ML17272A690
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| ML17272A690 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/18/1979 |
| From: | RENBERGER D L WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | ENGELKEN R H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML17272A691 | List: |
| References | |
| GO2-79-191, NUDOCS 7910230482 | |
| Download: ML17272A690 (3) | |
Similar Documents at Columbia | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17284A9041999-10-19019 October 1999
[Table view]Forwards FEMA Evaluation Rept for out-of-sequence Washington State Lab & Food Control Drills for Washington Nuclear Power Project 2.Rept Indicates That FEMA Did Not Identify Any Deficiences or Areas Requiring C/A During Drills IR 05000397/19990111999-10-19019 October 1999 Forwards Insp Rept 50-397/99-11 on 990927-1001.No Violations Noted.Licensee Inservice Exam Program Plan for Second 10-year Interval for Washington Nuclear Project-2 Facility Well Defined ML20217K9681999-10-19019 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 ML17284A8951999-10-18018 October 1999 Forwards SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at WNP-2 & That Licensee Adequately Addressed Actions Requested in GL-96-05 ML17284A9011999-10-15015 October 1999 Advises That WNP-2,OL NPF-21,request for Amend Re MCPR Safety Limits (Addl Info Channel Bow),Dtd 990830,marked Proprietary,Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) GO2-99-182, Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.51999-10-14014 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 GO2-99-173, Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl1999-09-24024 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 ML17284A8821999-09-24024 September 1999 Forwards Insp Rept 50-397/99-09 on 990725-0904.Three Violations Identified & Being Treated as Noncited Violations GO2-99-174, Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-21999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7571999-09-23023 September 1999 Informs of Completion of Licensing Activity for Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in BWRs for Facility GO2-99-172, 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 & 3981999-09-22022 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 ML17292B7561999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WNP-2 on 990818 & Found No Areas in Which Licensee Performance Warranted Addl Insp Effort Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl GO2-99-169, Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS1999-09-0909 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) GO2-99-166, 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 9912011999-08-30030 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 ML17284A8771999-08-30030 August 1999 Advises That Addl Info on MCPR Safety Limits for Cycle 15 Operation,Submitted with Util ,Will Be Withheld from Public Disclosure,Per 10CFR2.790 GO2-99-164, 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 Withheld1999-08-30030 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 GO2-99-165, 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 51999-08-30030 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 GO2-99-162, Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)1999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) GO2-99-163, Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 9910061999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 GO2-99-158, 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 Encls1999-08-19019 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 ML17284A8651999-08-13013 August 1999 Forwards Insp Rept 50-397/99-08 on 990613-0724.One Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy GO2-99-155, Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety1999-08-12012 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 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 ML17284A8611999-08-10010 August 1999 Forwards SE Accepting & Suppls & 0702 Re Exam Results of Reactor Recirculation Sys Suction Nozzle to safe-end weld,24RRC(2)A-1 & Associated Flaw Evaluation for Detected Flaw for WNP-2 ML17284A8571999-08-0404 August 1999 Forwards Notice of Withdrawal of Application for Amend to License NPF-21,per .Proposed Change Would Have Modified TSs Pertaining to Secondary Containment Drawdown Time & Secondary Containment Bypass Leakage 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 GO2-99-149, 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 Withheld1999-08-0202 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 GO2-99-148, 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 20011999-07-30030 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 ML17284A8291999-07-26026 July 1999 Forwards Suuplemental Request for Addl Info Re Minimun Critical Power Ratio Amend Application for Plant.Mutually Agreeable Target Date for RAI Established for 990804 GO2-99-139, 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,Encl1999-07-22022 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 GO2-99-397, 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 Counties1999-07-20020 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 ML17292B7401999-07-20020 July 1999 Discusses WPPSS Request That Addl Info Submitted on 990525 on MCPR Safety Limits for WNP-2 Cycle 15 Operation Be with- Held from Public Disclosure.Determined Info Proprietary & Will Be Withheld from Public Disclosure Per 10CFR2.790 GO2-99-133, 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 9911121999-07-16016 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 ML17292B7371999-07-15015 July 1999 Informs That NRC Has Reviewed Encl Computer Access & Operating Agreement & Find Terms & Conditions Satisfactory ML17292B7321999-07-14014 July 1999 Forwards Exemption from Requirements of 10CFR55.59 Re Operator Requalification Program ML17292B7291999-07-13013 July 1999 Forwards Insp Rept 50-397/99-05 on 990607-11.No Violations Noted ML17284A8641999-07-13013 July 1999 Advises That as Result of Review of Responses to GL 92-01, Rev 1,Suppl 1 & Suppol 1 Rai,Nrc Revised Info in Rvid & Releasing Info as Rvid Version 2.NRC Efforts in Regard to TAC MA1213 Closed GO2-99-128, Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls1999-07-12012 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 ML17292B7241999-07-0909 July 1999 Forwards Insp Rept 50-397/99-07 on 990502-0612.Two Violations Noted & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy GO2-99-123, Provides Notification of Early Completion on 990630 of Exception Noted in .Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready1999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in .Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready GO2-99-122, Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO1999-07-0202 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 GO2-99-121, Forwards Addl Info Requested in to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves1999-06-30030 June 1999 Forwards Addl Info Requested in to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves GO2-99-117, Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps1999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps ML17292B7081999-06-23023 June 1999 Forwards Request for Addl Info Re 990324 Planar Indication Found on Weld Number 24RRC(2)A-1 for Washington Public Power Supply Sys Nuclear Project 2 ML17292B7071999-06-23023 June 1999 Forwards Request for Addl Info Re 990420 Amend Request Re Pressure Temperature Limit Curves for Washington Public Power Supply Sys Nuclear Project 2 GO2-99-113, Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.7901999-06-21021 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 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARGO2-99-182, Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.51999-10-14014 October 1999
