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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
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20059E0601990-08-0707 August 1990 Requests That Proprietary Suppl 3 to WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, Be Withheld Per 10CFR2.790(b)(4) ML18094B4141990-03-27027 March 1990 Outlines Plan & Basis for Plan to Update Steam Generator Tube Fatigue Evaluations Performed by Westinghouse in Response to NRC Bulletin 88-002 ML20246H2601989-08-28028 August 1989 Requests That Suppl 2 to WCAP-12093, Addl Info in Support of Evaluation of Thermal Stratification for Beaver Valley Unit 2 Pressurizer Surge Line, Be Withheld from Public Disclosure Per 10CFR2.790 ML20248E8731989-03-0101 March 1989 Application for Withholding Proprietary WCAP-12141, Beaver Valley Unit 2 Evaluation for Tube Vibration Induced Fatigue (Ref 10CFR2.790) ML20245H6201989-02-20020 February 1989 Requests Withholding of Proprietary Suppl 1 to WCAP-12093, Addl Info in Support of Evaluation of Thermal Stratification for Beaver Valley Unit 2 Pressurizer Surge Line, (Ref 10CFR2.790) ML20245G6811988-12-22022 December 1988 Requests That WCAP-12058, Resistance Temp Detector Bypass Elimination Licensing Rept for Beaver Valley Unit 1, Be Withheld (Ref 10CFR2.790) ML20151G3491988-06-16016 June 1988 Requests Withholding of Proprietary Suppl 7,Rev 0 to WCAP-10170, Westinghouse SPDS Design & Verification... Process for Beaver Valley Unit 1 Nuclear Station, from Public Disclosure (Ref 10CFR2.790) ML20154A6511988-04-13013 April 1988 Requests Proprietary WCAP-11799, Beaver Valley Unit 1 Evaluation for Tube Vibration Induced Fatigue, Be Withheld Per 10CFR2.790(b)(4) ML20236S0731987-11-0606 November 1987 Requests That Proprietary Suppl 2 to WCAP-11317, Verification of Fracture Mechanics Analysis Techniques Used in Support of Technical Justification for Eliminating Large Primary Loop Pipe Rupture..., Be Withheld Per 10CFR2.790 ML20236A9631987-10-26026 October 1987 Requests That Proprietary WCAP-11419, Westinghouse Setpoint Methodology for Protection Sys Beaver Valley Unit 1, Be Withheld,Per 10CFR2.790(b)(4) ML20235J4491987-09-18018 September 1987 Requests That Proprietary WCAP-11317,Suppl 1, Addl Info in Support of Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases... Be Withheld from Public Discloser Per 10CFR2.790 ML20237L3031987-07-0707 July 1987 Requests That Proprietary WCAP-11522, Response to NRC Question on LOCA Hydraulic Forces Analysis of Beaver Valley Power Station Unit 2, Be Withheld (Ref 10CFR2.790). Affidavit for Withholding Rept Encl ML20206E4521987-03-24024 March 1987 Requests Withholding of Proprietary Addl Info on Beaver Valley Power Station Unit 2 SER Confirmatory Issue 032, from Public Disclosure (Ref 10CFR2.790) ML20209B2041987-01-0909 January 1987 Requests Withholding of WCAP-11366, Westinghouse Setpoint for Protection Sys,Beaver Valley Unit 2, Per 10CFR2.790. Affidavit Encl ML20198J5121986-05-0606 May 1986 Forwards Nonproprietary & Proprietary Addl Info on SER Confirmatory Item 32 Re Analysis of Feedwater Malfunction Event.Affidavit Also Encl.Proprietary Info Withheld (Ref 10CFR2.790) ML20151Z3281986-01-28028 January 1986 Forwards Proprietary Affidavit AW-77-18 Re Withholding Proprietary WCAP-11061, Unit 1 & Unit 2 Differences Analyses,Accident Analyses Per 10CFR2.790.Affidavit Withheld NRC-85-3041, Requests That WCAP-9735, Multiflex 3.0 - Fortran IV Computer Program for Analyzing Thermal-Hydraulic-Structural Sys Dynamics (III) Advanced Beam Model, Be Expeditiously Reviewed & Approved1985-06-18018 June 1985 Requests That WCAP-9735, Multiflex 3.0 - Fortran IV Computer Program for Analyzing Thermal-Hydraulic-Structural Sys Dynamics (III) Advanced Beam Model, Be Expeditiously Reviewed & Approved