NUREG-0814, Forwards Methodology for Evaluation of Emergency Response Facilities Review of Beaver Valley Power Station,Unit 1. Conceptual Design Plan Insufficiently Detailed to Determine Compliance w/NUREG-0696
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| ML20011B118 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/09/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Carey T DUQUESNE LIGHT CO. |
| Shared Package | |
| ML20011B119 | List: |
| References | |
| RTR-NUREG-0696, RTR-NUREG-0814, RTR-NUREG-696, RTR-NUREG-814 GL-81-10, NUDOCS 8112040021 | |
| Download: ML20011B118 (3) | |
Similar Documents at Beaver Valley | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1591999-10-19019 October 1999
[Table view]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-99-152, 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 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 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 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 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 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 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-99-098, 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-99-136, 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-99-137, 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-99-037, 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-99-111, 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-99-113, 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-99-112, 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 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 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 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 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 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 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 1999-09-08 Category:NRC TO UTILITY MONTHYEARML20062F2471990-11-16016 November 1990
[Table view]Summarizes Staff Understanding of Current Status Re GSIs Remaining Unimplemented at Facility Based on Util 900627 Response to Generic Ltr 90-04 & 901025 Meeting ML20058D5321990-10-30030 October 1990 Forwards Addl Info Re Proposed Change Request 1A-176 Relating to Overpressure Protection Sys ML20058B6651990-10-19019 October 1990 Grants 901018 Request for Temporary Waiver of Compliance from Tech Spec 3.6.2.2 Re Reduced Flow Through Spray HXs ML20062B6621990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062A6961990-10-11011 October 1990 Responds to Util 900907 Request for Authorization to Use Alloy 690 for Steam Generator Tube Plugs.Use of Alloy 690 Acceptable ML20059N4651990-10-0101 October 1990 Forwards Insp Repts 50-334/90-19 & 50-412/90-19 on 900917- 21.One Noncited Violation Noted ML20059L6341990-09-20020 September 1990 Advises That No short-term Safety Concerns Noted Per 890530 Response to NRC Bulletin 88-011 Re Thermal Stratification ML20059E7531990-08-24024 August 1990 Forwards Requalification Program Evaluation Rept 50-334/90-14OL-RQ on 900709-19.Util Requalification Program Assigned Overall Rating of Satisfactory ML20058P3921990-08-10010 August 1990 Forwards Requalification Program Evaluation Rept 50-412/90-11(OL-RQ) Administered on 900529-0607.Program Assigned Overall Rating of Satisfactory ML20058N0711990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Establishment of Engineering Managers Forum ML20056A3511990-07-24024 July 1990 Forwards Safety Insp Repts 50-334/90-12 & 50-412/90-12 on 900505-0622 & Notice of Deviation ML20055G8071990-07-16016 July 1990 Forwards Insp Repts 50-334/90-15 & 50-412/90-15 on 900611-15.No Violations Noted ML20055G4251990-07-11011 July 1990 Forwards Radiological Controls Insp Repts 50-334/90-16 & 50-412/90-16 on 900604-08.No Violations Noted.Weaknesses Noted.Review of Weaknesses Requested & Results of Review Should Be Submitted to NRC by 900901 ML20058K4511990-06-29029 June 1990 Advises That NRC Has No Objection to Util Corrective Actions & Schedule for Unqualified Fire Damper Engineering Evaluations.Complete Review of Util Engineering Evaluations Will Be Issued Later ML20043H9141990-06-22022 June 1990 Advises That Financial Info for Participants Submitted for 1990 in Satisfies Requirements of 10CFR140.21 That Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Operating