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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:UTILITY TO NRC
MONTHYEARML20059L4271990-09-0707 September 1990 Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications ML20059G0821990-09-0404 September 1990 Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8 ML20059F7551990-08-29029 August 1990 Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining ML20059F1501990-08-29029 August 1990 Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829 ML20028G8731990-08-29029 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71 ML20059D3761990-08-24024 August 1990 Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant ML20028G8881990-08-24024 August 1990 Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned 05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990 Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued ML20058P7651990-08-14014 August 1990 Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc ML20059E0571990-08-10010 August 1990 Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4)) ML20059E7631990-08-0101 August 1990 Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory ML20059B8141990-08-0101 August 1990 Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations ML20056A3471990-07-31031 July 1990 Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed ML20056A1841990-07-27027 July 1990 Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon ML20055H2581990-07-25025 July 1990 Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b) ML20055F7061990-07-0909 July 1990 Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage ML20055D3871990-07-0202 July 1990 Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results ML20058K5031990-06-29029 June 1990 Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria ML20044A3661990-06-21021 June 1990 Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue ML20043G6811990-06-14014 June 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown ML20043H9341990-06-14014 June 1990 Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04 ML20043G5981990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1 ML20043G6851990-06-12012 June 1990 Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp ML20043G7941990-06-12012 June 1990 Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl ML20043G8001990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d ML20043H0291990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program ML20043F5251990-06-0707 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl ML20043F1361990-06-0404 June 1990 Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002 ML20043B5971990-05-18018 May 1990 Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531 ML20043B0511990-05-15015 May 1990 Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario ML20043B1921990-05-11011 May 1990 Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14 ML20042G9761990-05-0808 May 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601 ML20042G8541990-05-0303 May 1990 Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests ML20042G9071990-05-0101 May 1990 Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b) ML20042F1381990-04-30030 April 1990 Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990 ML20042F0991990-04-20020 April 1990 Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program ML20012F5951990-04-10010 April 1990 Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990 ML20042E1471990-04-0404 April 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization ML20012F6021990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed ML20012E3091990-03-23023 March 1990 Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation ML20012E3451990-03-23023 March 1990 Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl ML20012D6491990-03-19019 March 1990 Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus ML20012E4091990-03-16016 March 1990 Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI ML20012D6181990-03-15015 March 1990 Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled ML20042D7401990-03-14014 March 1990 Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89. ML20012D5801990-03-13013 March 1990 Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index ML20012D6221990-03-13013 March 1990 Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events ML20012C1791990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled ML20012E0911990-03-0505 March 1990 Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2) ML20012B7051990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G 1990-09-07
[Table view] |
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.1hVL
'Af Duquesne umt m;ee W 2) 92W60 Nuclear Construction Division Telecopy (412) 787-2629 Rr.,Nnson Plaza, Building 2. Suite 210 Pittsburgh, PA 15205 March 25, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Hugh L. Thompson, Jr. , Director Division of Licensing Office of Nuclear Reactor Regulation Mr. James P. Knight, Director Division of Engineering Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Soil-Structure Interaction - Additional Information
REFERENCE:
DLC letter 2NRC-5-016, dated February 1, 1985 Gentlemen:
In letter 2NRC-5-016, dated February 1,1985, we provided our response to the NRC Structural and Geotechnical Engineering Branch's (SGEB) Draf t SER open item on Scil-Structure Interaction. DLC's position on this issue, which is stated in detail in that submittal, was discussed with members of the SGEB and Licensing Branch in a telephone conversation on February 12, 1985. In this conversation, the SGEB indicated that their position remains as stated in our November 30, 1984, meeting with them. The SGEB position requires that DLC provide a soil-structure interaction analysis with the free-field ground surface mation applied at the containment structure fo unda t ion level.
However, the SGEB gave no indication as to whether they would address this
! req ues t for information as a backfit as requested by DLC in our February 1, .
1985, submittal.
