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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 ML16342A8811999-08-23023 August 1999 Forwards Emergency Response Data Sys (ERDS) Implementation Documents for Listed Plants.Changes Should Be Made to ERDS as Soon as Possible.Without Encl 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc PY-CEI-NRR-2377, Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 11999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys ML20207G8721999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating Licenses & Issuance of Conforming Amends & Opportunity for Hearing.Application Seeks Approval of Proposed Transfer of Dl Ownership Interests in BVPS ML20207G2611999-06-0707 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon IR 05000412/19980091999-05-26026 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-412/98-09 ML20195C4461999-05-21021 May 1999 Forwards Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Were Identified.Licensee Conduct of Activities at Beaver Valley Power Station Characterized by Safe Conduct of Activities During Refueling Outage ML20206P1241999-05-14014 May 1999 Refers to Proposed Changes Submitted by Dl on 990316 to BVPS QA Program Described in BVPS-2 Ufsar,Chapter 17.2.Forwards RAI Re Proposed QA Program Changes L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc PY-CEI-NRR-2377, Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 11999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS L-98-077, Informs of Change in Scheduled Completion Date for Commitments Made in LERs 98-020-00 & 98-020-01.Util Believes That Listed Change Does Not Represent Challenge to Plant Safety1999-05-0606 May 1999 Informs of Change in Scheduled Completion Date for Commitments Made in LERs 98-020-00 & 98-020-01.Util Believes That Listed Change Does Not Represent Challenge to Plant Safety L-99-072, Informs of Resignation of J Witter,License SOP-11376,from Employment at Bvps,Unit 2,per 10CFR50.74(b).Util Requests Withdrawal of Subject License1999-04-30030 April 1999 Informs of Resignation of J Witter,License SOP-11376,from Employment at Bvps,Unit 2,per 10CFR50.74(b).Util Requests Withdrawal of Subject License L-99-067, Forwards Rev 11 to UFSAR for Bvps,Unit 2, Replacement Pages.Submittal Reflects Changes to Facility & Procedures as Described in Ufsar,Completed During Annual Reporting Period Ending 9810311999-04-30030 April 1999 Forwards Rev 11 to UFSAR for Bvps,Unit 2, Replacement Pages.Submittal Reflects Changes to Facility & Procedures as Described in Ufsar,Completed During Annual Reporting Period Ending 981031 L-99-070, Requests Enforcement Discretion Re Compliance with TS 3.7.13.1 Action Statement,To Allow for Continued Plant Operation Beyond 7 Day Action Time for Sufficient Time to Complete Required Repairs & Perform Post Maint Testing1999-04-26026 April 1999 Requests Enforcement Discretion Re Compliance with TS 3.7.13.1 Action Statement,To Allow for Continued Plant Operation Beyond 7 Day Action Time for Sufficient Time to Complete Required Repairs & Perform Post Maint Testing ML20196F6711999-04-23023 April 1999 Requests That Proprietary Info Re LTOP Sys Setpoint Review for Bvps,Unit 2,15 EFPY Heatup & Cooldown Curves,Be Withheld from Public Disclosure IAW 10CFR2.790 L-99-055, Forwards Disk Containing Annual Exposure Rept for 1998. Attachment 1 Is Description of File Structure of Transmitted Data.Without Disk1999-04-0909 April 1999 Forwards Disk Containing Annual Exposure Rept for 1998. Attachment 1 Is Description of File Structure of Transmitted Data.Without Disk 05000334/LER-1998-015-01, Forwards LER 98-015-01, Inadequate Performance of Channel Functional Tests, Per 10CFR50.73(a)(2)(i).Restatement of Corrective Action Provided with Underlined Words to Clarify Intent1999-04-0606 April 1999 Forwards LER 98-015-01, Inadequate Performance of Channel Functional Tests, Per 10CFR50.73(a)(2)(i).Restatement of Corrective Action Provided with Underlined Words to Clarify Intent ML20206N3361999-04-0505 April 1999 Informs NRR of Continued Events Re Transfer of Generation