ML20100E1051985-03-20020 March 1985 Requests That Proprietary Seismic Response Spectrum at Reactor Vessel Supports Be Withheld (Ref 10CFR2.790) ML20107G1131984-12-27027 December 1984 Requests Withholding of Proprietary Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Beaver Valley Unit 1, (Ref 10CFR2.790) ML20140D5721984-12-0404 December 1984 Requests Proprietary Rev 1 to WCAP-9736, Multiflex 3.0, FORTRAN-IV Computer Program for Analyzing Thermal-Hydraulic- Structural Sys Dynamics (III) Advanced Beam Model Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20101F7361984-11-0606 November 1984 Application for Withholding Study Re ESF Actuation Sys Setpoint Methodology (Ref 10CFR2.790) ML20098C8591984-08-14014 August 1984 Alleges That Unqualified Suppliers Awarded Contracts from Plants to Provide Flexible Conduits Unqualified Under IEEE Stds 323 & 344 Despite IEEE Bid Requirements.Meeting Re NRC Position on safety-related Installations Requested ML20093G8991984-06-0606 June 1984 Requests That WCAP 10565, Technical Bases for Eliminating Large Primary Loop Rupture as Structural Design Basis for Beaver Valley Unit 2, Be Withheld from Public Disclosure, Per 10CFR2.790 ML20083P7631984-03-0909 March 1984 Requests Withholding WCAP-10493, Third Cycle Performance of Beaver Valley Unit 1 Fuel, from Public Disclosure,Per 10CFR2.790.Authorizes Use of Affidavit AW-76-35 in Support of Util Request ML20082P8901983-11-10010 November 1983 Application for Withholding Proprietary Steam Line Break Blowdown Data (Ref 10CFR2.790).Affidavit Encl ML20074A0151983-04-20020 April 1983 Application for Withholding Proprietary WCAP-10196, Second Cycle Performance of Beaver Valley Unit 1 Fuel, Per 10CFR2.790.Affidavit Encl ML20028C7361982-12-31031 December 1982 Forwards Proprietary & Nonproprietary Incore Detector Thimble Reduction Study, Submitted in Support of 821216 Proposed Tech Spec Change Request 75.Proprietary Rept Withheld (Ref 10CFR2.790).Affidavit Encl ML20008G1421981-06-11011 June 1981 Advises That Facility Should Be Deleted from 810610 Part 21 Rept Re Missile Penetration Analysis ML19350C9491981-04-0808 April 1981 Authorizes Use of Encl Previously Furnished Affidavit for Withholding Portion of Cycle 2 Rod Misalignment Analysis (Ref 10CFR2.790) ML19347D4311981-01-21021 January 1981 Forwards Affidavit Requesting That Analytical Results of Impact of Increased Rod Misalignment on Peaking Factors Be Withheld (Ref 10CFR2.790) ML19347C7401980-12-23023 December 1980 Requests That Proprietary Info Submitted as Responses to NUREG-0737 Re Instrumentation for Inadequate Core Cooling Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML19249E8941979-09-19019 September 1979 Notifies of Failure of Personnel Fabricating Pipe Spools to Comply W/Asme Boiler & Pressure Vessel Code Re Welding Qualifications.Work Ceased Upon Issuance of Rept by Inspectors ML19289E6271979-03-23023 March 1979 in Response to 780922 Part 21 Rept,Informs That Injection Pumps Were Removed & Inspected Using Newly Established Criteria of Suppl 2, & Were Reinstalled on Engines.No Further Action Contemplated ML19289E6241979-03-22022 March 1979 Notification of Test Results Indicated in 780922 Part 21 Rept.Cites Three Causes of Injection Pump Failure.Concludes Pumps Are Now Adequate.No Further Action Contemplated ML19263D6021979-03-22022 March 1979 Notifies NRC Insp Completed Re Exhaust Rocker Arms of Two PC-2 Generator Sets.Unit Free of Potential Defects ML20083P7681976-08-13013 August 1976 Requests Withholding Info,Re Notification of Generic Problems Under 10CFR50.59(a) & 10CFR50.55(e) on Increased Temp in Upper Head & DNB Penalty Re Rod Bow,From Public Disclosure,Per 10CFR2.790.Affidavit Encl 1990-08-07
[Table view] |
Text
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ATTACHMENT A.