DLC's position as provided in our February 1,1985, submittal, can be summarized as follows:
The information on soil-structure int eract ion that exists on the BVPS-2 docket provides a complete record fo r the satisfactory closure of this _ issue. Included on the BVPS-2 docket are two tech-nically appr opriate so il-s truct ure interaction analyses (a finite element method analysis and a Kausel-Whitman, three-step me thod analysis) which demo ns trat e that BVPS-2 meets the underlying requirements of SRP 3.7.2.11.4. DIC believes that perfo rming additional soil-s truc tur e interaction analyses using alternat ive methods will provide no meaningful additions to the existing record.
In particular, DLC believes that the analysis requested by the SGEB 8504010188 DR 850325 ADOCK 05000412 h PDR g g u __-
1
' q.
-.. 'U;it d Stctsu Itclect Rsgulttory Coausission
- Mr. Hugh L. Tho pson, Jr. , Director WA + Mr (J ame s . P . Knigh t , Director-Soil-Structure-Interaction . Additional Information
, ;Page ;- 2 would yield results.diich are neither physically representative of the actu'a1.siteiconditions'nor technically appropriate.
To obtain an . addi tional review of our position, DLC has assembled a
> ' panel of L consult ant s' i > evaluate .the . soil-structure. interact ion analyses . that
= have l been docketed J ,fori EVPS-2. . The ~ panel consists of the following
-individuals: .
E.M.KauselhPh.D.(MassachusettsInstituteofTechnology)
J . M. Roesset , Ph.D (University of Texas at Austin)
J; Lysser, Ph.D -(University of California ;at Berkeley)
- 1. M. Idriss,'Ph.D (Woodward-Clyde Consultants)
'D. E. Shaw, P.E. (Consultant)
C.LW.4Lin, Ph.D (Westinghouse Electric Corporation)
To accomplish the . evaluation, representatives of. . DLC and Stone &
Webster Engineering Corporation (SWEC) met with the panel; members at . SWEC of fices Din .- Boston, MA , on -February 4, 1985. SWEC presented the docketed
- x. . soil-scructure interaction analyses _ t6 the panel at that meeting and the panel members were requested; to: provide written evaluations ' based on their review Lof these analyses. These - evaluat ions have been provided and 'are -
attached..
DLC ' believes that c the' attached evaluations further substantiate our 7" position.' We' would again like to ' state our-willingness to meet with the SCEB staf f and appropriate NRC management personnel to clarify any : point s . in this
- or ; previous submittals if you feel'such a meeting would facilitate the reso-
~
6 .lut ion ' of this - issue. We would appreciate being informed as soon as .possible of- the NRC's status on this issue in order to avoid any unnecessary delays in re' aching a resolution.
.DUQUESNE-LIGHT COMPANY-
-SUBSpIBEDAND WORN TO'BEFORE ME THIS g AY OF ~ ,
d() , 1985.
- 42) h- M By . /
/m Notary Public yJ . arey Vice cesident
[/ '
' - - :d:EiLA LL FATTORE fl0TARY FUSitC s SHiPPIECPSRT Bart0, SEAVE1 COUkTY
- ' MY CCUMISMN EXP!EES SEPT.16,1985 lacmber,Pennsyimia Associatica cf Notnies
~
)D0/wjs
'A t t achment lcc: Dr. W. fKerr, - ACRS (w/a)
- . Dr. D. Okrent, ACRS (w/a)-
=
- Dr. C. P. . Siess, ACRS (w/a)
Mr. G. E. Lear, NRC SGEB Chief (w/a)
Mr. B. K..Singh,. Project Manager (w/a)
Mr.; G. Walton, .NRC Res ident Inspector (w/a) p c* .
..f.
