ML20216G458
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| ML20216G458 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/17/1987 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Sieber J DUQUESNE LIGHT CO. |
| Shared Package | |
| ML20216G462 | List: |
| References | |
| NUDOCS 8707010097 | |
| Download: ML20216G458 (2) | |
Similar Documents at Beaver Valley | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999
[Table view]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 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 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 Category:OUTGOING CORRESPONDENCE MONTHYEARIR 05000412/19990071999-10-21021 October 1999
[Table view]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 |
See also: IR 05000334/1987007
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JUN 171987
Docket / License: 50-334/DPR-66
Duquesne Light Company
ATTN: Mr. J. D. Sieber
Vice President
Nuclear Operations
Post Office Box 4
Shippingport, Pennsylvania 15077
i
Gentlemen:
Subject: Inspection 50-334/87-07
This refers to the resident safety inspection by Messrs. J. Beall, F. Young and
S. Pindale on April 18 - June 4, 1987, at the Beaver Valley Power Station, Unit
1, Shippingport, Pennsylvania. The inspection consisted of document reviews, in-
terviews and observation of activities. The findings were discussed with you and
other members of your staff. ,
1
Based on the results of this inspection, it appears that certain of your activities
were not conducted in full compliance with NRC requirements. Please respond to
these matters in accordance with the enclosed Appendix A.
Additionally, it has been noted that during the past five months (January - May,
1987), a nuuber of apparently unrelated events involving errors by personnel in
various station groups have occurred. Specific examples include the failure to
perform a technical specification surveillance test, minor unplanned gaseous and
liquid releases, two auto AFW pump starts, several inadvertent ESF actuations and
the failure to make a timely required report. While each event separately was
minor with respect to safety significance, collectively, they are cause for in-
creased concern in that the number and types of events may be an early indication
of an adverse trend in performance. Therefore, in your response to this letter,
please include ycur assessment of the cause of these events and identify your cor-
rective actions.
The response directed by this letter and the accompanying Notice are not subject
to the clearance procedures of the Office of Management and Budget as required by
the Paperwork Reduction Act of 1980, PL 96-511.
Your cooperation with us is appreciated.
l
Sincerely, !
.Or inal sned By -
ward . Wenzinger, Chief
e707010097 QM34 Projects Branch No. 3
PDR ADOCK PDR Division of Reactor Projects
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Duquesne Light Company 2
r g y 7 3g37
Enclosures:
1. NRC Notice of Violation, Appendix A
2. NRC Region I Inspection Report 50-334/87-07
cc w/encls:
H. M. Siegel, Manager, Nuclear Engineering Department
C. E. Ewing, QA Manager
W. S. Lacey, Plant Manager
R. Druga, Manager, Technical Services
R. Martin, Manager, Regulatory Affairs
J. Crockett, Senior Manager of Nuclear Operations
N. R. Tonet, Manager, Nuclear Engineering & Construction Unit
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
Commonwealth of Pennsylvania
bcc w/ encl:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
Section Chief, DRP
M. McBride, RI, Pilgrim
F. Young, SRI, BV-2
P. Tam, LPM, NRR
Robert J. Bores, DRSS
I
RT4pP RI:DRP
R :bD/P / ph
epfl/meo Wenzinger
6/16/87 Tipp,[
h g (o [17
0FFICIAL RECORD COPY
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