.(
Westinghouse Water Reactor an355 PlusburghPemsylvania15230 Electric Corporation Divisions December ,1982 CAW-82-74 Mr. Stephen A. Varga, Chief Operating Reactors Branch 1 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conunission.
7920 Norfolk Avenue 4
Bethesda, MD 20014
SUBJECT:
Reduction in Incore Detector Thimbles REF: Duquesne Light Company letter Carey to Varga, December 1982
Dear Mr. Varge:
The proprietary material for which withholding is being requested by Duquesne
. Light, Company is proprietary to Westinghouse and withholding is requested
] pursuent to the provisions of paragraph (b)(1) of Section 2.790 of the Consaission's regulations. Withholding from public disclosure is requested with respect to the subject information which is further identified in the j affidavit accompanying this application.
The proprietary material transmitted by the referenced letter supplements the proprietary material previously submitted. Further, the affidavit, AW-76-8, submitted to justify the previous material was approved by the Commission on November 9,1977 and is equally applicable to the subject material.
Accordingly, withholding the subject information from public disclosure is requested in accordance with the previously submitted affidavit, AW-76-8, a copy of which is attached.
Accordingly, this letter authorizes the use of the proprietary information and affidavit AW-76-8 by the Duquesne Light Company for Beaver Valley Unit 1.
' Correspondence with respect to this application for withholding or the accompany affidavit should reference CAW-82-74 and be addressed to the under-si gned.
Very truly yours, 8301140049 830104 PDR ADOCK 05000334 >
P PDR 1
Robert A. Wiesemann, Manager Regulatory & Legislative Affairs
, /bek L'
Enclosure cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC
AW-76-8' AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, de-poses and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that .the aver-ments of fact set forth-in this Affidavit are true and correct to the best of his knowledge, information, and belief: - -
t he'AlfMC?RR Robert A. Wiesemann, Manager Licensing Programs Sworn to and subscribed before me this // day of [bmI 1976.
d
. 1-. 04 4 &
/ Notary Public/
ue rc:-
,i.- in t.,V s. th n. i.. 13, 1978 CL Cw ;dMJ.4 e
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AW-76-8 .l l
(1) I:am Manager, Licensing' Programs, in'the' Pressurized. Water Reactor
._ Systems Division, of Westinghouse Electric Corporation.and as such, I have been specifically delegated the function of reviewing the proprietary information sought _ to be withheld from public dis-closure in. connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its. withholding on' behalf of the Westinghouse Water Reactor Divisions.
(2) I am making this Affidavit ~in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and-in con-
. junction with the Westinghouse application for withholding ac-companying this Affidavit. ,
(3) I have personal knowledge of the criteria and procedures utilized -
by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential com ercial or financial information.
(4) Pursuant to, the provisions of paragraph (b)(4) of Section 2.790 of the' Commission's regulations, the following is furnished for consideration by the Commission in determining whether the'in-formation sought to be withheld from public disclosure should be withheld. ,
(i) The information sought to be withheld from public disclosure
. is owned and has been held in confidence by Westinghouse.
