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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:NRC TO UTILITY
MONTHYEARML20062F2471990-11-16016 November 1990 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 IR 05000334/19890241990-07-0202 July 1990 Advises That Requesting Withdrawal of Violation Noted in Insp Rept 50-334/89-24 Inconclusive.Util Actual Measurements Demonstrate Wide Variation on Specified Angle Indicating Inaccuracies in Physical Measurement Technique 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 ML20059M9291990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248G0031989-09-29029 September 1989 Forwards Safety Insp Repts 50-334/89-13 & 50-412/89-14 on 890708-0831 & Notice of Violation ML20248D7451989-09-29029 September 1989 Forwards Supplemental Safety Evaluation Supporting Util 890707 Response to Open Items Re Plant Safety Monitoring Sys Verification & Validation ML20248G1541989-09-25025 September 1989 Forwards Safety Insp Rept 50-334/89-15 on 890905-08.No Violations Noted ML20247R4781989-09-20020 September 1989 Forwards Amend 12 to Indemnity Agreement B-73,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements ML20247K1771989-09-15015 September 1989 Advises That Licensee 890616 Response to NRC Bulletin 89-001 Consistent W/Actions Requested by Items 2,3 & 4 ML20247K3051989-09-12012 September 1989 Forwards Insp Repts 50-334/89-14 & 50-412/89-15 on 890801- 03.No Violations Noted ML20247K6461989-09-11011 September 1989 Forwards Vol 1 to NRC Maint Insp Guidance, Per 890907 Discussion.Guidance Contains Insp Element Trees ML20246K5691989-08-24024 August 1989 Forwards Insp Repts 50-334/89-17 & 50-412/89-17 on 890731-0810.No Violations Noted ML20246E9551989-08-22022 August 1989 Forwards Exam Rept 50-334/89-16OL Administered on 890727- 28 ML20246H8621989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits.Request That Util Ensure Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20246A9661989-08-11011 August 1989 Forwards Safety Insp Repts 50-334/89-12 & 50-412/89-13 on 890523-0707 & Notice of Violation ML20245F1811989-08-0707 August 1989 Confirms Plan to Conduct Site Audit to Evaluate NDE Performed in Response to Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Audit to Be Performed by R Hermann & M Hum ML20245F6411989-08-0404 August 1989 Requests Util Provide Encl List of Ref Matls for Maint Program Insp Scheduled for 890918-29.NRC Draft Temporary Instruction 2515/97, Maint Instruction, Also Encl for Info & to Aid in Preparing Insp ML20247L8321989-07-21021 July 1989 Forwards Insp Repts 50-334/89-08 & 50-412/89-08 on 890501-05.No Violations Noted ML20246Q0721989-07-17017 July 1989 Discusses NRC Position on Util 880811 Request for Amend to Tech Spec Section 4.7.8.1.b to Relax Supplemental Leak Collection & Release Sys Charcoal Filter Test Requirements. Deviation from Westinghouse STS Not Justified ML20246N2241989-07-13013 July 1989 Forwards Safety Insp Repts 50-334/89-11 & 50-412/89-12 on 890531-0602.No Violations Noted ML20246G2171989-07-0606 July 1989 Forwards Safety Insp Repts 50-334/89-10 & 50-412/89-11 on 890515-19.No Violations Noted ML20245K3501989-06-28028 June 1989 Confirms NRC Plan to Conduct Site Audit on 890803-04,as Part of Efforts to Complete Review of Util Submittals on Thermal Stratification of Pressurizer Surge Line.Encl 1 Provides Outline of Audit Activities for NRC Bulletin 88-010 Issues ML20245G6361989-06-20020 June 1989 Forwards Safety Insp Rept 50-412/89-10 on 890515-19.No Violations Noted ML20245A9291989-06-0909 June 1989 Fowards Security Insp Repts 50-334/89-09 & 50-412/89-09 on 890508-11.No Violations Noted ML20244C4661989-06-0707 June 1989 Confirms Plans to Conduct Site Tour on 890614 as Part of Efforts to Better Understand Phenomenon of Hydrogen Gas Accumulation in Charging Pump Suction Piping.Phenomena Also Subj of NRC Info Notice 88-023,Suppl 1 ML20244B5901989-06-0606 June 1989 Forwards Safety Insp Repts 50-334/89-05 & 50-412/89-05 on 890401-0522.No Violations Noted ML20247N3451989-05-30030 May 1989 Forwards SER Supporting Util