Letter Sequence RAI |
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MONTHYEARML20141H4411997-05-19019 May 1997
Forwards RAI Re Plant,Units 1 & 2 10CFR50.46 Annual Rept Providing Notification of Changes or Errors in Units 1 & 2 LOCAs
Project stage: RAI
ML20199A2621997-11-0505 November 1997
Informs That NRC Staff Reviewed Dlc Assessments of Changes BVPS-1 & BVPS-2 large- & small-break LOCA Licensing Models as Submitted on 960926,970321 & 971010.Agrees W/Dlc Conclusion That Reanalyses Are in Order & Accepts Schedule
Project stage: Approval
1997-11-05
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999
Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System
ML20217M1591999-10-19019 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
L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999
Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct
L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999
Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections
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
L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program
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
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
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
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
L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999
Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC
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-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999
Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)
L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999
Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls
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-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999
Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3
L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999
Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl
L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999
Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B
L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999
Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change
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
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-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999
Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001
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-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999
Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by
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-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999
Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl
L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999
Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6
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
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-99-108, 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-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl
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
L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999
Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages
1999-09-08
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARIR 05000412/19990071999-10-21021 October 1999
Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System
ML20217M1591999-10-19019 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
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
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
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
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
ML20207G2611999-06-0707 June 1999
Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart
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
ML20206N3161999-05-0606 May 1999
Responds to Ltr to NRC on Continued Events Re Transfer of Generation Assets Between Dl & Firstenergy.Info Will Be Considered as NRC Monitor Pending License Transfer Application of Bvps,Units 1 & 2 & Pnpp
ML20206H7931999-04-30030 April 1999
Ack Receipt of 990426 Request for Enforcement Discretion & 990427 Withdrawal of Request for Enforcement Discretion. Resolution Documented.Enforcement Discretion Not Necessary
ML20206B2751999-04-22022 April 1999
Forwards Insp Repts 50-334/99-01 & 50-412/99-01 on 990207- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy
ML20206A8381999-04-20020 April 1999
Forwards Reactor Operator Initial Exam Rept 50-412/99-301 on 990322-25.All Three Reactor Operator Applicants Passed. Initial Written Exam Submittal Was Determined Not to Meet NRC Guidelines in Certain Instances
ML20205R9071999-04-20020 April 1999
Forwards Second Request for Addl Info Re Response to GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves, for Beaver Valley Power Station,Units 1 & 2
ML20205Q8311999-04-14014 April 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-334/98-11 & 50-412/98-11 Issued on 990225.Actions Will Be Examined During Future Insp of Licensed Program
ML20205L0341999-04-0909 April 1999
Forwards SER Accepting Util 971209 & 980729 Submittal of Second 10-year Interval ISI Program Plan & Associated Relief Requests for Beaver Valley Power Station,Unit 2.TER Also Encl
ML20205P2431999-04-0909 April 1999
Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Ltr Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival
ML20205K0901999-04-0505 April 1999
Informs of Individual Exam Result on Initial Retake Exam Conducted on 990322-25 at Licensee Facility.Three Individuals Were Administered Exam & All Three Passed. Forwards Encl Re Exam.Without Encl
ML20205R1791999-03-30030 March 1999
Responds to Issue Re Generic Implication of part-length Control Rod Drive Mechanism Housing Leak at Praire Island, Unit 2 & Beaver Valley Power Station,Units 1 & 2
ML20205C0301999-03-26026 March 1999
Informs That Util Responses to GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps Acceptable
ML20204D7371999-03-16016 March 1999
Advises That RW Lindsey Authorized to Administer Initial Written Exams to Sh Cencic,Tf Lardin & Ta Pittas on 990322. Region I Operator Licensing Staff Will Administer Operating Tests