[Unitied States Nuclear Regulatory . Commission
~
i Mr. Hugh L. Thompson, Jr.,. Director iMr. James P. Knight, Director
- Soil-Structure Interaction - Additional Information
.Page 3 COMMONWEALTH OF-PENNSYLVANIA )
) SS:
COUNTY OF BEAVER- )
)
On this [ M day'of g _, ,/ @ [6 , before me, a Notary lPublic in and-for said' Commonwealth and County, personally appeared J. J. Carey, who being duly sworn, deposed and said that (1) he'is Vice President of Duquesne Light, (2) he is duly authorized to execute-and_ file the foregoing Submittal on behalf of said Company, and (3). the statements set forth in the . Submittal are true and correct to the best of his knowledge.
N -
/ Notary Public
- HEllA LL FATTORL Il01ARY PUBUC Sill?PlK; PORT BOE0. BEAVER C0'J'4TY MY COVMlut0N EXPIRES SEPT. IG.193 uen3er, Peerf.nnia Anestica of Em}
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CAussiooE Massachusetts o2:30 Feb. 7,1986 PwCNE 16t7' 253- 5336 Dr. John T. Christian Stone'&WebsterEn@neeringCorp.
245 Sumer St.
Boston, MA 02107- -
Ref.: Seismic Analyses, Beaver Valley 2 Nuclear Power Station
Dear Dr. Christian:
In the course of my work as member of a consulting board to Duquesne .-
Light .Co., I .had the opportunity to review in detail the procedures used by Stone & Webster in the analyses of the Beaver Valley 2 nuclear contain-ment structure for soil-structure interaction effects. This, letter is to give my strongest: endorsement to these analyses. Specifically, the following points.are worth emphasizing:
1)'- It is consistent with current practice and understanding to allow for reductions in the levels of earthquake ground motion in the free field result-ing from wave interference. Such reductions are a necessary corollary of the computational models used, and to ignore or suppress them is tantamount to violations of demonstrable-physical laws.
- 2) It can also be rigorously demonstrated that an embedded foundation .is subjected to an excitation that differs from the motions that would have been .
observed at that location in the absence of the structure (i.e., in the free field). Such an effect, as you well know, is referred to as Kinematic-Inter-action. Thus, analyses such as Stone & Webster's, which account for this phenomenon, provide a more realistic description of the actual seismic event.
On the other hand. use of the surface motion as input at the base of. the structure is clearly erroneous, and should be vigorously rejected by Stone and Webster. Its use may not only lead to grossly overconservative results at some points in the structure, but to unconservative results at others, especially at higher elevations.
3); A comparison shown to me between the results of a finite element idealiza-tion of the BV2 system and an analysis with a spring and dashpot model (account-ing for kinematic interactions) demonstrated excellent agreement, particularly when consideration is given to the widely different techniques employed. This is, perhaps, the strongest evidence that the analyses performed are beyond re ,
proach.
.x In conclusion..it is my conviction that the soil-structure interaction analyses performed by Stone and Websger conform with current technical stan-dards and state of the art.
S,incerely, s <f /
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y E. Kausel' Assoc. . Prof. of Civil Engineering EK/jm M.I.T., Room 1-271
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l Jose M. Roesset, Sc.D.
Consulting Engineer
- l 11909 Arch Hill Drive Austin, Texas 78750 Dr.- John-T. Christian Stone & Webster Engineering Corporation 245 Summer Street Boston.. Mase. '02107 ,
Dear Dr.-Christian:
, At the request' of Duquesne Light I have reviewed the -
- vario'us documents related to the seismic design and soil structure ,
interaction-analyses of the Beaver Valley Power Station #2, which -
were sent to me by Stone & Webster Engineering Corporation. These documents are: .
- 1. Attachments A and B to letter, dated February 1, 1985, from E.'J.;Woolever, Duquesne Light Company to U.S. N.R.C. attention-George.W. Knighton.
~ 2. , Sections 3 71 and 3 7 2 of the PSAR for the Beaver Valley Power Station,' unit 2.
l 3 Item 17 of attachment to letter, dated June 15,1984, from '
E.J. Woolever, Duquesne Light Company to U.S. N.R.C. attention George W..Knighton.. I In addition I attended a meeting at the offices of Stone
& Webster.on February 4: 1985,.in which the background history of the analyses and the results obtained from the various models were presented by the Structural Staff of SWEC. Questi'on- on the details'of_the analyses were: asked at the. meeting and answered. by SWEC.
