will attend a review of this event and will be informed of their responsibility with regard to pr oblem report initiation in accordance with PPM 1.3.12. |
| Corrective Action to be Taken 1.Plant QA Procedure PQA-03,"Conduct of QA Surveillances," will be revised to provide direction to evaluate deficiencies (findings) against PPM 1.3.12 to determine if an NCR is required.2.Plant Licensing and Assurance Engineers will attend a review of this event and will be informed of their responsibility with regard to pr oblem report initiation in accordance with PPM 1.3.12.3.A review of the Plant Compliance organization has been completed. | | : 3. A review of the Plant Compliance organization has been completed. Several methods of improving the efficiency of the group have been identified and will be implemented. |
| Several methods of improving the efficiency of the group have been identified and will be implemented. | | Date of Full com liance |
| Date of Full com liance 1.Corrective Actions 1 and 2 will be completed by November 18, 1988.2.Corrective Action 3 will be implemented during FY 1989.}} | | : 1. Corrective Actions 1 and 2 will be completed by November 18, 1988. |
| | : 2. Corrective Action 3 will be implemented during FY 1989.}} |
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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
+CC~~~~GULANAkWAZAKDZQ~Z%VLLRRW(RZQ'~~~
ACCESSION NBR:8809290114 DOC.DATE: 88/09/23 NOTARIZED: NO DOCKET ¹
'FA'CIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 TH.NAME AUTHOR AFFILIATION ENSEN,G.C. Washington Public Power Supply System ECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) to NRC 880824 ltr re violations noted in Insp Rept l
SUBJECT:
Responds 50-397/88-21.Corrective actions:
DISTRIBUTION CODE'EOZD COPIES RECEIVED'LTR General (50 Dkt)-Insp Rept/Notice of ENCL Response Violation SIZE'ITLE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 PD 1 1 SAMWORTH R 2 2 INTERNAL: ACRS 2 2 AEOD DEDRO 1 1 NRR MORISSEAUPD NRR/DLPQ/PEB 11 1 1 NRR/DLPQ/QAB 10 NRR/DOEA DIR 11 1 1 NRR/DREP/EPB 10 NRR/DREP/RPB 10 2 2 NRR/DRIS DIR 9A NRR/PMAS/ILRB12 1 1 NUDOCS-ABSTRACT OE LXEBERMAN,J 1 1 OGC/HDS2 RE L 02 1 1 RES/DSIR DEPT RGK FILE 01 1 1 RNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25
C II
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 September 23, 1988 G02-88-205 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, D. C. 20555 Gentlemen:
Subject:
NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 NRC INSPECTION REPORT 88-21 The Washington Public Power Supply System her eby replies to the Notice of Violation contained in your letter dated August 24, 1988. Our reply, pursuant to the provision of Section 2.201, Title 10, Code of Federal Regulations, consists of this letter and Appendix A (attached).
In Appendix A, each violation is addressed with an explanation of our position regarding validity, corrective action and date of full compliance.
Very truly yours, G. . Sorensen, Manager Regulatory Programs cc: JB Martin - NRC RV NS Reynolds - BCPZR RB Samworth - NRC DL Williams - BPA, 399 NRC Site Inspector - 901A 88092901l4 880923 PDR ADOCK 05000397 6 PNU
Appendix A Page 1 of 3 APPENDIX A During an NRC inspection conducted on May 30 - July 7, 1988, the following violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, these violations are listed below:
A. Section 3.4.6.1 of the Technical Specifications states in part, "The reactor coolant system temperature and pressure shall be limited ..., with:
- a. A maximum heatup of 100 in any 1-hour period,..."
Con)rary to the above. a reactor coolant system heatup of approximately 137 F occurred during a plant startup on June 27, 1988.
This is a Severity Level IV Violation (Supplement I).
Validit of Violation The Supply System acknowledges the validity of this violation.
Corrective Ste s Taken/Results Achieved
- 1. Regarding exceeding the heatup limitation of Plant Technical Specification 3.4.6.1 on June 27, 1988:
a) Plant heatup was immediately terminated when determined to be excessive.
b) An Engineering evaluation was performed which concluded that no safety concerns were created by the excessive heatup r ate.
c) Plant Procedure 7.4.4.6.1.1, "RPV (Reactor Pressure Vessel)
Temperature/Pressure Log," was revised to provide additional guidance on control of Plant heatup and cooldown evolutions.
