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MONTHYEARML20097A3591992-05-28028 May 1992 Forwards Response to NRC 910628 Request for Addl Info Re Turbine Valve Surveillance Testing.Based on Westinghouse Rept,Total Turbine Missile Generation Probability Meets Appropriate Turbine Sys Reliability Criteria Project stage: Request ML20127B6621992-12-30030 December 1992 Forwards Rev 1 to Proposed OL Change Request 16 to License NPF-73,changing Spec 3/4.3.4 by Extending Test Interval for Reheat Stop & Intercept Valves to 18 Months Project stage: Other 1992-12-30
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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:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct 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 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 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-99-037, 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-99-012, 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-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC 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-99-104, 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 ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03
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Text
A t
Beaver Valiey Power Station
, SNppmgport, PA 15077-0004 (412) 393-525$
JOHN D StEBEft vse pres oent - wuciear oroup Flay 28,1992 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Subject. Beever Valley Power Station, Unit No. 2 Docket No.30-412, License No. NPF-73 Turbine Valve Surveillance Testing (TAC M77640)
Ref: 1) Letter from A. W. De Agazio (Nuclear Regulatory Commission) to J.D. Sieber (Duquesne Light Company), dated June 28, 1991. Subject -
Request for Additional Information Ref: 2) Letter from J. D. Sieber (Duquesne Light Company) to the NRC, dated October 1, 1990. Subject -
P oposed Operating License Change Request No. 16 This letter provides a response to the NRC Request for Additional Information (RAI) forwarded by Reference 1. Baaed on the attached Westinghouse report it has been determined that, with an eighteen (18) month reheat stop and intercept valve test interval, the total turbine missile generation probability for Beaver Valley Power Station Unit 2 meets the appropriate turbine system reliability criteria.
Our proposed technical specification revision, submitted by Reference 2, will be revised to propose a reheat stop and intercept valve -test interval of 18 months. The revieed submittal will be forwarded in the near future.
In response to the concerns raised by the Salem turbine overspeed event, as described in Information Notice 91-83, a surveillance program is being developed to functionally verify the operability of each turbine trip solenoid valve on a refueling frequency. This program along with turbine surveillance tests and inspections -will ensure the turbine overspeed protection system is maintained and operated consistent with the assumptions used in the attached evaluation.
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PDR -ADOCK 05000412 P PDR ,
- - - - . - _ - - _ _ _ _ . _ . . l
A
' Turbine Valve Surveillance Testing (TAC M77640)
Page 2 9
Should you have any questions regarding this response, please contact Mr. Ken McMullen at (412) 393-5214.
Sincerely, N D. Sieber my cc: Mr. L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. A. W. De Agazio, Project Manager Mr. M. L. Bowling (VEPCO) 1 v - - _ _ _ - _ - . - _ - - _
6 REQUESTfFOR ADDITIONAL-INFORMATION
. TURBINE REHEAT STOP AND: INTERCEPT-VALVE-TESTING ^
Reauest
- 1. Please submit information relating to_the probabilities 1for missile ejection over the entire spectrum of overspeed conditions.
Response
Based on the Westinghouse evaluation (documented in the attached report),- it has been determined that with an eighteen (18) month reheat stop- and intercept ~ valve _ test interval, the total _ turbine missile generation probability for Beaver Valley Power Station Unit-2 meets applicable _ acceptance criteria.
Three _overspeed events- were'- considered in . evaluating- the probability -for missile- ejection: design overspeedL(120 percent of-rated speed), : intermediate;overspeed-(132 percent of rated speed),
and destructive overspeed -(speeds greater than 170 percent of rated-speed). The Westinghouse- evaluation focused
- cn1 the design and intermediate overspeed events < since theyz would-beLaffected by-the test' -intervals of the reheat stop valves and intercept valves. :The destructive overspeed _ event does not result fror failures of reheat stop and intercept valves and therefore was excluded from further consideration.
Table 2- of the Westinghouse report _ presents the_ total probability of -turbine missile ejection for the design and intermediate _overspeed1 events- given. that system separation occurs. The total probability is based on conditional probabi.lities of missile-ejection for Unit--1 given that design' or intermediate overspeed. occurs.-
-. Unit- .1 conditional probabilities Eare more conservative than values calculated-for. Unit 2.
The total- probabilities for a. missile ejection must_be-multiplied Eby_.the average annual frequency of system' separation for the: Unit so that they can be measured >against' acceptance: criteria. ' Based on a reviewu of Unit 2 plant. trips, -the average annual frequency 1of-system separation was: -calculated--to be 0.22 -(one occurrence in'four.and -
one-half -years). -To -provide additional 7 conservatism, the average annual frequency Lof system : separation was assumed to be one-half (0.5).