1 5
_ _ _ _ _ _ _ _ _ . . _ . . . _ _ _ . - _, , , . _ . , _ _ , , , . , , . . _ . . , ,m. _ . . .. m, ,. _., ., -
AW-76-8' (ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.
Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidencs if it falls in one or more of several types, the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, ' tool, method, etc.)
where prevention of its use by any of Westinghouse's competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g. , by optimization or improved marketability.
u- - g , - , , - --,ev. ,
AW-76-8 (c) Its use by. a competitor would reduce his expenditure of resources or improve his competitive position in the design,- manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production cap-acities . budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future West-inghouse or customer funded developtrent plans and pro-grams of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Westinghouse, but must be '
treated as proprietary by Westinghouse according to agreements with the owner.
There are sound policy reasons behind the Westinghouse -
system which include the following:
l 1
(a) The use of such information by Westinghouse gives j
~
Westinghouse a competitive advantage over its ccm-peti tors . It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
I
. .- . Tf' AW-76-8 l
(b) It is information which is marketable in many ways.
The. extent-to which such'information is available to competitors diminishes the Westinghouse ability to.
sell products 'and services ~ involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure.
of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage _ is potentially.
as valuable as the total competitive advantage. If competitors acquire components of proprietary infor-mation, any one component may be the key' to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) U,nrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in those countries.
(f) The Westinghouse capacity to invest corporate ssets in research and development-depends upon the success in obtaining and maintaining a competitive advantage.
i r
i
AW-76-8 (iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
, (iv) Th'e information is not available in public sources to the .
- best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in the attach-ment to.Wesurghousa letter number NS-CE-1139, Eicheldinger to Stolz, dated July 19, 1976, concerning supplemental infor-mation for use in the Augmented Startup and Cycle 1 Physics.
Program. The le.tter and attachment are being submitted as part of the above mentioned program in response to concerns of the Advisory Committee on Reacter Safeguards with the new Westinghouse PWR's, which are rated at higher power densities than currently operating Westinghouse reactors.
This information enables Westinghouse to:
(a) Justify the Westinghouse design correlations.
(b) Assist its customers to obtain licenses.
(c) Provide greater flexibility .to customers assuring them of safe reliable operation.
(d) Optimize performance while maintaining a high level of
- fuel integrity.
l m.
n
-AW-76-8 (e) Justify operation at a reduced peaking factor with a
, wider target band Ethan normal.
- (f) Justify ' full power opera' tion and meet warranties.
Further, the information gained from the Augmented Startup and Cycle 1 Physics Program is of commercial value and is sold for onsiderable sums of money as follows:
(a) Westinghouse uses the information to perform and justify analyses which are sold to customers.
(b) Westinghouse uses the information to sell to its customers for the purpose'of meeting NRC requirements for full power licensing.
(c) Westinghouse could sell testing services based on the experience gained and the analytical methods developed using this ~information.
Public disclosure of this information concerning the Augmented Startup program is likely to cause substantial"h~ arm to the coiapetitive position of Westinghouse by allowing its com-petitors to develop similar analysis methods and models at a much reduced cost. ,
8 6
ww I
~
, g .- -
8- AW-76 .
The analyses performed, their methods.and evaluation repre-sent a considerable amount of highly qualified development effort, which has been underway for many years. If a com-petitor were able to use the results of the analyses in the attached document, to normalize or verify their own
. methods or models, the development effort and monetary expen-diture required to achieve an equivalent capability would
.be significantly reduced. In total, a substantial amount of money and effort has been expended by Westinghouse which could only be duplicated by a competitor if he were to invest similar sums of money and provided he had the appro-priate talent available.
Further the deponent sayeth not.