Actions in Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Functional Testing ML20247K9431989-05-23023 May 1989 Forwards Safety Insp Repts 50-334/89-07 & 50-412/89-07 on 890417-21.No Violations Noted ML20247H6191989-05-23023 May 1989 Concludes That Proposed Use of Type 420 Stainless Steel Plug in Regulating Valve Acceptable for One Fuel Cycle (Cycle 2) or Until ASME Code Committee Transmits Written Approval ML20247D3481989-05-19019 May 1989 Final Response to FOIA Request.Regulatory Info Tracking Sys Project Managers Rept Encl ML20247D4181989-05-15015 May 1989 Forwards Radiological Controls Insp Repts 50-334/89-06 & 50-412/89-06 on 890410-14.No Violations Noted.Lack of Awareness Re Requirements of 10CFR50.70(b)(4) Identified IR 05000334/19880021989-05-12012 May 1989 Ack Receipt of Changing Schedule for Completion of Corrective Actions Re Insp 50-334/88-02.Actions Will Be Examined During Next Insp of Unit 2 Emergency Operating Procedures,Scheduled for Sept 1989 ML20246M0491989-05-10010 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, That Was Mutually Agreed Upon Between NRC & Westinghouse at 890411 Meeting.Util Schedule Not Approved ML20246M1651989-05-10010 May 1989 Forwards Safety Evaluation Re Plant Safety Monitoring Sys Verification & Validation Plan Submitted by . Hardware Design of Subj Sys Acceptable.Verification & Validation Plan Incomplete & Unacceptable.Info Requested ML20245K6481989-05-0303 May 1989 Forwards Revised Tech Spec Bases Section 3/4.7.9,adding New Paragraph to Define Sealed Sources ML20246P7851989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar Planned by Region I on 890531 in King of Prussia,Pa.Seminar Agenda & Map of Local Area Encl ML20245H4291989-04-28028 April 1989 Confirms Plan to Conduct Site Insp as Part of Efforts to Resolve Issue of Differential Settlement of Buried Pipes. Areas to Be Inspected Includes Ongoing Settlement Monitoring & Review of Settlement Data ML20245H7731989-04-26026 April 1989 Forwards Comments on Util 890113 Response to Generic Ltr 88-17 Re Loss of Dhr.Though Response Appears to Meet Recommended Expeditious Actions,Overall Response Brief & Therefore Fails to Address All Items in Detail 1990-09-20
[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
[Table view] |
Text
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I Docket No. 50-412 DISTRIBUTION Docket. File t N. Thompson NRC PDR P. Tam Mr. J. J. Carey, Senior Vice President Local PDR J. Guillen Duquesne Light Company PAD #2 Rdg D. Miller Nuclear Group T. Novak ACRS (10) i Post Office Box 4 OGC-Bethesda Tech Branch l Shippingport, Pennsylvania 15077 E. Jordan B. Grimes
Dear Mr. Carey:
J. Partlow
Subject:
Beaver Valley Power Station, Unit 2 - Transmittal of a Preliminary Draft of the Proposed Low Power License Enclosed for your review and comment is a preliminary draft of the proposed low power license for the Beaver Valley Power Station, Unit 2. A principal objective of this transmittal is to provide for timely identification of any clarification needed regarding the conditions stated in this license. The enclosures to the license are not included in this transmittal.
We expect that the license conditions for the full power license will be the same as those in this draft low power license, unless a resolution is reached before issuance of the full power license. In addition, there is potential that new license conditions may be added as we attempt to close out SER open eisd confirmatory issues. Please note that proposed conditions (41 steam generator tube rupture, (8) control room design review, (9) safety parameter display system, and (10) regarding natural circulation, may be eliminated if you provide written commitments to do what these proposed conditions would require.
Please provide your comments by March 25, 1987. If you require any clarification of this matter, please contact the Project Manager, Peter Tam at (301) 492-9409.
The reporting and/or recordkeeping requirements of this letter affect fewer than 10 respondents; therefore OMB clearance is not required under P.L.96-511.