The -Westinghouse report Ldid -not consider _desbructive.overspeed progability. Therefore,, the " general"~ acceptance: criteria-'of 1 x-110~ per year for- turbine missile Lejection-- from1 an unfavorably _
oriented turbine was reduced. A ten (10)Lpercent. fraction of the'
" general"- acceptance criteria.was assumed asithe acceptance criteria for (the ' design- -and intermediate overspeed- missileE probabilities
-ev~luated. -Thisa11 eaves an adequate reserve-margin of-90 percent of
_the acceptance criteria for other significar.t overspeed events such as destructive _overspeed.
t
' Request For Additional Information Turbine Rehent Stop'and Intercept Valve Testing Page 2 The product of the average annual-frequency of turbine separation for Unit 2 (conservatively assumed to be 0.5) and e total '
probability of turbine missile ejection (6.79 x 10 y) is- less ,
than the acceptance criteria of 1 x 10 . mus, the turbine system reliability is acceptable with an eighteen (18) month test interval for reheat stop aM intercept valves.
Beauest
< 2. Provide a discussion of the availrble data relating .to testing-the subject valves that could justify DICs conclusion regarding the reliability of the overspeed protection system.
Response
During the operating life of Beaver Valley Power Station Unit 1 and Unit 2 there has not been a single incidence of unplanned turbine overspeed nor a single turbine reheat- stop cr intercept valve malfunction that could have lead to-a turbine overspeed condition.
We Unit 1 reheat stop and intercept valves were tested during Unit start-ups and monthly thereafter until 1987. 'Ihe monthly testirg at Unit 1 was discontinued in 1987 when it was found to be 4 causing moisture separator reheater damage. Since 1980 the Unit i reheat stop aM intercept valves have undergone 31 operational surveillance tests (OST 3.26.1) .
We Unit 2 reheat stop and intercept valves have been tested during Unit start-ups aM monthly thereafter. Since the inception of operation in November of 1987, the Unit 2 reheat stop aM intercept valves have been tested at least 43 times (per OST 2.26.1) and continue to be tested on a monthly frequency.
Problems were encountered during performance . of 12 of the 31 surveillance tests at Unit 1. In these instances a limit or permissive switch associaced with the test circuitry required adjustment or repair. 'Ihese adjustments and repairs only .affected the test circuitry and did not represent a pc sibility for turbine overspeed since subsequent tests or plant trips showed that the valves operated as designed. 'Ihe other nineteen (19) of the 31 surveillance tests were conpleted satisfactorily with no problers.
In addition, the valves operated properly on 10 plant trips (closing on the turbine trip aM opening on the subsequent plant start-up) .
Each of the 43 operational surveillance tests performed at Unit 2 were completed satisfactorily. %at is, full reheat stop and intercept valve strokes were verified.
Request For Additiortal Information Turbine Reheat Stop and Intercept Valve Testing Page 3 e Minor problems were encountered during performance of 16 of the 43 surveillance tests at Unit 2. These problems typically involved a test push-button or valve position indication. In each case the problems would not have preventcd the reheat stop and intercept valves from closing in the event of a turbine trip.
The Beaver Valley data regardirg reheat stop ard intercept valve testire dia' m M above along with the attached probability analysis (based on the Westirghouse program for tracking turbine valve failure rates) provides evidence that the reheat stop and intercept valves are reliable.
Recuest;
- 3. Timely detection ard correction of any problem (e.g.,
nechanical problem) that my arise in the main steam turbine system, includity the subject valves, is vital because of the potential for serious adverse consequences. Please address the plant-specific aspects of this concern as it relates to the propcsed deletion of surveillance tests for the subject valves.
Response
A proposed revision to the technical specifications will be sutrtitted to charge the requested reheat stop and intercept valve test interval to an 18 mmth frequency. The 18 raonth test interval is adequate to identiP/ and correct rechanical problems based on the favorable probability analysis described in response to Item 1 above, and the -favorable valve test experience described in response to Item 2 above. In addition, the turbine is inspected periodically as described in Updated Final Safety Analysis Report Section 10.2.3.5.
EeElest
- 4. Frequent testing of the subject valves at Unit 1 is rot required by the technical specifications, but DLC does perform testing prior to start-up. However, DIf asserts. that even these relatively infrequent tests have caused extensive damage. In view of this experience, please explain how DIE expects to avoid such damage to Unit 2 since DIC has committed to verify proper operation of the subject valves during each plant _ start up as is done at Unit 1.
J
Roquest For kklitional Inforriation
'Ibrbine Reheat stop and Intercept Valve 'Ibsting Page 4
Response
'Ibe damage _ described at Unit i resulted from testing conducted during power operation. During testing of an intercept /stop valve, closure of the _ valve results in the shut-off of cycle steam flw to one (1) noisture separator reheater (MSR) and diversion of flw mostly to the opposite side MSR.