[Table view]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 GO2-99-174, Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-21999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 GO2-99-173, Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl1999-09-24024 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 GO2-99-172, 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 & 3981999-09-22022 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 GO2-99-169, Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS1999-09-0909 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) GO2-99-166, 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 9912011999-08-30030 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 GO2-99-165, 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 51999-08-30030 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 GO2-99-164, 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 Withheld1999-08-30030 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 GO2-99-162, Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)1999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) GO2-99-163, Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 9910061999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 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 GO2-99-158, 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 Encls1999-08-19019 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 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 GO2-99-155, Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety1999-08-12012 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 GO2-99-149, 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 Withheld1999-08-0202 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 GO2-99-148, 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 20011999-07-30030 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 GO2-99-139, 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,Encl1999-07-22022 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 GO2-99-397, 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 Counties1999-07-20020 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 GO2-99-133, 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 9911121999-07-16016 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 GO2-99-128, Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls1999-07-12012 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 GO2-99-123, Provides Notification of Early Completion on 990630 of Exception Noted in .Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready1999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in .Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready GO2-99-122, Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO1999-07-0202 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 GO2-99-121, Forwards Addl Info Requested in to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves1999-06-30030 June 1999 Forwards Addl Info Requested in to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves GO2-99-117, Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps1999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps GO2-99-113, Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.7901999-06-21021 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 GO2-99-110, Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls1999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls GO2-99-107, 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,Encl1999-06-10010 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 GO2-99-103, Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs1999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs GO2-99-101, 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 Activities1999-06-0101 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 GO2-99-100, 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 10CFR2.7901999-05-25025 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 GO2-99-099, 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 Date1999-05-25025 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 GO2-99-088, 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 Facility1999-05-0707 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 GO2-99-086, Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.7901999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 GO2-99-083, 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 Exam1999-04-29029 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 GO2-99-084, Forwards Rept of Individual Monitoring for 1998 Cy,As Required by 10CFR20.2206(b)1999-04-29029 April 1999 Forwards Rept of Individual Monitoring for 1998 Cy,As Required by 10CFR20.2206(b) GO2-99-074, Responds to NRC Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security1999-04-19019 April 1999 Responds to NRC 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 GO2-99-068, Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests1999-04-13013 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 GO2-99-067, Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS1999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS GO2-99-062, 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 Schedule1999-04-0606 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) GO2-99-057, 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 Indication1999-03-24024 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 GO2-99-051, 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 Encls1999-03-16016 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 GO2-99-052, 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 Question1999-03-16016 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 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) GO2-99-053, 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 Achievement1999-03-16016 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 GO2-99-049, Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted1999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted GO2-99-042, Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.11999-03-0101 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 1999-09-09 Category:UTILITY TO NRC MONTHYEARML17286A2801990-08-27027 August 1990
[Table view]Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) GO2-90-141, 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 Inspectors1990-08-23023 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 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 GO2-90-138, Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee1990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee GO2-90-136, 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 Revised1990-08-10010 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 GO2-90-133, Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns1990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns GO2-90-131, Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per . Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys1990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per . Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys GO2-90-130, 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 Specs1990-07-27027 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 GO2-90-124, Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring1990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring GO2-90-125, 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 Completed1990-07-12012 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 GO2-90-123, 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 Occur1990-07-11011 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 GO2-90-122, Forwards Util 1990 Emergency Exercise Scenario.W/O Encl1990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl GO2-90-118, 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 Manager1990-07-0505 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 GO2-90-116, 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 Environ1990-06-29029 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 ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) GO2-90-113, 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 Actions1990-06-28028 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 GO2-90-110, Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed1990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed GO2-90-108, 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 Instead1990-06-20020 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 GO2-90-109, Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval1990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval GO2-90-107, 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 Conditions1990-06-19019 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 GO2-90-106, Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 9006011990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 GO2-90-105, 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 Cycle1990-06-15015 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 GO2-90-103, Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty1990-06-12012 June 1990 Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty GO2-90-098, Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 9007011990-06-0707 June 1990 Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701 GO2-90-095, Responds to NRC Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons1990-05-29029 May 1990 Responds to NRC 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 GO2-90-094, Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 19911990-05-22022 May 1990 Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991 GO2-90-093, Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util .W/O Encl1990-05-11011 May 1990 Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util .W/O Encl GO2-90-087, Advises That No Changes to Tech Specs Required as Stated in in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS1990-05-0101 May 1990 Advises That No Changes to Tech Specs Required as Stated in in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS GO2-90-081, Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered1990-04-26026 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 GO2-90-080, Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-171990-04-25025 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 Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed GO2-90-074, Responds to NRC 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 Fundamentals1990-04-11011 April 1990 Responds to NRC 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 GO2-90-068, 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,Respectively1990-04-0505 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 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 GO2-90-069, Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-211990-04-0505 April 1990 Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21 GO2-90-067, Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-04-0404 April 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) GO2-90-062, 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 9003121990-03-29029 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 GO2-90-061, 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 19921990-03-29029 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 GO2-90-063, 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 Results1990-03-29029 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 GO2-90-060, Responds to NRC 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 Insps1990-03-23023 March 1990 Responds to NRC 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 GO2-90-058, 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 Exception1990-03-21021 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 GO2-90-057, 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 Sys1990-03-19019 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 GO2-90-056, 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 19901990-03-19019 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 GO2-90-050, Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement1990-03-15015 March 1990 Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement GO2-90-035, 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 Indicators1990-03-0202 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 GO2-90-034, Responds to NRC 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 Guide1990-03-0202 March 1990 Responds to NRC 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 GO2-90-033, Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-011990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 1990-08-27 |
Text
REGULATORY ORMATION DISTRIBUTION SY M (RIDS)ACCESSIPA NBR:7910230482 DOC~DATE: 79/10/18 NOTARIZED; NODOCKET FACIL.50-397
'WPPSS Nuclear Pro]ect~Unit 2~PIashington Public Powe 05000397 AUTH, NAME AUTHOR AFFILIATION RENBERGER,D,L.
washington Public Power Supply System RECIP~NAME'ECIPIENT AFFILIATION ENGELKENtR
~Hs Region 4i Dallas~Office of the Director
SUBJECT:
Forwards interim deficiency rept re spent fuel pool coo'Iing sys~oIsTRISUTioN coDE,;so>9s covIss REcsIYEo:LTR I, EscL g sIzsi L 4 J'ITLE: Construction Deficiency Repor t (10CFR50,55E)
NOTES;2 C++L I MAT L.WWWMSIWS\0 MWMORMM\O~M~MWtMWMW 00\04$0$00%%%&WOMW~OWWMWQ\WWWW\fWWM&WO4'IA RECIPIENT COPIES ID CODE/NAME LTTR ENCL ACTION: 14 PM~I-/AC H]20 LAl RECIPIENT COPIES ID CODE/NAME LTTR ENCL 15 BCL-~~M Q 1 1 21 AD L~~1 1 INTERNAI: 05 ISE 08 NPA 10 QAB 12 JORDANgE/IE 16 AD FOR ENGR 17 AD REAC SFTY 23 OELD DIRECTOR DSE I&C SYS BR MECH ENG BR S HANAUER F 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 02 NRC PDR 07 EDO L STAFF 09 DEPY DIR DPN 11 STANDRDS DEV 13F IELD COOR/IE 17 AD PLANT SYS 22 DIR DPM AD/SITE TECH GEOSC IENCES BR NATL ENG BR PONER SYS BR STRUCT ENG BR 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EXTERNAL: 03 LPDR 24 ACRS 1 1 1 6 16 04 NSIC 0g g4>9't9 89 TOTAL NUMBER OF COPIES REQUIRED: LTTR~NCI 8?tt(~
J II ll p Washington Public Power Supply System A JOINT OPERATING AGENCY P.O.8OX 9ee 3OOO 0CO.W*SHINCYON WAY RICHLAND, WASHINGTON 99352 PHONC (509)375 5000/October 18, 1979 G02-79-191 Nuclear Regulatory Commission Region V Office of Inspection and Enforcement Suite 202, Walnut Creek Plaza 1900 N.California Boulevard Walnut Creek, California 94596 Attention:
Mr.R.H.Engelken, Director
Subject:
WPPSS NUCLEAR PROJECT NO.2 DOCKET NUMBER 50-397, CPPR-93 REPORTABLE DEFICIENCY
-10CFR50.55(e)
Dear Mr.Engelken:
In accordance with the provisions of 10CFR50.55(e), your staff was informed by telephone on September 21, 1979, of a reportable condition involving the spent fuel, pool cooling system which is not designed to Seismic Category 1 standards.
Attached is our report of this deficiency.
Action to correct this condition is currently being evaluated.
A final report of action taken will be forwarded to your office before November 30, 1979.Please contact us if you have additional questions.
Very truly yours, DLR/GLC/jdb
Attachment:
As stated D.L.RENBERGER Assistant Director Technology cc: JJ Verderber-B&R, w/att JJ Byrnes-B&R, w/att JR Lewis-BPA, w/att JG Davis, Director, NRC, Washington, D.C., w/att WNP-2 Files, w/att>910230 Q p g
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