Sincerely, is(
Lester S. Rubenstein, Director PWR Project Directorate 42 Division of PWR Licensing-A Office of Nuclear Reactor Pegulation
Enclosure:
As stated cc w/ enclosure: See next page p
- See previous concurrence fgf]
- LA: PAD #2 *FE: PAD #2 PD: PAD #? y DMiller JGuillen:he *PM:Pp)#2 PTamy LRubenstein 3/ /87 3/ /87 3//2,/87 ] 3//?/87 8703260466 870312 PDR ADOCK 0S000412 A PDR
Docket No. 50-412 DISTRI8tlTION Docket File N. Thompson NRC PDR P. Tam Mr. J. J. Carey, Senior Vice President local PDR J. Guillen Duquesne Light Company PAD #2 Rdg D. Miller Nuclear Group T. Novak . ACRS (10)
Post Office Box 4 OGC-Rethesda . Tech Branch Shippingport, Pennsylvania 15077 E. Jordan
~-
B. Grimes near Mr. Carey: .J. Partlow
Subject:
Beaver Valley Power Station, Unit 2 - Transmittal of a Preliminary Draft of the Proposed Low Power License Enclosed for your review and connent is a preliminary draft of the proposed low power license for the. Beaver Valley Power Station. Unit 2. A principal ob,iective-of this transmittal is to provide for timely identification of any
-clarification needed regarding the conditions stated in this license. The enclosures to the license are not included in this transmittal.
We expect that th'e license conditions for the full power license will be the same as those in this draft low power license, unless a resolution is reached before issuance of the full power license. In addition, new license conditions may be added as we attempt to close out SER open and confirmatory issues.
Please note that proposed conditions (4) regarding steam generator tube rupture, (8) regarding control room design review, (9) regarding safety parameter display system, and (10) regarding natural circulation, may be eliminated if you provide written commitments to do what these proposed conditions would require.
.Please provide your comments by March 25, 1987. If you require any clarification of this matter, please contact the Project Manager, Peter Tam at (301) 492-9409.
The reporting and/or recordkeeping requirements of this letter affect fewer than 10 respondents; therefore OMB clearance is not required under P.L.96-511.
Sincerely, i
Lester S. Rubenstein, Director l PWR Project Directorate #2 l Division of PWR Licensino-A
( Office of Nuclear Peactor Regulation
Enclosure:
As stated cc w/ enclosure: See next page M#N MW PE, 2 Jrh llen:he PM:PA PTam PD: PAD #2 LRubenstein
/87 3/p/87 3/[L 3/ /87
= _ _ - - -
Mr. J. J. Carey Duquesne Light Company Reaver Vallev 9 Power Station cc:
Gerald Charnoff, Esq. Mr. R. E. Martin, Manager Jay E. Silberg, Esq. Regulatory Affairs Shaw, Pittman, Potts & Trowbridge Duquesne Light Company 2300 N Street, N.W. Beaver Valley Two Project Washington, DC 20037 P. O. Box 328 Shippingport, Pennsylvania 15077 Mr. C. W. Ewing, Quality Assurance Zori Ferkin Manager Assistant Counsel Quality Assurance Department Governor Energy Council Duquesne Light Company 1625 N. Front Street P. 0. Box 186 Harrisburg, PA 15105 Shippingport, Pennsylvania 15077 John D. Burrows, P.E.
Director, Pennsylvania Emergency Director of Utilities Management Agency State of Ohio Room B-151 Public Utilities Commission Transportation & Safety Puilding 180 East Broad Street Harrisburg, Pennsylvania 17120 Columbus, Ohio 43266-0573 Mr.1. J. Lex Bureau of Radiation Protection i
Westinghouse Electric Corporation PA Department of Environmental Power Systems Resources P. O. Box 355 ATTN: R. Janati
. Pittsburgh, Pennsylvania 15?30 P.O. Box 2063 Harrisburg, Pennsylvania 171?O Mr. P. RaySircar Stone & Webster Engineering Corporation BVPS-2 Records Management Supervisor P. O. Box 2325 Duouesne Light Company Boston, Massachusetts ~02107 Post Office Box 4 Shippingport, Pennsylvania 15077 Mr. J. Beall U. S. NRC John A. Lee, Esq.