ML20207E0201999-02-25025 February 1999
Forwards Insp Repts 50-334/98-11 & 50-412/98-11 on 981227- 990206 & Forwards Notice of Violations Re Uncontrolled Reduction of Main Condenser Vacuum
ML20203D0691999-02-10010 February 1999
Forwards SE Accepting Approval of Proposed Revs to Plant QA Program Description in Chapter 17.2 of Updated Fsar,Per Util 981224 Submittal
ML20206U3011999-02-0505 February 1999
Forwards Insp Repts 50-334/98-09 & 50-412/98-09 on 981116-1217 & Nov.Violation Identified Re Inadequate Design Control in Unit 2 Dc Voltage Drop Calculation
ML20203A0811999-02-0404 February 1999
Forwards Request for Addl Info Re Review of Beaver Valley Power Station,Unit 1 License Amend to Allow one-time Extension of Steam Generator Insp Interval
ML20199E6681999-01-14014 January 1999
Forwards RAI Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant,Units 1 & 2
ML20199F1961999-01-13013 January 1999
Forwards Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Informs That Overall Fire Protection Program Functioning Well
ML20199F5101998-12-29029 December 1998
Discusses Third 10-year Interval ISI Program Plan & Associated Relief Requests for BVPS-1 Submitted by Dlc on 970917 & 980618.Informs That NRC Has Adopted Ineel Recommendations in TER INEEL-98-00893.Forwards SE & TER
ML20198K5911998-12-24024 December 1998
Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls
ML20198K8251998-12-21021 December 1998
Forwards SER Granting Licensee 980611,as Suppl 981015 Pump Relief Request PRR-5 for Third 10-year IST Interval for Beaver Valley Power Station,Unit 1 Pursuant 10CFR50.55(a)(f)(6)(i)
ML20198B1301998-12-0909 December 1998
Advises of Planned Insp Effort Resulting from Beaver Valley Power Station mid-year Insp Resource Planning Meeting Held on 981110.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl
ML20198A1301998-12-0909 December 1998
Forwards SE Re USI A-46 Program Implentation for Plant Unit 1.Staff Concludes Program Implementation Met Purpose & Intent of Criteria in Generic Implementation Procedure 2 & Suppl SER 2 for Resolution of USI A-46
ML20196J2761998-12-0404 December 1998
Forwards Corrected Pages 17 & 18 of NRC Integrated Insp Repts 50-334/98-06 & 50-412/98-06 for Exercise of Enforcement Discretion
ML20196H3051998-12-0202 December 1998
Forwards Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Conduct of Activities at Beaver Valley Power Station Facilities Characterized by Safe Plant Operations
ML20196H2781998-12-0202 December 1998
Forwards Insp Repts 50-334/98-08 & 50-412/98-08 on 981026- 30.No Violations Noted.Plant Operations Witnessed by Team Were Conducted in Safe & Controlled Manner
ML20196G9921998-12-0101 December 1998
Forwards Ltrs from Fk Koob, to JW Pack & CF Wynne Re Plant Deficiencies Assessed During 981006 Exercise Against Hancock County,Wv & Beaver County,Pa,Respectively
ML20196D4371998-11-25025 November 1998
Discusses Concerns Re Announced Asset Transfer Between Firstenergy Corp & Duquesne Light Co
ML20196A7101998-11-24024 November 1998
Forwards Notice of Withdrawal of Amend to License NPF-73. Proposed Change Would Have Extended on one-time Only Basis, Surveillance Interval for TSs 4.8.1.1.1.b & 4.8.1.2 Until First Entry Into Mode 4 Following Seventh Refueling Outage
ML20195K3331998-11-18018 November 1998
Informs That Effective 981214,DS Collins Will Become Project Manager for Beaver Valley Power Station,Units 1 & 2
IR 05000334/19980041998-11-13013 November 1998
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-334/98-04 & 50-412/98-04 Issued on 980915.C/As Will Be Examined During Future Insp of Licensed Program
ML20195J2941998-11-12012 November 1998
Forwards Safety Evaluation Re First & Second 10-year Interval Inservice Insp Request for Relief
ML20155K4041998-11-0505 November 1998
Forwards Insp Repts 50-334/98-07 & 50-412/98-07 on 981006- 07.No Violations Noted.Overall Performance of Emergency Response Organization Was Good
1999-09-08
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- - - . . . . .- .
l g May 19, 1997 .,
Mr. J. E. Cross
, President - Generation Group Duquesne Light Company ;
Post Office Box 4 Shippingport, PA 15077 :
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING BEAVER VALLEY ,
POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 and BVPS-2) 10 CFR 50.46 ANNUAL REPORT (TAC.NOS. M93775 and M93776)
Dear Mr. Cross:
l By letter dated September 26, 1996, Duquesne Light Company (DLC) submitted an annual report required by 10 CFR 50.46 providing notification of changes or errors in the BVPS-1 and BVPS-2 loss-of-coolant accident analyses. The NRC staff has reviewed the subject submittal and has determined that additional ;
information is required for us to complete our review of this submittal. The ,
additional information that is needed is identified in the enclosed RAI. !
Please provide the requested additional information within 90 days of receipt of this letter to enable us to complete our re!iew within a timely manner.
Please contact me at (301)-415-1409 if you have any questions regarding this issue. .
Sincerely,
/S/
1 I
Donald S. Brinkman, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-334/412 7
Enclosure:
Request for Additional l Information l
cc w/ enc 1: See next page ,
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May 19, 1997 '
Mr. J. E. Cross
' President - Generation Group'
- - -Duquesne Light Company.
Post' Office Box 4 ;
-Shippingport, PA 15077 ;
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING BEAVER VALLEY <
POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 and BVPS-2) 10 CFR 50.46 4
ANNUAL REPORT (TAC N05. M93775 and M93776) ,
- Daar Mr. Cross
- '
o By letter dated September 26, 1996, Duquesne Light Company (DLC) submitted an l annual report required by 10 CFR 50.46 providing notification of changes or errors in the BVPS-1 and BVPS-2 loss-of-coolant accident analyses. The NRC
. staff has reviewed the subject submittal and has determined that additional ;
information is required for us to complete our review of this submittal. The ;
additional information that is needed is identified in the enclosed RAI. t Please provide the requested additional information within 90 days of receipt of this letter to enable us to complete our review within a timely manner.