O m
e
.- , v - - - - - - v-- , -, . .-- . , ,-, .. . . - , -
l ATTACMENT C ~
Beaver Valley Unit 1 Incore Detector Thimble Reduction Study Methodology To assess the additional peaking factor measurement uncertainties asso-ciated with a-50% reduction in the number of moveable detector (M/D) thimbles, three full power INCORE power distribution maps from Beaver Valley Unit 1 Cycle 2 were regenerated with random deletions of 25 thimbles. For each of the Cycle 2 maps, five separate random dele-
~
tions were made, giving a total of 15 thimble deletion maps. The measured peaking factors from the thimble deletion maps were then com-pared with the measured peaking factors in the reference maps, i.e., the original Cycle 2 maps employing all 50 moveable detector thimbles. ,
These comparisons yielded the additional measurement uncertainties asso-ciated with the 50% thimble reduction. Estimates of additional measurement uncertainties were made for both FAH and F . Also, q
thimble deletion effects on the INCORE measured axial offset and core quadrant tilt were assessed in a similar manner.
To examine the effect of thimble deletion on measurement of off-nonnal power distributions, a dropped rod map from the Cycle 1 startup physics testing was regenerated with random deletions of 25 thimbles. The measured peaking factors from the thimble deletion maps were then com-pared to the reference map as for the normal operation maps described
- above.
2573F:6 d
Results Table 1 provides the INCORE measurement data for the Cycle 2 nomal operation reference maps and the thimble deletion maps. As indicated, the mean percent difference and one-sided 95/95 tolerance for FAH were
[ ]+ respectively. For F ,g the corresponding values (a,c) were [ ]+ respectively. Statistical combination of (a,c) thess values with current peaking factor measurement uncertainties will be discussed below. Also shown in Table 1 are the peaking factor assembly locations. Figure 1 shows the M/D locations for the Beaver Valley core.
The mean axial offset difference for the 15 thimble deletion maps was found to be [ ]+ while tne mean quadrant tilt difference was (a.c)
E 3! (ac)
Table 2 shows similar data for the Cycle 1 dropped rod map.
F3H Thimble Deletion Uncertainty The FAH measurement uncertainty appearing in the Beaver Valley Tech.
Specs. is 4%. This can be statistically combined with the mean bias and (KS) values from Table 1 in the following manner:
[ (a,c) r 3+
i I
2573F:6 t
l A discussion of the above expression is provided in Appendix A. When the values from Table 1 are inserted into the expression:
u
[' M F3 H (5M T.D. ) = [
= 1.047 Consequently, the FAH measurement uncertainty increases from 1.04 to 1.047 when 50% of the moveable detector thimbles are deleted. This result will be conservatively rounded up to 1.05.
[ (a c)
Y S
l 2573F:6
. , _ , , , . ._ , _ _ _ , _ _ _ , , , , , ,,_._,,___.m.,
\
E (a,c)
]+
1 FQ Thimble Deletion Uncertainty The expression for the thimble deletion Fg uncertainty is analogous to the FAH expression. The Tech. Spec. F g uncertainty is 5%. Conse-quently, from Table 1:
Fu,p 3+
(a,c)
-Q
= 1.066
. I I
i i
2573F:6 e
., , , . - , , ,- , .y,.-.. --w-.. - . - - -.,s ,,, , , - , , , ,.--,,m.,,7 g.a , .- ,
Conservatively rounded up to 1.07, this represents the appropriate Fg uncertainty for 50% thimble deletion. Furthermore, since Fxy is a component of gF ,1.07 is appropriate for F 9 as well.
1 Axial Offset and Quadrant Tilt 1
The mean change'in quadrant tilt was found to be only [ ]+ (a.c) l Similarly the mean change in axial offset was also quite small at ;
E ]+ These values' indicate that thimble deletion has (a.c) negligible impact on the core average axial power shape measurement.
Changes of this magnitude are not significant and will not adversely affect excore detector calibration.
l Off-Nomal Power Distributions l
The data in Table 2 generated from a Cycle 1 dropped rod map, is pro-vided to demonstrate that thimble deletion to the 50% level does not significantly degrade the ability of the moveable detector system to measure off-normal core power distributions. As Table 2 shows, the measured peaking factors for the thimble deletion cases are quite com-parable to the reference case. The measured tilt values also indicate that even with the reduction in thimbles, the quadrant tilt factor is adequately measured.