Significant changes made to prevent recurrence of this situation i'nclude:
~ heatup and cooldown rate is limited to 20 F during each 15 minute period.
~ heatup and cooldown rate is limited to 80 F per hour.
Appendix A Page 2 of 3 Pressure/Temperature
~ heatup/cooldown and RPV e Monitoring activities were divided into separ ate sections.
~ A steam table was provided to convert steam pressure (in PSIG) to temperature.
d) A heatup and cooldown program has been added to the Plant status display on the Control Room Process Computer CRT. The program graphically displays heatup/cooldown in relation to 80 F/hr reference lines. In addition, digital displays indicate projected heatup/cooldown rates based on 15, 30 and 45 minute temperature changes. This information is updated every 60 seconds. Digital displays are also provided for actual hour ly rates. An alar m functi~n is provided for both projected and actual rates when the 80 F/hr limit is exceeded.
- 2. Regarding the followup actions associated with the potential heatup/cooldown problems identified in Plant ()A Surveillance Report 2-88-018, Plant Operations failed to recognize the significance of the issue with regard to preventing recurrence due to lack of rigor and discipline in the initial review process.
Corrective Action to be Taken
- 1. Plant Oper ations Management will emphasize, to the Operations staff, the need for increased awareness and a more effective quality review of Plant gA Surveillance Reports.
- 2. General Operating Procedures, for Plant startup and shutdown evolutions, will )e revised to limit hourly heatup and cooldown rates to a maximum of 80 F.
Date of Full Com liance Although the Supply System is currently in full compliance, further corrective actions will be completed by October 31, 1988.
B. 10CFR50.73.d states in part, "Licensee Event Reports must be ... submitted within 30 days of discovery of a reportable event..."
Contrary to the above, the licensee identified in a ()A surveillance report issued on April 29, 1988 that the Technical Specification heatup and cooldown limits had been exceeded on February 20 and June 19, 1987, and did not issue a licensee event report within 30 days after this discovery.
This is a Severity level IV Violation (Supplement I).
Appendix A Page 3 of 3 Validit of Violation The Supply System acknowledges the validity of this violation. A definite determination that the Technical Specification limit had been exceeded was not provided in the QA Surveillance Report. Plant QA management had mistakenly determined that a Plant QA deficiency (finding) was the appropriate mechanism to initiate the reportability evaluation by the Plant personnel qualified and responsible for that function (e.g. Shift Manager or Plant Technical Compliance group). A Plant Nonconformance Report (NCR) should have been issued in accordance with Plant Procedure (PPM) 1.3.12, "Plant Problems." The purpose of the procedur is to provide instructions for the identification, documentation and disposition of Plant problems, and to ensure that each problem is reviewed for reportability in accordance with regulatory requirements.
The Plant Operations Department, during the initial review of the Plant QA Surveillance Report, also failed to recognize the potential Technical Specification violation and; therefore, the reportability of the situation.
Corrective Ste s Taken/Results Achieved
- 1. On July 5, 1988 an NCR was written by the Plant QA organization which documented the situation that the QA Surveillance Report had identified three examples where the heatup/cooldown rates may have been exceeded. The Plant Technical Compliance Group was aware of the NCR and recognized the need to perform a reportability evaluation. However, due to the workload associated with scheduled commitments, the group was unable to evaluate the situation in a timely manner (the situation was determined to be reportable on August 23, 1988).
- 2. Licensee Event Report 88-028 is currently being prepar ed and will be submitted to the NRC in accordance with the requirements of 10CFR50.73.
Corrective Action to be Taken
- 1. Plant QA Procedure PQA-03, "Conduct of QA Surveillances," will be revised to provide direction to evaluate deficiencies (findings) against PPM 1.3.12 to determine if an NCR is required.
- 2. Plant Licensing and Assurance Engineers will attend a review of this event and will be informed of their responsibility with regard to pr oblem report initiation in accordance with PPM 1.3.12.
- 3. A review of the Plant Compliance organization has been completed. Several methods of improving the efficiency of the group have been identified and will be implemented.
Date of Full com liance
- 1. Corrective Actions 1 and 2 will be completed by November 18, 1988.
- 2. Corrective Action 3 will be implemented during FY 1989.