Please contact me at (301)-415-1409 if you have any' questions 'regarding this j
- ... issue. )
1
( Sincerely,
?
M . g 2" L
Donald S. Brinkman, Senior Project Manager t Project Directorate I-2 Division of Reactor Projects - I/II
- Office of Nuc. lear Reactor Regulation Docket Nos. 50-334/412
Enclosure:
Request for Additional Information
. cc w/ encl: See next page l
^
l I
. 1 J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc: l Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW. Environmental Resources i Washington, DC 20037 ATTN: Michael P. Murphy Post Office Box 2063 Director-Safety and Licensing Harrisburg, PA 17120 Department (BV-A) l Duquesne Light Company Mayor of the Borrough of l Beaver Valley Power Station Shippingrort '
PO Box 4 Post Office Box 3 Shippingport, PA 15077 Shippingport, PA 15077 i
Commissioner Roy M. Smith Regional Administrator, Region I West Virginia Department of Labor U.S. Nuclear Regulatory Commission
- Building 3, Room 319 475 Allendale Road Capitol Complex King of. Prussia, PA 19406 Charleston, WVA 25305 Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 ATTN: S. C. Jain, Vice President Ohio EPA-DERR Nuclear Services (BV-A)
ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando-Avenue State College, PA 16803 Duquesne Light Company Beaver Valley Power Station PO Box 4 Shippingport, PA 15077 ATTN: R. L. Grand, Division Vice President, Nuclear Operations Group and Plant Manager (BV-50SB-7) -
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1
, = _=. 7 . = = . - -. . - . - - - - - . _ - . .
I' Reauest for Additional Information Reaardina In CFR 50.46 Annual Reports Beaver Valley Pc ar Station. Unit Nos. I and 2 Docket Nos. 50-334 and 50-412 i
- The NRC staff has reviewed the Beaver Valley Power Station, Unit Nos. I and 2 annual 10 CFR 50.46 report of September 26, 1996, submitted by the Duquesne i t Light Company (DLC). The submittal lacks sufficient detail to determine if 4
the licensee has correctly determined whether the errors, changes, etc. are significant per 10 CFR 50.46(a)(3)(1). It is also unclear whether the ,
licensee has taken appropriate actions >er 10 CFR 50.46(a)(3)(ii) based on its determinations. It appears from the su)mittal that large break (LB) loss-of-coolant accident (LOCA) analyses were appropriately considered; but, it appears that small break (SB) LOCA analyses were not appropriately considered.
For SBLOCA, DLC did not differentiate between permanent and temporary changes. .
This is important for the SBLOCA analyses where it appears that there are at least 190 'F of permanent change in the DLC assessment of adjusted peak cladding temperature (PCT) for both plants. For such a large PCT adjustment, '
10 CFR 50.46(a)(3)(ii) requires a proposed schedule for action to either
' modify the plant configuration to again conform with the licensing SBLOCA analysis of record or to reanalyze with an approved model for the present i
- configuration. DLC also submitted a 10 CFR 50.46 report on March 21, 1997. i This more recent report is equally unclear with regard to SBLOCA analyses, and also likely does not satisfy the reporting requirements of 10 CFR 50.46 f (a)(3)(ii). '
From the inception of the emergency core cooling systems rule, the "LOCA
- model" has been interpreted to be the analytical model covering all break sizes, types, locations, event chronologies and landmarks, and addressing all the criteria of 10 CFR 50.46 (b), as if this were contained in one calculational model. There are still " single" models in use by certain :
vendors; however, it has become common, for various reasons, to treat large ;
'. break and small break LOCA models as variant subsets of the overall LOCA l methodology. '
Licensees are required by 10 CFR 50.46(a;(3)(ii) to perform two assessments,
, one to determine if safety is compromised (2200 *F criterion), and the other to determine if the explicit analysis of record (calculated with an approved i
model) retains precision (50 *F, sum of absolute values of changes, +
, criterion). In the safety assessment, all changes are summed to determine a :
net peak cladding temperature (PCT), as apparently has been done. To address l 4
L the 50 *F criterion, only the absolute values of " permanent" changes are summed.
Since the overall LOCA methodology is no more precise than its most '
? imprecise constituent, both assessments must be performed for both the LBLOCA l and the SBLOCA constituents of the LOCA methodology. These assessments must i
be reported annually and when assessments indicate necessary according to ,
10 CFR 50.46 requirements. Additionally, corrective actions and schedular t commitments for hath LBLOCA and SBLOCA constituents of the LOCA methodology l must be provided in accordance with schedules provided in 10 CFR 50.46. ;
4
- i. DLC is requested to submit information to clarify / rectify the September 26, !
1996,'and March 21, 1997 reports, specifically with regard to SBLOCA analyses, !
for both units.
'