On the basis.of'these documents and the presentation of
-February 4', it is my opinion that the soil structure interaction' analyses ' for' the- containment ' building of the Beaver Valley Power f Station..wnit 2, have been performed in a rational and competent-
- - manner, in e way which is in fact very similar to what I would
,have suggestad or requested myself.
The analyses d'escribed in:the Beaver Valley Power Station unit 2 PSAR were conducted using a two dimensional finite element model with-the program PLAXLY, which is essentially the same as .
FLUSH.- This was for many years the best available state of the -
art 1 technique in engineering practice and it was widely used. The ,
-most significant question that had been raised in relation to the accuracy of this type of solution concerned the two dimensional
' idealization.
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-The.new analyses were aonducted using the three step, substructure or impedance approach using a three dimensional ideali-zation.of the soil'and:the foundation. This is the procedure I
-personally would prefer. A comparison of the results from the two series of analyses indicates good agreement, with the selected
. design' spectra enveloping.both' solutions. This provides a desirable check:on the reasonableness ofLthe results. since different approxi-
- mations wereLinvolved in the two formulati'ons.
I-understand a question has been raised.about the fact'that the= control motion was specified at the fr'ee surface of the soil. ..
This'~is, in my~ opinion, the best approac'h. A concern was raised some. years ago about the fact that the" corresponding, deconvoluted,-
~
. -motions at_the foundation level in the free field would exhib i t very sharpmvalleys in their response-spectra ar'ound the natural frequency
- of:the embedment layer. It is important to realize that a) these valleys are not so sharp _when performing a kinematic inter-action analysis and determining the motions at the foundation level
. accounting-for the geometry of the excavation and the stiffness of the foundation, instead of the free field.
b) _'the-foundation motions resulting from kinematic interaction have both a translational and a rotational component. Their combination imay produce higher responses in some cases than direct use of the .
control motion-at the foundation level. There is now mounting evi-
' dence that the: decrease in the high frequency range of the transla-tional motions predicted by theoretical considerations does in fact take place and the use of kinematic-interaction if the most reason-able and realistic approach from a physical point.of_ view as long as both translational and rotational components of motion are included.
c)- the existence of sharp valleys in.the response spectra is elimi-nated if analyses are conducted with logical variations in _the soil properties and the final results are enveloped. This is the approach that was.followed in the analyses for the containment building.
Figure B.4 of attachment B to the letter of February 1,1985, shows clearly that the envelope, design response' spectrum at the base of the' mat has only a very small dgerease over the spectrum of the contro1' motion in the range of 3 to 4 cps and is in fact larger at~
other frequencies. Thus not only is the procedure used correct but by enveloping results for various soil properties safeguards have been introduced to guarantee conservatism.
I do -not find from my review any point I would contest .or any issue that may lead to unrealistic or unconservative results.
Sincerely yours.
f.,./bIh4 7
Jose M. Roesset e
JOHN L_YS M EE R ,, Ph D-Engineering Consultant 1968 Marin Avenue Berkeley, Calffornia 94707
- (415) 521-2615 Files SWE501B/EWS February 8 , 1985 --
Dr. John T. Christian Stone & Webster: Engineering Corporation P.O. Box 2325
-Boston, Mass. 02107 Suh. ject Beaver Valley Power Station - Unit 2 Seismic Soil-Structure Interaction Analysis
Dear Dr. Christian:
At the request of the Duquesne Light Company, I have reviewed Refs. 1, 2 and 3 which relate to the seismic soil-structure interaction analysis of the above plant. On February 4, 1985, I participated in a. full-day-meeting in your offices during which your technical staff presented further details and results of the different analyses, which have been performed for the containment structure of the plant.