Reactor Over 100 Mw(E) ML20044A6041990-06-18018 June 1990 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 900801 in King of Prussia,Pa to Discuss Recent Format Changes to Requalification/Initial Exams. Proposed Agenda & Lodging Info Encl ML20059M9291990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043F7961990-06-12012 June 1990 Requests That Util Inform Commission in Writing of Replacement of Independent Safety Evaluation Group ML20043F7361990-06-0808 June 1990 Grants 900606 Request for Temporary Waiver of Compliance from Requirements of Tech Spec 3.6.3.1 ML20034D0061990-05-25025 May 1990 Forwards Safety Insp Repts 50-334/90-11 & 50-412/90-10 on 900430-0504.No Violations Noted.Weaknesses Noted in Lab Qa/ QC Program.Complete Data from Independent Measures Taken Will Be Reported in Subsequent Insp Rept ML20043C3171990-05-22022 May 1990 Advises That Assessing Intakes of Radioactive Matl Using Bioassay Data Should Be Based on Best Data & Models Available for That Purpose.Licensees May Use Improved & Generally Accepted Methodology Used in Icrp Publications ML20043A2851990-05-10010 May 1990 Forwards Insp Repts 50-334/90-80 & 50-412/90-80 on 900226-0307.Weaknesses Identified.Overall Assessment of Program at Unit 2 for Development & Maint of symptom-based EOPs Found Very Good ML20042G3551990-05-0909 May 1990 Advises of Closeout of Generic Ltr 89-19, Actions Re Resolution of USI A-47, `Safety Implications of Control Sys in LWR Nuclear Power Plants ML20042G7831990-05-0404 May 1990 Informs of Proposed 900620-21 Workshop in King of Prussia,Pa to Promote Better Understanding of NRC Insp Program.Proposed Agenda Encl ML20042F4381990-05-0303 May 1990 Requests Submission of Westinghouse Reassessment of NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20043A8961990-05-0202 May 1990 Forwards Agenda for NRC Region I Radiation Protection Managers Conference on 900523-24 in King of Prussia,Pa ML20042F3491990-04-27027 April 1990 Forwards Safety Insp Repts 50-334/90-07 & 50-412/90-06 on 900217-0330.No Violations Noted ML20012C6781990-03-21021 March 1990 Reaffirms Granting of Temporary Waiver of Compliance W/Tech Spec 3.8.2.1, Onsite Power Distribution Sys & Informs of Plan to Issue Amend to Adopt Westinghouse STS Requirement Upon Expiration of Comment Period ML20012E6021990-03-19019 March 1990 Informs of 900523-24 Radiation Protection Manager Conference in King of Prussia,Pa to Discuss Issues of Mutual Interest Re Power Reactor Radiological Controls Program ML20012D3201990-03-16016 March 1990 Advises That Evaluation of Requalification Program & Licensed Personnel Scheduled for Wks of 900709 & 16.NRC Examiners Will Visit Site Approx 14 Days Prior to Evaluation.Ref Matls,Listed on Encl,Should Be Furnished ML20012C3131990-03-13013 March 1990 Forwards Understanding of Current Status of All Unimplemented USIs for Plant,Per Generic Ltr 89-21 & Licensee 891127 Response ML20033E3671990-02-27027 February 1990 Forwards Safety Insp Repts 50-334/90-03 & 50-412/90-03 on 900122-26.No Violations Noted.Corrective Actions Re Problems Experienced W/Aluminum Cables Require Further Mgt Attention & Will Be Reviewed During Future Insp ML20011F7431990-02-26026 February 1990 Forwards Insp Repts 50-334/89-80 & 50-412/89-80 on 890911-29.No Violations or Unresolved Items Noted.Response to Weakness Identified in Insp Rept Requested within 60 Days of Ltr Receipt ML20011F6771990-02-22022 February 1990 Advises That Evaluation of Requalification Program & Licensed Personnel Scheduled for Wks of 900528 & 0604.NRC Examiners Will Visit Site Approx 14 Days in Advance of Exams.Ref Matl,Listed on Encl,Should Be Furnished NUREG-1057, Advises That Util May Decide to Revise Emergency Operating Procedure (EOP) Procedure Generation Package (PGP) Based on Safety Evaluation Submitted Via Unit 2 Sser 5 (NUREG-1057, Suppl 5) & Insps But Need Not Submit PGP Rev to NRC1990-02-16016 February 1990 Advises That Util May Decide to Revise Emergency Operating Procedure (EOP) Procedure Generation Package (PGP) Based on Safety Evaluation Submitted Via Unit 2 Sser 5 (NUREG-1057, Suppl 5) & Insps But Need Not Submit PGP Rev to NRC ML20006F3811990-02-16016 February 1990 Forwards Insp Rept 50-334/90-04 on 900122-26.Enforcement Conference Will Be Scheduled in Mar 1990 to Discuss Operation of 120-volt Ac Vital Instrument Bus in Degraded Condition W/O Restrictions