When this testing in conducted at power, significantly -higher shell side (cycle steam) velocity (flw) rates and corresponding pressure drops occur. 'Ihese pressure drops can cause high stress levels in the shell- side closure plates. At the ssm time, the heat transfer across the three (3) active tube bundles is increased due to higher shell side flw arri this causes additional reheat steam to be cooled in the tubes resulting in larger tube side pressure drops. 'Ibe cumulative effects from a series of intercept /stop valve tests performed at power are considered the primary cause of the shell side closure plate damage.
Tests conducted during start-up demonstrate that valve stem sticking is not occurring, ard the .uts are performed at lower flw rates which result in lov * ;ressure drops and stress levels that are not as likely to cause MSh werage.
CALCULATION OF TURBINE MISSILE EJECTION PROBABILITY RESULTING FROM EXTENDING TIIE TEST INTERVALS OF INTERCEPTOR AND RElIEAT STOP VALVES AT BEAVER VALLEY UNITS 1 AND 2 prepared: April 11,1992 A calculation of the effects of extending the test intervals of the turbine interceptor and reheat stop valves at Beaver Valley Units 1 and 2 was perfonned using fault tree models and methodology from the Westirr, Souse report WCAP-ll525, "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency," dated June 1987. 'Ibe calculation considered the probabilities of turbine missile ejection due to overspeed. The evaluation focused on two of the three overspeed events defined in WCAP-ll525 that would be affected by the test intervals of the reheat stop valves (RSVs) and interceptor valves (IVs); design and intermediate overspeed. The third overspeed event in WCAP-Il525, destructive overspeed, de s not result from failures of RSVs and IVs and was not included in the calculation.
Design overspeed is considered to be an overspeed of 120 percent of rated speed and results from the following failure sequence:
- 1. System separation (total loss of load) occurs. (This event is not moceled or accounted for in the analysis. Its frequency should be determined by Duquesne Light Co. before applying acceptance cdteria.)
- 2. One or more govemor (control) valves or two or more IVs stick open, or the initial protective action of dumping the govemor and interceptor valve emergency trip fluid header fails upon loss of load or upon reaching the setpoint of the overspeed protection control system.
- 3. Stop and reheat stop valves close successfully after reaching the overspeed trip setpoint.
IntermMiate overspeed is considered to be an overspeed of 132 percent of rated speed and results from the following failure sequence:
- 1. System separation occurs.
- 2. One or more combinations of RSVs and IVs (in the same steam path) stick open or fail to close.
- 3. Stop valves close successfully after reaching the overspeed trip setpoint.
Because the stop valves or governor valves must close to limit the overspeed and prevent destructive overspeed, the mechanical overspeed trip function a d dump of the autostop oil 1
system is assumed to be successful. Herefore, failures of the components of mechanical overspeed trip, including the interface valve and 20/AST solenoid valve which dump the emergency trip fluid, ws.w not modeled in the fault trees. Referring to item 2 of the design overspeed event, failure of the overspeed protection control (OPC) system and related solenoid valves, and failure of the 20/AST solenoid valve which dumps the autcstop on upon loss of load were considered in the analysis of design overspeed.
Three test intervals of the RSVs and IVs were considered; 3 months,12 months, and 18 months. Test intervals of the OPC solenoid valves and 20/AST solenoid valve were assumed to be 18 months in order to provide a bounding estimate of the failure probabuity of these valves. The failure rates of key components of the analysis are given in Table 1.
Turbine overspeed probability results are given in Table 1. Design overspeed is minimally affected by the extension of the IV and RSV test intervals because the overspeed is dominated by the failure of the control valves. His dominance is shown in Table 3.
Intermediate overspeed probabuity increases significantly with the extension of the IV and RSV test intetval. However, the products of intermediate overspeed probability and conditional probability of missile ejection, using the data from Table 2, are all small numbers, ne probabilities of turbine missile ejection are calculated in Table 2. Rese probabuities can be multiplied by the average annual frequency of system separation for the Beaver Valley Units so that they can be measured against acceptance criteria. He frequency of system separation typically ranges from 0.1 to 1.0 per year for plants that are equipped with reverse power relay systems. Rese systems delay the trip of the generator following a trip of the turbine for approximately 30 seconds or until there is adequate assurance that overspeed will not occur following a turbine trip which occurs prior to generator trip.
He acceptance criteria in WCAP-11525 was applied to a " total" probabuity of turbine missile ejection which summed the turbine missile p:obabilities for all known everspeed events. The analysis for Beaver Valley did not consider destructive overspeed probability or other possible causes of over md such as reverse steam flow through failed extraction non-return valves.