Assets Between Duquesne Light Co & Firstenergy.No Negotiated Settlement Between Firstenergy & Local 270 Pertaining to Generation Asset Swap Has Been Reached L-99-051, Provides Response to NRC Request to Maintain Change That Was Proposed to Be Deleted in LAR 214 & 81,submitted 980709.New Marked Up TS Pages Are Encl1999-03-31031 March 1999 Provides Response to NRC Request to Maintain Change That Was Proposed to Be Deleted in LAR 214 & 81,submitted 980709.New Marked Up TS Pages Are Encl ML20205H6171999-03-29029 March 1999 Forwards Util Consolidated Financial Statements for Twelve Month Period Ending 981231 & Internal Cash Flow Projection, Including Actual 1998 Data & Projections for 1999 ML20205F6811999-03-19019 March 1999 Forwards Bvps,Units 1 & 2 Annual Radioactive Effluent Release Rept for CY98 & Revs to Offsite Dose Calculation Manual PY-CEI-NRR-2264, Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities1999-03-17017 March 1999 Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities L-99-042, Submits Info Concerning Property Damage Insurance Coverages for Site of BVPS Located in Borough of Shippingport,County of Beaver & Commonwealth of PA1999-03-16016 March 1999 Submits Info Concerning Property Damage Insurance Coverages for Site of BVPS Located in Borough of Shippingport,County of Beaver & Commonwealth of PA L-99-030, Forwards Response to Violations Noted in Insp Repts 50-334/98-09 & 50-412/98-09.Corrective Actions:Engineering Administrative Procedures Were Reviewed to Ensure That Design Analysis Process Contains Adequate Controls1999-03-0505 March 1999 Forwards Response to Violations Noted in Insp Repts 50-334/98-09 & 50-412/98-09.Corrective Actions:Engineering Administrative Procedures Were Reviewed to Ensure That Design Analysis Process Contains Adequate Controls ML20207E6531999-02-26026 February 1999 Provides Response to NRC 990204 RAI Re LAR 261,extending SG Surveillance Interval to Coincide with Thirteenth RFO or End of 500 Efpds,Whichever Is Sooner.Rev 0 to EMECH-0713-1 Re Operational Asssessment of SG Tubing,Encl L-99-034, Forwards Typed,Final TS Pages for LAR 111,as Requested by NRC Project Manager.Summary Description of Changes, Provided as Attachment B1999-02-26026 February 1999 Forwards Typed,Final TS Pages for LAR 111,as Requested by NRC Project Manager.Summary Description of Changes, Provided as Attachment B L-99-032, Requests to Withdraw Part of LARs 246 & 116,modifying Various Reporting Requirements Contained in TS Design Feature Section 5.1.Affidavit,encl1999-02-23023 February 1999 Requests to Withdraw Part of LARs 246 & 116,modifying Various Reporting Requirements Contained in TS Design Feature Section 5.1.Affidavit,encl L-99-013, Forwards Rev 11 to Chapter 57 of BVPS Emergency Preparedness Plan, Vol 1,per 10CFR50.4.Submittal Includes Info Re Implmentation of Severe Accident Management Guidelines.Changes Do Not Decrease Effectiveness of Plan1999-01-29029 January 1999 Forwards Rev 11 to Chapter 57 of BVPS Emergency Preparedness Plan, Vol 1,per 10CFR50.4.Submittal Includes Info Re Implmentation of Severe Accident Management Guidelines.Changes Do Not Decrease Effectiveness of Plan 1999-09-28
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Beav Valley Power Station Shippingport, PA 150774X)4 SUSHIL C. JAIN (41C WOM2 Senior vice er..ident September 2, 1999 Fax ; 2:,643-8069
$$7,$.*r*$ivi. ion L-99-098 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Units No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. DPR-73 Operations Quality Assurance Program Description Change In accordance with 10 CFR 50.54(a)(3)(ii), this letter forwards for NRC approval, a proposed change to the Beaver Valley Power Station (BVPS) Units I and 2 Operations Quality Assurance (QA) Program Description.*
This change would reduce the Operations QA Program Description commitments by limiting required Onsite Safety Committee (OSC) reviews of modifications and changes of safety related and non safety related items and proposed tests and experiments to those items requiring a completed 10 CFR 50.59 safety evaluation.