Technical Specification Changes Attachment A contains the requested changes to the Beaver Valley Tech.
i Specs. Note that the peaking factor uncertainties have been increased to reflect the additional uncertainties caused by thimble deletion. For F,F9 g , and FAH, the peaking factor uncertainty has been changed to a functional fom dependent on the number of available thimbles. The uncertainty has been assumed to ir. crease linearly from the nominal values to the 50% deletion values.
1 P
f: .
L L
- 2573F
- 6
- - . . , - - - , , - ., - , , ,,.,e . - . - -.,.s.-., n-,, .,,s.., .,.e
=
Conclusion With the inclusion of the additional peaking factor uncertainties in the plant Tech. Specs., it is concluded that o'peration of the moveable ,
detector system with 25 or more thimbles is acceptable provided that the appropriate uncertainties described above are applied to the INCORE measured peaking factors.
t 9
f 1
r P
[
2573F:6
. ~ , . - - - , , - - - -, -,,-- ,-- ~ --
.w. .~..-..a..'~ ~
^ :, < - .
- ~ ' ' ' - -
4
- TABLE 1 COMPARISON OF NORMAL OPERATION AND THIMBLE DELETION INCORE MAPS Core Cycle 2 Thimbles Meas. Meas.
i Power Burnup Deleted Meas. F0 Fo Meas. FAH Fan Tilt a Tilt + ~ AO -aA0**
Map (%) (MWD /MTU) (%) Fg Location % Otff* FAH Location % Diff* Factor (%) (1) (%) ,
~Y 12 99.7 931 Ref (a,b,c) 12 99.7 931 50 12 99.7 931 50 12 99.7 931 50 12 99.7 931 50 i 12 99.7 931 50 16 97.5 1552 Ref 16 97.5 1552 50
- 5. 16 97.5 1552 50 16 97.5 1552 50 16 97.5 1552 50 16 97.5 1552 50 i
18 100 1997 Ref 18 100 1997 50 18 100 1997 50 18 100 1997 50 18 100 1997 50 18 100 1997 50 Ref. - Del. x 100%
4
+ Atilt = (Ref. - Deleted) x 100% ~
^ ^ - ' ~ ^
.?a - _ . . , . . . ^<.c - ... u._. .. . a i . ~ . .
s k
TABLE 2 COMPARISON OF DROPPED R00 AND THIMBLE DELETION INCORE MAPS Core Cycle
Power Burnup Deleted Meas. Fg Fo Meas. FaH FaH Tilt a Tilt + AO aA0**
Map (%) (t1WD/MTU) (%) Fg Location % Olff* FaH Location % Diff* Factor. (%) (1) (1)
-+
3 12 30 0 Ref 2.207 (*
. 12 30 0 50 2.193 i
12 30 0 50 2.198
, 12 30 0 50 2.199
- 12 30 0 50 2.232
$ 12 30 0 50 2.185 i
Ref. - Del. x 100%
+ Atilt = (Ref. - Deleted) x 100%
4 ,
I j
_ _ _ - _ _ _ _ _ _ _ - . - - - _ , _ -m.- _r
- ,w, .. , w --- 9 _. , __3 y- -
i
.i TABLE 3 QUARTER CORE MEASURED PEAKING FACTORS Syuuntric Syuuntric Map FAH Locations Fg Locations (a.c)
[
n 3+
4 9
l 4
2573F:6
_. + . -
e . mm e .m - ~ e m w . e . aue .s s . - . , es ;. s , e ,
RPNM LKJHG F EDCB A
.I
O, C
@ C*@ O @
4 o . .
. - O*O C * @ @
6 0 @
7 00 * ,
. o @ @ o o O
O + = 10 11
.O
. O @
13 14
is
- 00 Flcw Mixing,Thermocouples and Inco e Movable Detector Locations o Thermocouple (si)
Flow Mixing Device (47) g Incore Movable Detectors (50)
FIGURE l INSTRUMENT LOCATIONS '
,i
Fiqure 2 M
Percent Differenceso in Reaction Rate integrals A P N M L K . .J ...H. . .G . . F E D C a n
. . 7.1. .