ML20033E0531990-02-15015 February 1990 Advises That 900130 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable ML20006F3111990-02-15015 February 1990 Forwards Combined Safety Insp Repts 50-334/89-23 & 50-412/89-22 on 891118-1231 & Notice of Violation.Response Re Failure to Follow Written Procedures That Apparently Led to Unit 1 Safety Injection Actuation Requested ML20006F2681990-02-13013 February 1990 Forwards Final SALP Repts 50-334/88-99 & 50-412/88-99 for June 1988 - Aug 1989.Typos & Editorial Corrections Made After Review of Encl 900103 Response to SALP Rept.List of Meeting Attendees & 891124 Transmittal Ltr Also Encl ML20011E5911990-02-0707 February 1990 Forwards Safety Insp Repts 50-334/90-01 & 50-412/90-01 on 900108-12.No Violations Noted ML20006C3581990-01-31031 January 1990 Forwards Combined Insp Repts 50-334/90-05 & 50-412/90-04 on 900129 & Notice of Violation ML20006B4401990-01-24024 January 1990 Advises That Licensee 890223 & 0317 Responses to Generic Ltr 88-17 Re Programmed Enhancements for Loss of DHR Appears to Meet Intent of Ltr But Lacks Detail.Util Suggested to Consider Listed Items to Assure Required Actions Addressed IR 05000334/19890211990-01-18018 January 1990 Discusses Insp Repts 50-334/89-21 & 50-412/89-20 on 890925- 29 & 1004-10 & Forwards Notice of Violation.Violation in Section I Classified as Severity Level III Because Substantial Potential for Radiation Overexposures Created ML19354E0481990-01-18018 January 1990 Forwards Safety Evaluation Accepting Util 890104,0516,17 & 0830 Ltrs Re Pressurizer Surge Line Thermal Stratification ML20005G2591990-01-12012 January 1990 Discusses Review of Plant 60-day Response to Generic Ltr 88-20, Individual Plant Exams, Per Util . Individual Plant Exams,Methodology & Schedule Acceptable ML20005H2721990-01-11011 January 1990 Confirms Insp of Emergency Operating Procedures on 900226- 0309,per Conversation Between F Lipchick & L Briggs.Ref Matl Required to Be Provided to NRC No Later than 900109 to Support Insp Schedule Encl & Tentative Schedule Encl ML20005G7221990-01-11011 January 1990 Forwards Safety Insp Repts 50-334/89-22 & 50-412/89-21 on 891014-1117 & Notice of Violation.Weaknesses Noted Re Control of Licensed Activities Which Contributed to Loss of One Train of Cold Overpressure Protection Sys ML20006D6371990-01-0505 January 1990 Forwards Revised NRC Forms 398 & 396 Re Personal Qualifications Statement & Certification of Medical Exam by Facility Licensee,Respectively.All Applications for Licenses to Be Submitted on Revised Forms by 900201 ML19354D5561989-12-20020 December 1989 Forwards Insp Rept 50-334/89-19 on 891030-1103.No Violations Noted ML20005D6261989-11-22022 November 1989 Responds to Re Util Obligation to Rept Decommissioning Info Per 10CFR50.75.Each Licensee May File Rept Under 10CFR50.75 for pro-rata Share of Reactor or Licensee Designated by co-licensees May File One Rept 1990-09-20 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M1591999-10-19019 October 1999
[Table view]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 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 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 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 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 IR 05000334/19980111999-04-14014 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 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 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 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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DISTRIBUTION UNITED STATES
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NUCLEAR REGULATORY COMMISSION Docket File NRC PDR
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NOV 9 1981 D. Eisenhut J. Heltemes O!
S. Varga Docket No. 50-334 4%
Q'd[U. 'f;*)g' C. Parrish x
D. Chaney 6
Mr. J. J. Carey
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OELD NOV191981a -,-
ISE (3) l Vice President, Nuclear Duquesne Light Company
'63 u.Atm gym j NSIC TERA 435 Sixth Avenue
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ACRS (10)
Pittsburg, PA 15219 g
Dear Mr. Carey:
This letter is in response to the design plan proposed for the Emergency Response Facilities of the Beaver Valley Power Station, Unit 1, which was submitted in response to the Generic Letter 81-10 from the Director of Licensing.