, further describes the proposed change, the reason for the change, and provides the basis for concluding that the revised program incorporating this change continues to satisfy the criteria of 10 CFR 50, Appendix B. presents the proposed wording changes to the Unit 2 UFSAR to reflect this change.
If you have any question regarding this submittal, please contact Mark S. Ackerman, Manager of Safety and Licensing in the Nuclear Services Group, at (412) 393-5203.
Sincerely,
,/
.' 'I I
9909130056 990902 PDR ADOCK 05000334 I
P PDR Sushil C. Jain DEllVERING I
' The Operations QA Program description for BVPS Unit I was deleted from the Unit I ggg(l7y Updated Final Safety Analysis Report (UFSAR)in January 1988 and the program description ENERGV for BVPS Units I and 2 is provided in Section 17.2 of the Unit 2 UFSAR.
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1 Beaver Valley Power Station, Unit No. I and No. 2 Operations Quality Assurance Program Description Change I
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Attachments -
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Mr. D. S. Collins, Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator i
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ATTACHMENT 1 PROPOSED CHANGE DESCRIPTION Unit 2 UFSAR' Section 17.2.3 regarding design control, currently specifies (in-part) that the Operations QA Program requires that all design changes of safety-related items shall be reviewed by the OSC and ORC (Offsite Review Committee) in accordance with the quality assurance program description and the requirements of the Operations QA Program. As part ofits responsibilities, the OSC now reviews all modifications and changes to the facility involving safety related items (i.e. those items that require a 10 CFR 50.59 screening or involve a 10 CFR 50.59 evaluation). The proposed change to
- Section 17.2.3 would allow the OSC to limit reviews of modifications and changes of safety related and non safety related items to those requiring a completed 10 CFR 50.59 evaluation. A change will also be made to Section 17.2.1.3 which will require the OSC to review those proposed tests and experiments and modifications and changes which require a completed 10 CFR 50.59 evaluation. In addition, the ORC would continue to meet the requirement in Section 17.2.1.4, to review proposed and completed changes to equipment or systems, regarding a potential or actual unreviewed safety question, as defined in 10 CFR 50.59.
REASON FOR THE PROPOSED CHANGE 4
OSC reviews now include modifications and changes that do not require a completed 10 CFR 50.59 safety evaluation and are, therefore, outside the realm of what could constitute an unreviewed safety question. Limiting these reviews would improve the OSC focus and effectiveness by better concentrating resources on issues important to j
nuclear safety. Additional benefits would include improved utilization of management personnel and other members of the plant staff serving on the OSC.
BASIS FOR CONCLUDING THAT THE REVISED PROGRAM INCORPORATING THE PROPOSED CHANGE WOULD CONTINUE TO SATISFY THE CRITERIA OF 10 CFR 50 APPENDIX B.
The proposed change is considered to be a reduction in commitment to the NRC, as it would no longer require the OSC to review all proposed changes or modifications to the plant systems or equipment. However, with the proposed change the OSC will continue to review proposed modifications and changes requiring a completed 10 CFR 50.59 evaluation. As such, the proposed change will not reduce the effectiveness of the Operations QA Program. In addition, since no changes were made to the Operations QA Program description that affect our commitments to 10 CFR 50, Appendix B, the Program will continue to satisfy 10 CFR 50, Appendix B.
ATTACHMENT 2 l
BVPS-2 UFSAR Revision (TBD)
The Operations QA Program provides measures to assure that changes or deviations from specified design requirements or quality standards are identified, documented, and controlled.
Design changes at BVPS after release and acceptance of design documents are subject to design control measures commensurate with those originally applied to the design. The Operations QA Program requires that, whenever practical, changes should be reviewed and approved by organizations that originally performed the review and approval of the design. In the event that it is not practical for the ariginal organizations to perform the required review and approval, other responsible organizations will be designated. The
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designated organization shall have access to pertinent background information, have competence in the specific design area ofinterest, and have adequate understanding of the requirements and intent of the original design.
Design documentation, inclading design review reports, specifications, drawings, and revisions thereto shall be collected, filed, stored, and maintained in a systematic manner.