P. O. 181 Duquesne Light Company Shippingport, Pennsylvania 15077 1 0xford Centre 301 Grant Street Mr. Thomas E. Murley, Regional Admin. Pittsburgh, Pennsylvania 15279 U. S. NRC, Region I 631 Park Avenue King of Prussia, Pennsylvania 15229
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~g UNITED 8TATES
. E o NUCLEAR RfGULATORY COMMISSION wA2Howcrow,n.c.rosss h
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>j Dtl00ESNE LTGHT COMPANY OHIO EDIS0N COMPANY THE CLEVELAND ELECTRTC ILLUMINATINf; COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT 2 FACILITY OPERATING LICENSF License No. NPF-6a
- 1. The Nuclear Regulatory Comission (the Comission or the NRC1 has found
.-- that:
A. The application for license filed by the Duquesne Light Company acting for itself, and Ohio Fdison Company, The Cleveland Electric Illuminating Company, and The Toledo Edison Company, (the licensees),
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;
- 8. Construction of the Beaver Valley Power Station, Unit 2, (the facility) has been substantially completed in conformity with Construction Pemit No. CPPR-105 and the application, as amended, the provisions of the Act and the regulations of the Comission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D.
belowl; D. There is reasonable assurance: (11 that the activities authorized by this operating license can be conducted without endancering the i health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter T (except as exempted. from compliance in Section 2.D. below); _
~
\
E. Duquesne Light Company
- is technically cualified to engage in the ,
activities authorized by this license in accordance with the i Comission's reoulations set forth in in CFR Chapter I; l l
F. The licensees have satisfied the applicable provisions of 10 CFR !
Part 140, " Financial Protection Requirements and indemnity Agreements," of the Commission's regulations; l G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H. After weiching the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-64, is sub. ject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix R. is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable recuirements have been satisfied;
.-- I. The receipt, possession and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40, and 70.
i
- 2. Based on the foregoing findings regarding this facility and satisfaction of conditions therein imposed. Facility Operatina License No. NPF-64 is hereby issued to the Duquesne Light Company and Ohio Edison Comoany, The
- Cleveland Electric Illuminating Company, and The Toledo Edison Company, (the licensees) to read as follows:
A. This license applies to the Beaver Valley Power Station, Unit 2, a pressurized water reactor and associated equipment (the facility) owned by Ohio Edison Company, The Cleveland Electric illuminating Company, and The Toledo Edison Company and owned and operated by the Duouesne Light Company. The facility is located on the licensees' site on the southern shore of the Ohio River in Reaver County, Pennsylvania, approximately ?2 miles northwest of Pittsburgh and 5 miles east ef East Liverpool, Ohio, and is described in Duouesne Light Company's Final Safety Analysis Report, as supplemented 4
and amended, and in its Environmental Report, as supplemented and amended; t
- Duquesne Light Company is authorizeh to act as agent for Ohio Edison Company, The Cleveland Illuminating Electric Company, and The Toledo Edison Company and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
~ ~
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses: ,
(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, Duquesne Light Company to possess, use, and operate the facility at the designated location in Beaver County, Pennsv1vania, in accordance with the procedures and limitations set forth in l this license;
(?) Pursuant to the Act and 10 CFR Part 50, Ohio Edison Company.
The Cleveland Electric Illuminating Company, and The Toledo Edison Company to possess the facility at the designated
, location in Beaver County, Pennsylvania, in accordance with the procedures and limitations set forth in the license; (31 Pursuant to the Act and 10 CFR Part 70. Duquesne Light Company to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70. Duquesne Light Company to receive, possess, and use at any time any byproduct, source, and special nuclear material such as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70. Duquesne Light Company to receive, possess, and use in amounts as required any byproduct, source er special nuclear material without restriction to chemical or physical form, for sartple analysis or instrument calibration or associated with radioactive apparatus or components; (6) Pursuant to the Act and 10 CFR Parts 30, 40, and 70. Duquesne Light Company to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.
C. This license shall be deemed to contain and is subject to the conditions specified in the Comission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is sub.iect to the additional conditions specified or incorporated below: ,
(
(11 MaximumDowerltevel Ducuesne Light Company is authorized to operate the facility at reactor core power levels not in excess of 2652 mecawatts thermal (100 percent powerl in-accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational tests, startup tests and other items ider.tified in Attachment I to this license shall be completed as specified.