I as pleased to' confirm that: I consider your-methods rational and in agreement with the current state of the art of seismic interaction analysis. By your methods, I refer.to the complete finite element analyses perforned by the computer program PLAXLY and the so-called 3-Step Method, including the kinematic
' interaction step. This last step must be included for the method to yield'a proper solution to the equations of motion.
I agree that. the' seismic input motion is best defined at the ground. surface in the free field. This does not conform with the most.recent version, Rev. 1- July 1981, of the U.S. NRC Standard Review Plan, Section.3.7.2, ,I I , Paragraph 4.iii, which specifies that the controlling motion should be specified at the foundation level in the free field. This provision, however, has no rational basis and leads to unrealistic results if applied. A detailed explanation- of this statement is given in Ref. 4. and there appears to be consensus within academic community on this matter.
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You have in my-opinion provided adequate checks on your resultu which also agree- with my experience of how the plant should move if'sub.jected to the specified event.
Sincerely yours, f .
1 John Lysmer Professor of Civil Engineering
- Univ. of. Calif., Berkeley
References:
- 1. ' Attachments - A and B to letter dated February 1, 1985.
From: E. J. Woolever, Duquesne Light Company.
To: U.S._NRC, attention George W. Knighton.
2.. Beaver Valley Power Station - Unit 2 - F.S.A.R.,
Sections 3.7.1 and 3.7.2 ..
- 3. Item 7 of Attachment to letter dated June 15, 1984.
, From E. J. Woolever, Duquesne Light Company.
To: U.S. NRC, attention George W. Knighton.
- 4. Seed, H. B., and Lysmer, J., "The Seismic Soil-Structure Interaction Problem for Nuclear Facilities". Appendix to Johnson, J.J., " Sail-Structure Interaction: The Status of Current Analysis Methods and Research - Seismic Safety Margins Research Program". NUREG/CR-1780 or UCRL-53011, Lawrence Livermore Laboratory, January 1981.
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's "i*.cT;?:"" WoodwardiClyde Consultants (7141 835 6886 (213) 581-7164 Te!en 68 3420 ,
15 February 1985
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Dr. John T. Christian Stone & Webster Engineering Corpo.ation 245 Summer Street Boston, Massachusetts 02107 _
Dear Dr. Christian:
As requested by Duquesne Light Company and Stone & Webster, I have reviewed ; documents pertaining to the seismic soil-structure interaction (SSI) considerations for the Beaver Valley Power Station, Unit No. 2. The documents reviewed are the following:
- 1. Attachments A and B to letter, dated 1 February 1985, from E. J. Woolever, Duquesne Light Company to the USNRC, Attention: George W. Knighton.
- 2. Sections 3.7.1 and 3.7.2 of the FSAR, Beaver Valley .
Power Station, Unit No. 2.
- 3. Item 7 of the attachment to letter, dated 15 June 1984, from E. J. Woolever, Duquesne Light Company to the USNRC, Attention: George W. Knighton.
In addition, the results of the SSI analyses for this unit were presented by representatives of the Structural Engi-neering Staff of SWEC at our meeting on 4 February 1985 in Boston. These results covered analyses dating back to 1973-74 and included the most recent analyses completed in 1984.
Based on this review, I find that the SSI analyses completed by SWEC for this power plant are appropriate and are in accordance with the current State of the Art for conducting such analyses. .
Consutting Engineers. Geologists and Envwonmental Scientrsts Offces in Other Pnncipal Cat:es .
Woodward Clyde Consultants Dr.-John T. Christian 15 February 1985 Page 5 In particular, I an in full agreement that the design earth- ,
quake ground motic: s be specified at the finished ground surface and.that kinematic interaction be explicitly incor-porated ir the soil-structure inte raction analyses.
Very;truly yours, ..
Nw. % -
E M" I. M. Idriss IMI/hab e
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DONALD E. SHAW, P.E.
~
5558-C.Old William Penn Highway
. Export, PA 15632 (412) 327-0051 February 8, 1985 .
