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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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hv Valley Power Station Shippingport, PA 15077-0004
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n or V) President June 25, 630 Fax 724) 643-Do*0.**E,w. ion L-99-093 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to Request for AdditionalInformation on Proposed Change to the Operations Quality Assurance Program Description By letter dated March 16,1999, Duquesne Light Company (DLC) submitted for NRC approval in accordance with 10 CFR 50.54(a)(3)(ii), a proposed change to the Beaver Valley Power Station (BVPS) Units 1 and 2 Operations Quality Assurance (QA) Program Description provided in BVPS Unit 2 Updated Final Safety Analysis Report, (UFSAR) Chapter 17.2. In its letter, DLC stated that this change would reduce the program description commitments for both Units by limiting required Onsite Safety Committee (OSC) reviews of procedures to those requiring a 10 CFR 50.59 safety evaluation.
Subsequently, in their review of this submittal, the NRC determined that additional information is required from DLC in order for the NRC to complete their review. By letter dated May 14,1999, the NRC provided to DLC a request for additional information (RAI) concerning its proposed change to the QA Program Description. In their letter the NRC requested this response to the RAI be provided by July 13, 1999.
The BVPS response to the RAIis provided in Attaclunent 1. provides the revised markup for proposed changes to affected UFSAR 17.2.5, which supersede those previously proposed for this section in DLC's March 16,1999
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submittal. In addition, Attachment 2 includes the markup of previously proposed changes to UFSAR Section 17.2.1.3, which remain unchanged by this submittal.
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1 iBeaver Valley Power St tion, Unit No. I and No. 2 Response to Request for Additional Infonnation on Proposed Change to Operations Quality Assurance Program Description Page 2 Following NRC approval of this proposed change to the Operations QA Program description, the transition from our current procedure review and approval process to the IQR process will be conducted in a deliberate and controlled manner.
The fmal step in this transition will be implementation of the proposed UFSAR changes, as outlined in this subittal.
If there are any questions concerning this matter, please contact Mr. Mark S. Ackerman, Manager, Safety & Licensing Department at 412-393-5203.
Sincerely, Sushil C. Jain Attachment c:
Mr. D. S. Collins, Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator
7 i
ATTACHMENT 1 Duquesne Light Company Beaver Valley Power Station Units 1 and 2 NRC Reauest for Additional Information. dated May 14.1999 NRC Request:
Duquesne Light Company (DLC) has proposed to limit required Onsite Safety Committee (OSC) reviews of new procedures, and procedure revisions, to those requiring a 10 CFR 50.59 safety evaluation. All other procedural reviews would be performed by an independent qualified reviewer (IQR) and approved by the responsible discipline manager or his/her designee. While this proposed procedural review alternative is not unprecedented, the existing QA Program for BVPS-1 and BVPS-2 does not explicitly define, in UFSAR Chapter 17.2 of the BVPS-2, the requisite qualifications, authority, and review responsibility of an IQR (as described in Attachment I to the March 16,1999 letter). Additionally, the QA Program contains no discussion of how the population of designated IQRs is to be controlled or tracked. Please provide appropriate revisions of the QA Program which incorporate this information and support the QA Program change requested in your March 16,1999 submittal.
DLC Response:
Reauisite Oualifications of an IOR IQRs shall meet the applicable qualifications of ANSI /ANS 18.1-1971, for a Staff Specialist.
IQRs shall be qualified to perform 10 CFR 50.59 safety evaluations.
Authority and Review Responsibilities of an IOR Each procedure or revision thereto of Technical Specification 6.8 shall be reviewed and approved, as described below, prior to implementation.
Each procedure or revision thereto shall be reviewed by an IQR, who is knoveledgeable in the functional area affected. This IQR is not the individual who prepared the procedure or associated procedure revision. Required cross disciplinary reviews of new procedures and procedure revisions shall be completed prior to approval of the procedure. The responsible IQR shall ensure each procedure or revision thereto includes a determination of whether a procedure requires a 10 CFR 50.59 safety evaluation. If a procedure or revision thereto requires a 10 CFR 50.59 safety evaluation, the responsible Manager or his designee shall forward the procedure, with the associated 10 CFR 50.59 safety evaluation, to the OSC for review. Pursuant to 10 CFR 50.59, NRC approval ofitems involving unreviewed safety questions shall be obtained prior to approval of the procedure or revision thereto for implementation. Final procedure approval shall be by the responsible Manager or his designee as specified in administrative procedures.
Discussion of How the Population of Designated IORs is to be Controlled or Tracked Personnel reconunended to be IQRs shall be reviewed by the OSC and approved and documented by the Plant Manager as specified in administrative procedures. The responsible Manager shall ensure that procedures or revisions thereto are reviewed by an IQR knowledgeable in the functional area prior to approval.
i ATTACHMENT 2
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Duquesne Light Company Beaver Valley Power Station Units 1 and 2 NRC Reauest for Additional Information. dated May 14.1999 BVPS-2 UFSAR Revision (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 b: 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 alternates.
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ATTACHMENT 2 (continued)
Duquesne Light Company Beaver Valley Power Station Units 1 and 2 NRC Reauest for Additional Information. dated May 14.1999 BVPS-2 UFSAR Revision (TBD)
The OSC shall be responsible for:
- 1. ~ Review of newa) :1! precedures required by Technical Specif::: ica 6.8 =d ch=ge: cf int = i=etc, b) =y cder p cpc:ed procedures reauirina 10 CFR 50.59 safety evaluations ander changes to existina procedures deretc which reauire 10 CFR 50.59 safety evaluations. : det:nained by 6: C===! M= gn. Nu !:= Op= tion: to afrect nn:!:= safety-2.