Attachment 1 is hereby incorporated into this license. Pending Comission approval, this license is restricted to reactor core power levels not to exceed 5 percent of full power (132.06 megawatts thermali.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the.
Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duquesne Licht Company shall operate the facility in accordance with the Technical Specifications and the
.-- Environmental Protection Plan.
(3) Initial Startuo Test Procram (Section 141*
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(4) Steam Generator Tube Rupture (Section 15.6.3)*
l At least 6 months before the first refcalino outage, Duquesne i
Licht Company shall submit the following plant-specific infonnation for NRC review:
(1) Analyses of steam line static load in the event of overfill; (2) Radiological consequence analysis; (3) A listino of systems and components credited in the analyses to miticate accident consequences, including .iustification of their use if they are not safety-grade.
The staff has detennined that the low probability of a design basis SGTR accident during the first cycle of operation offers reasonable assurance that Beaver Valley,tinit 2, can operate for one cycle until this issue is resolved.
- The parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
(5) Accumulator Tank Level or Pressure Instrumentation (Section 7.5.7.11*
Duquesne Light Company shall install and have operational qualified accumulator tank level or pressure instrumentation prior to startup following the second refueling outage.
(6) Fresh Fuel Storage The following criteria apply to the storage and handling of new fuel assemblies in the Fuel Handling Building:
(a) No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at any one time.
(b) The minimum edge-to-edae distance between the above two new assemblies, the shipping container array, and the storage rack arrays shall be at least 12 inches.
(c) New fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.
(7) Formal Federal Emeroency Management Agency Finding In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a maior substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54's)(2) will apply.
(8) Detailed Control Room Design Review (Section 18.1)*
Prior to startup following the first refueling outace, Duquesne Light Company shall complete all Detailed Control Room Design Review (DCRDR) surveys, satisfactorily resolve all open DCRDR issues, and implement all proposed control room improvements resulting from the DCRDR.
f (9) Safety Parameter Display System (Section 18.2)*
Prior to startup following the first refueling outage.
Duquesne Light Company shall provide acceptable . responses and implement any proposed corrective actions related to the open issues on the Safety Parameter Display System (SPDS).
~ . - - _ . _ . - .. .__ -. - . .-. . . .
~ ~
(101 Natural Circulation Test ISection 5.4.7)*
- At least 6 months be# ore the first refueling outage Duquesne Light Company shall submit for NRC review a natural circulation analysis which demonstrates that the Diablo Canyon test is applicable to Reaver Valley, Unit 2. As an alternate, Duquesne Light Company may perform a natural circulation and boron mixing
, test at Reaver Valley, Unit ? which meets the requirements of RTP RSB 5-1.
- D. Exemptions 1
(1) The facility requires a schedular exemption from General Design Criterion 4, Appendix A to 10 CFR 50, which reouires that structures, systems and components important to safety be appro-priately protected against dynamic effects, including the effects of missiles, pipe whipping and discharging fluids that may result from eouipment failures and from events and conditions outside the nuclear power unit. As the staff described in detail in Supplement 4 to the Safety Evaluation Report, installation of
-~
pipe whip restraints is not necessary to achieve the underiving purpose of the rule, since application of " leak-before-break" technology would achieve the same degree of safety at lower cost and reduce occupational exposure. This exemption is authorized by law and will not endanger life or property or the comon defense and security, and certain special circumstances are present. With the granting of this exemption, the facility will
,, operate, to the extent authorized hemin, in conformity with application, as amended, the provisions of the Act, and the rules and regulations of the Comission. This schedular exemption is, ranted pursuant to 10 CFR 50.1?f al(11 and therefore, 10 CFR 50.12(a)(21 hereby fii) as follows:
Beaver Valley Pc w r Station Unit 2 is exempt from the requirements of General Design Criterion (@C) A, Appendix A to 10 CFR 50 to eliminate the dynamic loading effects associated with the postu-lated pipe breaks described in detail in Section 3.6.3 of Supplement 4 to the Safety Evaluation Report. These dynamic loading effects include pipe whip, jet impingement, and break-associated dynamic transients. Specifically, this eliminates the need for pipe whip mstraints with pipe bmaks. This exemption will expire upon completion of the @C-4 rulem3 king changes but i
no later than startup following the second refueling outage.