The Operation: QA Progra:n require; th:1: All design changes of safety-related and non-safety-related items that reauire a completed 10 CFR 50.59 safety evaluation shall be reviewed by the OSC and the ORC in accordance with this quality assurance program description and the requirements of the Operations QA Program. Safety ev !uction: are condue:ed, : required by 10 CFR 50.59. OSC and ORC review of desian channes is discussed in Sections 17.2.1.3 and 17.2.1.4 of the Operations Ouality Assurance Program desciiotion.
17.2.4 Procurement Document Control i
ATTACHMENT 2 (Continued)
BVPS-2 UFSAR Rev. (TBD)
' 17.2.1.3 Onsite Safety Committee (OSC)
The OSC shall function to advise the General Manager, Nuclear Operations on all matters related to nuclear safety and shall provide review capability in the areas of:
1.
Nuclear power plant operations.
2.
Radiological safety.
3.
Maintenance.
4.
Nuclear engineering.
5.
Nuclear power plant testing.
6.
Technical advisory engineering.
7.
Chemistry.
8.
Quality control.
9.
Instrumentation and control.
The Onsite Safety Committee Coordinator is the OSC Chairman and shall appoint all members of the OSC. The membership shall consist of a minimum of one individual from each of the areas designated above.
OSC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3.
All alternate members shall be appointed in writing by the OSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSC activities at any one time.
The OSC shall meet at least once per calendar month and as convened by the OSC Chairman or his designated alternate. A quorum of the OSC shall consist of the Chairman or his designated alternate and at least one half of the members including attemates.
The OSC shall be responsible for:
1.
Review of a) all procedures required by Technical Specification 6.8 and changes of intent thereto, b) any other proposed procedures or changes thereto as determined by the General Manager, Nuclear Operations to affect nuclear safety.
2.
Review of all proposed tests and experiments that affect m:clea:-
safeef reauire a completed 10 CFR 50.59 safety evaluation.
3.
Review of all proposed changes to the Technical Specifications.
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BVPS-2 UFSAR Rev. (TBD) l 4.
Review of all proposed changes or modifications to plant systems or equipment that hmderr =fety reauire a completed 10 CFR 50.59 safety evaluation.
5.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the l
General Manager, Nuclear Operations and to the Chairman of the Offsite Review Committee.
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y ATTACHMENT 2 (Continued)
BVPS-2 UFSAR (Copy of this section provided FOR INFORMATION ONLY) 17.2.1.4 Offsite Review Committee (ORC)
The ORC shall function to provide independent review and audit of designated activities in the areas of:
1.
Nuclear power plant operations.
2.
Nuclear engineering 3.
Chemistry and radiochemistry 4.
Metallurgy 5.
Instrumentation and control 6.
Radiological safety 7.
Mechanical and electrical engineering 8.
Quality assurance practices The Chainnan and all members of the ORC shall be appointed by the President, Generation Group and Chief Nuclear Officer. The membership shall consist of a minimum of five individuals who collectively possess a broad based level of i
experience and competence enabling the committee to review and audit those i
activities designated above and to recognize when it is necessary to obtain technical advice and counsel. An individual may possess expertise in more than one specialty area.
The collective competence of the committee will be maintained as changes to the membership are made.
All alternate members shall be appointed in writing by the ORC Chairman or a member of Beaver Valley Power Station executive management to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time. Consultants shall be utilized as determined by the ORC Chainnan to provide expert advice to the ORC.
The ORC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter. A quorum of the ORC shall consist of the Chairman or his designated alternate and at least four members including nitemates.
No more than a i
minority of the quorum shall have line responsibility for operation of the facility.
The ORC shall review:
1.
The safety evaluations for a) changes to procedures, equipment or systems and b) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
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s ATTACHMENT 2 (Continued)
BVPS-2 UFSAR 2.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as dermed in Section 50.59, 10 CFR.
3.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59,10 CFR.
4.
Proposed changes in Technical Specifications or licenses.
5.
Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
6.
Significant operating abnormalities or deviations from nonnal and expected performance of plant equipment that affect nuclear safety.
7.
All reportable events of the type described in 10 CFR 50.73.
8.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.
j 9.
Reports and meeting minutes of the OSC.
10.
The results of the Radiological Environmental Monitoring Program i
annual report provided in accordance with Technical Specification 6.9.1.10, prior to submittal.
.