Review of all proposed tests and experiments that affect nuclear safety.
j 3.
Review of all proposed changes to the Technical Specifications.
4.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
]
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 General Manager, Nuclear Operations and to the Chairman of the Offsite Review Committee.
6.
Review of all reportable events of the type described in 10 CFR 50.73.
7.
Review of facility operations to detect potential safety hazards.
8.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Offsite Review Committee.
9.
Review cfie Security P!= =d implementing precedure:.
- 10. Review ofie E==gency Pl= =d imp!cmenting procedures.
The OSC shall:
1.
Recommend to the General Manager, Nuclear Operations written approval or disapproval ofitems considered under OSC responsibility 1 through 4 above.
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g ATTACHMENT 2 (continued)
Duquesne Light Company Beaver Valley Power Station Units 1 and 2 NRC Reauest for Additional Information. dated May 14.1999 BVPS-2 UFSAR Revision (TBD) l l
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- 2. Render determinations in writing with regard to whether or not each item considered under OSC responsibility 1 through 5 above constitutes an unreviewed safety question.
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- 3. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> te die President, Generation Group and
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Chief Nuclear Officer and the Offsite Review Conunittee of disagreement between the l
OSC and the General Manager, Nuclear Operations; however, the General Manager, L
Nuclear Operations shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.
l The OSC shall maintain written minutes of each meeting and copies shall be provided to the l
General Manager, Nuclear Operations and Chairman of the Offsite Review Committee.
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ATTACHMENT 2 (continued)
Duquesne Light Company Beaver Valley Power Station Units 1 and 2 NRC Request for Additional Information, dated May 14.1999 BVPS-2 UFSAR Revision (TBD) 17.2.5 Instructions, Procedures, and Drawings The Operations QA Program requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and will be accomplished in accordance with these instructions, procedures, or drawings.
These instructions, procedures, or drawings include, as appropriate, the requirements for special tools, test equipment, processes, controls, or skills, in order to attain the required level of quality.
The instructions, procedures, or drawings will include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
The Beaver Valley Power Station Operating Manual includes instructions and procedures covering the requirements of NRC Regulatory Guide 1.33, " Quality Assurance Program Requirements (Operations)", Appendix A, as they apply to Pressurized Water Reactors. The Operating Manual is implemented, enforced, and maintained by the General Manager, Nuclear Operations Unit, and staff. These procedures and/or instructions include step-by-step procedures for operating and securing the various systems, actions to be taken in the event of abnormal or emergency conditions and precautions to preclude exceeding system or equipment design. The applicable requirements of NRC Regulatory Guide 1.33 were used as guidance in the development of startup, operating, emergency, maintenance, and testing procedures.
Maintenance, repair, modifications, testing, and refueling activities which affect the quality or safety of Category I items are prescribed by documented instructions, procedures, or drawings.
These instructions, procedures, or drawings include, as appropriate, the requirements for special tools, test equipment, processes, controls, or skills, in order to attain the required level of quality.
Each procedure or revision thereto of Technical Specification 6.8 shall be reviewed and approved.
as described below. orior to implementation.
Each procedure or revision thereto shall be reviewed by an Independent Oualified Reviewer (IORL who is knowledaeable in the functional area affected. This IOR is not the individual who prepared the procedure or associated procedure revision. Reauired cross disciplinary reviews of new procedures and procedure revisions shall be completed prior to approval of the procedure.-
The responsible IOR shall ensure each procedure or revision thereto includes a determination of whether a procedure reauires a 10 CFR 50.59 safety evaluation. If a procedure or revision thereto I
reauires a 10 CFR 50.59 safety evaluation, the responsible Manauer or his desinnee shall forward the procedure. with the associated 10 CFR 50.59 safety evaluation. to the OSC for review.
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l, ATTACHMENT 2 (continued)
)
Duquesne Light Company j
Beaver Valley Power Station Units 1 and 2 l
NRC Reauest for Additional Information. dated May 14.1999 t
l BVPS-2 UFSAR Revision (TBD) l Pursuant to 10 CFR 50.59. NRC approval ofitems involving unreviewed safety auestions shall be 1
obtained orior to approval of the procedure or revision thereto for implementation. Final procedure approval shall be by the responsible Manager or his desinnee as specified in l
administrative procedures. IORs shall meet the applicable aualifications of ANSI /ANS 18.1-1971. for a Staff Specialist. IORs shall be analified to perform 10 CFR 50.59 safety evaluations.
Personnel recommended to be IORs shall be reviewed by the OSC and aooroved and documented by the Plant Mananer as specified in administrative procedures. The responsible Manager shall ensure that procedures or revisions thereto are reviewed by an IOR knowledgeable in the functional area prior to aoproval.
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procedure i: pe-formed '; hall receive = indep=d=: review by a q=liEed individu:1 =d eppreved by a deig=ted== ger er diacter Temporary channes to procedures will be approved by two knowledaeable members of the Beaver a
l Vallev staff prior to implementation. At least one of these will be a member of supervision. If the change affects operations procedures. at least one will be a person holding a senior reactor l
operator license for the unit affected. Prior to implementation, the OSC shall review and L
recommend approval of temporary channes to procedures which reauire a 10 CFR 50.59 safety evaluation. Within 14 days ofimplementation. temporary channes will be reviewed by an indeoendent aualified reviewer and approved by the responsible mananer or his desinnee.
1 l
T =per=y ch=ge'; to precedure of Techni=1 Spee!E=ti= 6.8.1 may be made provideo 1.
The int =: cfie crigi=1 p=cedum is not 01:ered.
2.
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