Enclosed is an evaluation, using NUREG-0814 " Methodology for Evaluation of Emergency Response Facilities," to determine whether the proposed conceptual design plan fulfills the design concepts of NUREG-0696,
" Functional Criteria for Emergency Response Facilities".
The proposed conceptual design provided is not sufficiently detailed to determine if it meets the criteria set forth in NUREG-0696.
The major items described in the proposed Beaver Valley, Unit 1 conceptual design plan requiring additional information are as follows:
1.
Legible diagrams of locations and layout for the TSC, OSC and E0F illustrating work station locations, data aquisition hardware, comunications hardware and locations within the emergency response facilities where emergency functions are to be perfonned.
2.
The staffing, data flow and communications procedures for the TSC and E0F, 3.
The habitability and structural features for the TSC and EOF.
4.
The functional description, staffing, comunications and size of the OSC.
5.
The radiological monitoring systems, dose assessment, monitoring techniques and hardware for the TSC, OSC and E0F.
6.
The descriptions of the emergency equipment and procedures used in the control room to interface with the TSC, OSC and E0F.
7.
The radiological monitoring procedures and equipnent for emergency response facilities personnel.
8.
The descriptions of computer environment, display devices and formats, documentation, reliability, maintenance, training and quality assurance for the data acquisition systems.
8112040021 811109 PDR ADOCK 05000334 F
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idr. J. J. Carey
-2 NOV 9 1991 We are unable to fully evaluate and approve your conceptual design plan for Beaver Valley Power Station, Unit 1 Emergency Response Facilities until you have resutnitted your design correcting the deficiencies noted above. Whereas fl0REGs 0696 and 0014 only provide guidance and are not requirements, they do provide a method by which your emergency response facilities can fulfill the requirements of 10 CFR 550.47 and 10 CFR, Appendix E, for adequate emergency facilities and equipment to support an emergency response. The enclosed evaluation. report, using flUREG-0814, provides additional guidance to assist you in reviewing your sutnittal.
Your revised conceptual design plan should be sutmitted for reevaluation within 45 days of the date of this letter. He will provide you with the results of our review of your revised plan within 40 days of the date of receipt. Whether or not you make a timely sutnittal of revised material, your emergency response facilities must be completed by the date by which operating reactors must complete these facilities.
Sincerely,
' Original Simed 41 Steven A. Varga, Chief Operating Reactors Branch flo. 1 Division of Licensing
Enclosure:
As stated cc: See next page CR2
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OFFICIAL RECORD COPY usom i i_mm g
Mr. J. J. Carey Duquesne Light Company ie cc: - Mr. 4. P. Williams Mr. J. D. Sieber, Manager Station Superintendent Nuclear Safety and Liter,;ing Cuquesne Light Company Duquesne Light Company beava Valloy Power Station Nuclear Division i
Inst Of fice Box 4 Post Office Box 4
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Shippingpert, Pennsylvania 15077 Shippingpert, Pennsylvaria 15077 i
Mr. T. D. Jones, Manager Resident Inspector
-Nuclear Operations U. S. Nuclear Regalatory Conmission Duquesne Light Company Post Of fice Box 298 Post Of fice Box 4 Shippingport, Pennsylvania 15077 4
Shippingport, Pennsylvania 15077 i
_ U. F. Jones Memorial Library 663 Franklin Avenue Aliquippa, Pennsylvania 15001 Gereld Charnoff, Esquire Jay E. Silberg, Esquire t~
Shaw, Pittman, _ Potts and Trowbridge t
1800 M Street, N.W.
l Washington, D.C.
20036 Karin Carter, Esquire Special Assistant Attorney General i; -
Bureau of Administrative Enforcement Sth Floor, Executive House l
Harrisburg, Pennsylvania 17120 i
Marvin Fein j
Utility Counsel City of Pittsburgh l
313 City-County Building Pittsburgh, Pennsylvania 15219 Mr. John A. Levin Public Utility Commission 4
P.O. Box 3265 Harrisburg, Pennsylvania 17120 i
Irwin A. Popowsky, Esquire Office'of Consumer Advocate 1425 Strawberry Square Harrisburg,' Pennsylvania 17120=
l Charles A. Thomas, Esquire
. Thomas and Thomas 212 Locust Street-l Box 999 Harrisburg, Pennsylvania 17108 l
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