(21 The facility requires a technical exemption from 10 CFR 50,
- Appendix J,Section III.D.?(b)(ii) which requires that " Air locks opened during periods when containment integrity is not required by the plant's Technical Specification shall be tested at the end of such periods at not less than P3 ." The justification of this exemption is contained in Section 6.7.6 nf Supplement 5 to 1
. - - -, , , ~ m--,we, - , , - , - - , , - - ,,,,,v ,,.,-.,--w , --,nnm.n-,,-.,,- .w.--------,,wa-.n,--,----,.--,-.,e,_ ,n,-.-,c, ,--rm r,-- - - , - - ,
the Safety Evaluation Report. This exemption is authorized by law and will not endanger life or property or the common de#ense and security, and certain special circumstances are present.
With the granting of this exemption, the facility will operate, to the extent authorized herein, in confomity with the applica-tion, as amended, the provisions of the Act, and the rules and regulations of the Commission. Therefore, pursuant to 10 CFR 50.12(a)(1) and 10 CFR 50.12/alf 2)(ii) and (111), Beaver Valley Power Station, Unit ? is exempt from the quoted requirement and instead, is required to perfom the overall air lock leak test at pressure P prior to establishing containment integrity if the air lock maintenance that has been perfomed could affect the air lock sealing capability.
(3) The facility requires a schedular exemption from 10 CFR 50.55alh),
which requires compliance with IEEE Standard 270-1971 pertaining to feedwater isolation on a high steam generator level. The staff has reviewed the infomation related to this exemption and documented its review in Section 7.3.3.12 of the Safety Evaluation Report, Supplement 5. This exemption is authorized
._ by law and will not endanger life or property or the comon defense and security, and certain special circumstances are present. With the granting of this exemption, the facility will operate, to the extent authorized herein, in confomity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission. Therefore, pursuant to 10 CFR 50.12(a)(1) and 10 CFR 50.12(a)(2)(v),
Beaver Valley, Unit 2 is granted a schedular exemption to postpone installation of the stean generator high level median selector, which is required to ensure that feedwater isolation on high steam generator level is in ccmpliance with IEEE Standard 279-1971, to the end of the first refueling outage.
(4) (Exemption regarding use of RM 50-2 is being developed).
, -----e, - - , , ,,- - - - - - - - - - - - . , , - - - - -
(5) The facility yas previously granted an exemption from the criticality alam requirements of paragraph 70.24 of 10 CFD Part 70 insofar as this section applies to this license.
(See License No. SNM-1954 dated April 9, 1986, which granted this exemption). -
E. Physical Security
,~ Duquesne Light Company shall fully implement and maintain in effect all provisions of the physical security, cuard training and oualifi-cation, and safeguards contingency plans previously approved by the Comission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.5af p'. The plans, which contain Safeguards Infomation protected under 10 CFR 73.21, are entitled:
F. Fire Protection Procram (Section o.5.1)*
Duquesne Light Company shall implement and maintain in effect all provisions of the approved fire protection procram as described in the Final Safety Analysis Report for the facility, as amended and as l*
described in the (SER) dated October 1985 (and Supplements 1 through 5) subject to the following provision below.
The licensees may make changes to the approved fire protection program without prior approval of the Comission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
I G. Reporting to the Comission l Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Duquesne Light Company shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be rade within twenty #our (24) hours to the NRC Operations Center
- via the Emergency Notification System with written follow-up with 30 days in accordance with the procedurws described in 10 CFR 50.73(b) (c) and (el. _
4 H. The licensees shall have and maintain financial protection of such i type and in such amounts as the Comission shall require in i accordance with Section 170 of the Atomic Energy Act of 1956, as amended, to cover public liability claims.
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. t i I. This license is effective as of the date of issuance and shall expire at midnight on FOR THE NUCLEAR REGULATORY COMMISSION
(
Harold R. Denton, Director Office of Nuclear , Reactor Regulation
Enclosures:
- 1. Attachment 1
- 2. Appendix A - Technical Specifications ,j
- 3. Appendix B - Environmental '-
Protection Plan r ,,,3 Date of issuance: "
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