~
Project No. 84-020-03 Dr. John T. Christian Stone & Webster Engineering Corporation
~
- 245 Summer Street I l
Boston, MA 02107 Beaver: Valley-Power Station, Unit 2 Soil-Structure Interaction Analyes Dear Dr. Christians ..
As requested by you and Duquesne Light Company, I have reviewed the material describing the soil-struct'are interaction analyses performed for the Beaver Valley Power Station, Unit 2, (BVPS-2) which you supplied (Refs 1,2,and
- 3) .- Also, I, along with other. esebers of the Soil-Structure Interaction Assessment Panel met at Stone & Webster Engineering Corporation -(SIEC) offices on February 4, 1985, for a.-presentation of the soil-structure interaction analyses and results.
t
. Based en the material provided and the presentation, I find that the analytical methods used fqt the soil-structure interaction analyses of the BVPS-2 containment structure are consistent with generally accepted principles of soil-structure interaction analysis.
1; Specifically, I note the-following points:
- 1. The Tivee-Step analytical procedure includes kinematic interaction as a method for deriving the. vibratory motion (translational and rotational)
( at the foundation level of-the containment building from the free-field
! ground-surface motion. The use of kinematic interaction is physically appropriate and consistent with well-recognized principles of soil-structura interaction.
Seismic Analysis Earthquake Engineering Structural Dynamics I
L
.Dr. John T. Christian February 8, 1985 t
2.
The results of.the Three-Step soil-structure interaction agree very well with the results of the finite-element analyses performed using both the
- Pt.AXLY and F1.USH computer programs. This agreement is expected because the finite element method of- analysis implicitly includes the use of k.nematic interactt.on wnich is explicitly used in the Three-Step method
) of analysis.
- 3. ; l#ille I have I not reviewed the detailed numerical calculations used in -
the Three-Step analyis, the_ procedures _w hich were .used relative to ,
I strain-dependent soil properties, foundation rigidity,. % t effects
- - and compliance functions are consistent with my understanding of site p conditions and the structural configuration.
- 4. Response spectra of the vibratory motion at the foundation level computed by both the Three-Step method and the finite element analyses show the espected " dip" at approximately 2.5 Hz which is the natural frequency of the soil. layer between the ground surface and the base of '
the foundation. This dip in the response spectra is a result of physical phenomena andsis.less than would be.obtained in the free field -
'at the foundation level. By free-field motion at the foundation level I mean that action which is derived by simply deconvoluting the. free-field
ground-surface action without considering geometric effects of the foundation as included in kinematic interaction.
In view of these findings, I believe that the letC request to perfore soil-structure interaction annlyses using the Three-Step method with the free-field ground-surface. time histry applied at the -foundation level is physically inappropriate. It neglects the substantial-body of-evidence which has been generated over the past 15 years which exhaustively, demonstrates that
-the vibratory motion-at depth-is difforent from -the ground-surface action. '
Furthermore, I find that the soil-structure interaction analyses performed for BVPS-2. are consistent with the requirements of 10CFRiOO, Appendix A, as I understand thee, and that the -NRC request would be inconsistent with the regulations.
I might' add that a study which I performed for the P5tC while at DiAppolonia Consulting Engineers and published as NLNtEE/CR-0693 investigated 1thequestion of- where- ter apply- the control motion. It concluded that the
. control motion should be- applied - at the ground surf ace with the motion ~ at the founution level computed based on actual site conditions relative to soil properties and the depth bf the foundation. While the study did not consider the- eHects of foundation geometry .and rigidity as is.done in the kinematic interaction formulation.used intthe Three-Step analysis, the t use-of. kinematic interaction -is a refinement of the methods which wereiconsidered in the study.
_2_
Dr. John T. Christian February 8, 1985 I will be pleased to participate in any meeting with the NRC to clarify
.the above issues and will also be plensed to particpate in any formal
' presentations or hearings on this issue, if required. '
ectfully submitted, 4 _
Donald E. Shaw, P.E.