1 . . . .
. .- . . . . 5.6. .
2 . . . . . . . .
. .5. . . -1.5. 2.6. . . . 5.7
- 3 . . . . . . . . . .
1 . . ... ... ... . . . . . . ... ... ... ... ... ..
21 . . . -1.4 . . .9. . -1.9. . . .
, 4 . . . . . . . . . . . .
. . .5. . -1.3. . -1.7. . . . .6. .2. . 5.3.
5 . .. . . . . . . . . . . . ..
. . . . -1.F. . . -1.0. . -2.7 . . . .
6 . . . . . . . . . . '. . . .
. . . .8. . . . -1.7. . -3.4. . . -1.2. . . 2. .
- 7. . . . . . . . . . . . . . . ..
~
. 8.9. . . 4. . .4 . .- . . -1.7. . . .6. 3.1.. .
- 8. . . . . . . . . . . . . . . .
4 .. . . . . -3.4.' . . . .5. -1.6. . . . . 8.2.
i 9. . . . . . . . .' . . .- .- . . ..
. . .9. . . . -1.7. . . . . -2.2. . 1.4 10 . . . . . . . . . . . .. . . .
.. . . . ... ... ... . . . . . . ... ... ... . ... ... ... 1 . .
. . . . -3.3. . . .5. . -1.2. -2.0. . . .
11 . . . . . . . . . . . . . .
. .2. . . . -5.4. . . . . .2. 2.0.
12 . . . .' . . . . . . . .
. . . . . -1.0. . .0. . .
13 . . . . . . . . . .
. 6.5. . . . .5. . .
1L . . . . . . .. .
. 4.0. . .
15 . . . .
1 i6 I .
. X 100%
Meas.
1 N
4 -A 7,
l I
1
~
-APPENDIX A' l Discussion of F"H 3 Expression The expression for the measured FAH difference as calculated in Table 1 is:
[ (a.c) 3+
4 i
l 2573F:6
. . , . . . , - , ,w %. -. -,.. - - - +,. _ ,.,m - , --
,--..,..-.---.-,,,-,.,-.-,,,.e -
[
]+ (a.c)
The 95/95 one-sided upper tolerance interval associated with the above error expression is:
(a,c) 3+
t 4
t I
l f
2573F:6 s .. , . - . - _- . . -_.
l l
Furthermore, since the .(MRR/PRR) ratios in the thimble deletion and reference maps have the same uncertainty: .
l (a,c) l E i 1
3+
The desired uncertainty, (H, can be expressed as:
[ (a.c) r I
~
]+
b Values for (KS)g and (KS)R from WCAP-7308 are [ ]* (a,c) respectively. These values are independent of thimble deletion and are components of the uncertainties in both F3 and FR 3
- f. Furthennore, (KS)g i s essentially (KS){f, defined in (A-5), and represents the 95/95 upper tolerance interval for the (MRR/PRR) ratios in the reference maps. From (A-1) it is vident that the (KS) for AFaH' IKSIFaH, intrinsically 2573F:6
$ w- , --ww -- , . .,, , . - -----v- -.e- + - -
-m-,--.-----.-.----a m , - -- *-- y
O TD includes-[ ]+ since the FAH expression includes FAH, the FAH value. (a.c) obtained by extrapolation from only [- ]+ of the total number of thimbles (a.c)
(versus the full complement of thimbles in the reference maps). [ .]+ (a,c) is essentially (KS)fD , the tolerance interval for the (MRR/PRR) ratios in the thimble deletion maps., (A-8) can be rewritten, then, as:
l [
(a,c) 4 2
]+
4 1 i
s 2573F:6 i
- . yD %*h 8444$ 6.45 *4 % $stp a4 6ggGism epga g,y,e%.p,awa , g
-. , _ ,-. , _ _ _ _ _ _ ,