Therefore the " general" acceptance criteria of 1.0E-05 per year for turbine missile ejection from an unfavorably oriented turbine would not be applicable. Hewever, it would be reasonable to allocate a fraction of the " general" acceptance criteria (5 to 10 percent, nr example, but no more than 25 percent) for the design and intermediate overspeed missile probabilities evaluated herein. His would leave an adequate reserve msrgin of 75 to 95 percent of the acceptance criteria for other significant overspeed events such as destructiv-overspeed.
2 m .
. , ,a TABLE 1 Turbine Overspeed Probabilities as Function of Interceptor Valve (IV) and Reheat Stop Valve (RSV) Test Interval IV & RSV P(A) P(B)
Test Interval 3MO 1.12E-02 1.24E4 12 MO 1.14E-02 9.81E4 18 MO 1.15E-02 1.96E-05 Notesi P(A) Probability of design overspeed (120% overspeed) given that system separation occurs.
P(B) Probability of intermediate overspeed (132% overspeed) given that system sep~ation occurs.
m KEY DATA Component Failure Mode Failure Rate Basis (1/hr) (See Notes Below)
Interceptor valve sticks open 2.915-07 A Reheat stop valve sticks open 2.91E-07 A Control valve sticks open 7.27E-06 B Emergency trip fluid line (common to 6.97E-08 A govertw and interceptor valve) is clogged 20/OPC solenoid valve failure 1.67E-06 C Notes:
- A Original failure data from WCAP 11525 Rev.0.
- B Curree' data base for BB 296 nuclear steam chest valves. %e current failure data consists of 24 incidents of stickhg in 754 valva operating years. This data is crrrently under further revi:w ard documentrtion in conjunction with the Westinghouse program for tracking mrbine valve failure rates.
- C Utilizes criginal WCAP 11525 valve operating years (4620 years) but assumes 50 incidents for the calculation of the failure rate for failure to close.
3
TABLE 2 Probabilities of Turbine Missile Generation Affected by 'nterceptor Valve (IV) and Reheat Stop Valve (RSV) Failure IV & RSV P(A) P(hCA) P(B) P(M/B) P(T) =
P(A)*P(M/A)+P(B)*P(M/B) 4 Test 120 % 132 %
- Interval Overspeed Ovenpeed 3.60E-05 1.24E-06 1.35E42 4.20E-07 3MO 1.12E-02 ,
12 MO 1.14E-02 3.60E-05 9.81E-06 1.35E-02 5.43E-07 18 MO 1.15E-02 3.60E 1.96E-05 1.35E42 6.79E-07 Notes:
P(T) Probability of turbine missile ejection given that system separation occurs. These probnbilities are multiplied by the aserage annual frequency of system separation to obtain annual probabilities of turbinc missile ejection.
P(A) Probability of design overspeed.
P(B) Probability of intermediate overspeed.
P(M/A) Conditional probability of missile ejection given that design overspeed occurs.
. P(M/B, Conditional probability of missile eje: tion given that intermediate overspeed occurs.
i KEY DATA Conditloaal Probabilities of Missile Ejection ,
LP. Rotor Beaver Valley 1 Beaver Valley 2 l Operating Time l (years / hours) P(M/A) P(M/B) P(M/A) P(M/B)
)
3/26280 1.13E-06 1.72E-03 4.23E 08 1.90E-04 l
3.60E-05
- 5/43800
- 7/61320 - 2.52E45 3.85E-02 2.96E45 ~ 9.71E-03
(*) 'Ihe calenlation of P(T) above utilizes the Unit 1 conditional .
probability data. The operating time of the L.P. rotors is assumed to not exceed 5 years or 43,800 houn between inspections. 'Ihe 5 year values have been used in the calculation above.
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TABLE 3 Importance Factors of Dominant Faults Contributing to Daign and Intermediate Overspeed probabilities IV & RSV 1mportance Freton
' " ' latermediate Ovenpeed Design Overspeed 3 MO A(94.68) B(85.36)
D( 4.09) D(55.34)
E(0.65) C(38.40) l 12 M O A(93.28) B(94.56) '
D( 4.03) I'QO.68)
E( 2.04) .>(25.26) 18 M O A(92.32) B(95.68)
D( 3.99) C(77.84)
E( 2.94) D(18.ti6)
Notes: ,
- Importance factors are detennined by summing the importances of all cusets in which the fault appears.
- The letters A through O cornspond to the following basic faults:
A Control valve (CV) sticks open.
B Reheat stop valve (RSV) sticks open.
C Interceptor valve (TV) sticks open.
D Emergency trip Guld line (common to govemor and interceptor valve) is clogged.
l- -E Two interceptor valves stick open due ta common cause.
F Dump valve /RSV - sticks closed. ,
O Dump valve /IV - sticks closed.
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