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DES /saa cc. Mr. Pedro A. Cadena, Duquesne Light Company Mr. Jack Onell, Duquesne Light Company 4
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l Dr. John'T. Christian February 8, 1985 -l l
LIST F REFEREE ES
- 1. Attach e ts A and B to Letter 2NRC-5-016, dated February 1, 1995, from E. J. Woolever, Duquesne Light Company, to U.S. NRC, attention George W.
Knighton.
- 2. Beaver Valley Poseer Station, Unit 2 -
F.S.A.R., Sections 3.7.1 and 3.7.2.
- 3. Item 7 of Attachment to Letter, dated June 15,' 1984, from E. J.
-Woolever, Duquesne Light. Company, to .U.S. MIC, attention George W.
Knighton.
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EM-CUL-352 Westinghouse Water Reactor Plant Engmeeneg Dmsion Electric Corporation Divisions g 333 PitisDurgh Pennsy:vania 1523C February 11, 1985 Dr. John T. Christian Stone and Webster Engineering Corporation 245 Jummer Street Boston, MA 02210 ..
Dear Dr. Christian:
SUBJECT:
Soil Structure Interaction Advisory Panel Review for BVPS-2 As a panelist of the subject panel, I participated in the review of the soil structure interaction analysis for Beaver Valley Power Station Unit -
No. 2. The review was primarily conducted to address the issue of whether the Kinematic Interaction technique is appropriate for the Unit No. 2 analysis, and whether the technique was properly applied by SWEC.
The objective of the review has been achieved based on the materials provided by the Duquesne Light Company (Refs.1, 2, and 3) publications in tne literature (Refs. 4 and 5), and the presentations made by SWEC -
engineers on February 4,1985.
Alth; ugh only limited detail was made available to the panel concerning the soil structure interaction analyses conducted by SWEC, the following points can be made as a result of this review:
- 1. When applying the soil spring approach in the soil-structure interaction analysis, free field motion should not be applied at the subgrade (embedment) level.
- 2. Kinematic interaction provides acceptable estimation to the motions at the subgrade (embedment level). Therefore, it is an acceptable approach in the so-1 structure inter-action analysis.
- 3. Comparison of the numerical data indicctes that the original finite-element analysis results as described in the BVPS-2 FSAR Section 3.7.2 for containment building are, in general, more conservative than the results obtained by the kinematic interaction approach.
~
Cir. ' John T. Christian Februa ry 11, 1985
- In conclusion, based on the information presented to me, I feel that Kinematic interaction technique is appropriate for developing the subgrade (embedment) motions in the soil _ structure interaction analysis
- using soil springs. Further, it appears that the results obtained for BVPS-2 using the kinematic interaction technique have shown that the
- original finite element soil structure interaction analysis results are -
conservative and, therefore, should continue to be used in the design and qualification process.
- Very truly yours,
/Yo r l1 C.-W. Lin, Advisory Engineer Engineering Mechanics rin cc: D. A. Bartol J. O'Neil (Duquesne Light Co.)
P. Cadena (Duquesne Light Co.)
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REFERENCES
- 1. Attachments.A and B to Letter, datedLFebruary 1,1985 from E. J. Woolever, Duquesne Light Co. ,
to U.S. NRC, attention George W. Knighton .
- 2. . Beaver. Valley
- Power Station - Unit 2 - F.S. A.R. Sections 3.7.1 and 3.7.2
- 3. Item 7 of Attachment to Letter,~ dated June 15, 1984, from.E. J. Woolever, Duquesne Light Co., ~'
to ' U.S. ~ NRC,-~ attention George W. Knighton _
- 4. - Johnson,-J. J. - Soil-Structure Interaction - The Status of Current Analysis Methods and.Research, Seismic Safety Margins Research Program, NUREG/CR-1780, January 1981.
- 5. Kausel, E. , et.al. "The Spring Method for Embedded Foundations",
Nuclear Engineering and Design,.48 (1979) 377-392.
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