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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] |
Text
1% .
'Af M 9 12) 456-6000 435 5<sth Avenue Pittsburgh, Pennsylvama 152 9 May 23, 1979 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attention: A. Schwencer, Chief -
Operating Reactors Branch No. 1 Division of Operating Reactors
'4ashington, D. C. 20555
Reference:
Beaver Valley Power Station - Unit No. 1 Docket No. 50-334 Submittal of Engineering Information Concerning Pipe Stress Reanalysis (March 13, 1979 Order to Show Cause)
Gentlemen:
In response to your letter of May 18, 1979, the information requested in order for the staf f to review amplified response spectra based on soil structure interaction has been developed.
Transmitted herewith are the following:
- 1. A clarification of the soil properties used for the programs REFUND cnd KINACT as well as PLAXLY.
- 2. Floor response spectra as defined in item 2 of your letter including 1% damping which was not specifically requested.
- 3. a. The results of SHAKE analcsis to determine soil modulus and damping values as requested.
- b. Spectra at the base of the containment in the free field for each of 3 sets of soil properties as requested.
- c. Floor response spectra at each of three containment floors using the three sets of soil properties derived using FSAR darping values and oscillatory dampings as requested, as well as for 1%.
2261 326 7 90605 0 Nc)M [
$o01 S
// /
Beaver Valley Power Station - Unit No. 1 Docket No. 50-334 Submittal of Engineering Information Concerning Pipe Stress Reanalysis (March 13, 1979 Order to Show Cause)
Page A copy of the deck of computer cards which gives the time history of ground accelerations that are being used in these analyses was furnished to the staf f by Stone & Webster in the Boston of fice on May 22, 1979.
Advance copies of all the requested data were furnished to the staff and discussed at that time.
It is our understanding that the data submitted herewith will serve as a basis for the resolution of acceptable ampliefied response spectra based on soil structure interaction to serve as a basis for reevaluation o' piping sys tems under earthquake induced Ic.ading.
Very truly yours, OblS-C. N. Dunn Vice President, Operations Attachment 2261 327
(CORPOPATE SEAL)
Attest:
j_2 H.W. Staas Secretary COMMONhrALTH OF PENNSYLVANIA)
) SS:
COUNTY OF ALLEGHENY )
On thir J -~ ' day of -
, 1979, before me, DONALD W. SHANNON , a Notary Public in and for said Common-wealth and County, personally appeared C. N. Dunn, 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, information and belief.
DONALD W, SH .NNCN 'ktary Patlic Pittstu'm A.ierea, Co., Ps.
My Co~m'ssien Einres June 7,1979 2261 228
ATTACHMENT RESPONSE TO NRC LETTER OF MAY 18, 1979 CONCERNING USE OF SOIL STRUCTURE INTEllACTION MAY 24, 1979 BEAVER VALLEY POWER STATION UNIT 1 DUQUESNE LIGHT COMPANY 2261 ;29
May 24, 1979 Docket No. 50-334 USE OF SOIL PROPERTIES IN DEVELOPMENT OF SOIL-STRUCTURE INTERACTION AMPLIFIED RESPONSE SPECTRA The following procedures were followed to cbtain soil properties for the soil-structure interaction analyses at the Beaver Valley 1 site for development of SSI based ARS:
First, a small strain soil profile was developed from the best available soil data, including cross hole seismic shear wave velocity measurements, as well as data from borings and samples.
Second, the effect of an earthquake in the free field was evaluated using the SHAKE computer program. The control motion was specified at the surface of the free field; two real records were used -
El Centro and Taft - normalized to the acceleration level of the specified design earthquake (OBE or DBE). The program iterated to obtain values of shear modulus and damping compatible with the levels of strain developed during the earthquake. The average of the results from the two records was used in further analyses and is here called the strain compatible, free field profile.
Third, the moduli and material darping for the strain compatible, free field profile were used for tne REFUND / FRIDAY analyses.
Fourth, the motion at the base of the profile obtained in the SHAKE analysis of the free field was input to several profiles representing the soil column under the Category I buildings.
The top layers of these profiles hr.d masses and fundamental periods equivalent to those of the corresponding buildings.
The small strain values of soil shear moduli were adjusted to account for the additional static stresses imposed by the buildings. The computer program SHAKE was run to obtain strain compatible moduli and damping values for each building profile. The average of results for the two time histories established each profile.
Fifth, the strain compatible properties under each building were used in the finite element dynamic analyses as soil properties directly under the corresponding buildings. The strain compatible, free field soil properties were us.3d for the elements representing the free field. Strain compatible soil properties were interpolated between these values for two columns of elements adjacent to the building.
Sixth, no further iteration on soil properties was performed in either the REFUND / FRIDAY or the finite element analysis.
2261 330
SHAKE ANALYSES BEA72)]_ VALLEY POWER STATION - UNIT NO.1 The strain dependent soil properties, shear modulus and damping.
were analyzed with SHAKE for the free-field and reactor containment.
These analyses were conducted using small strain shear moduli (Gmax) and site dependent soil unit weights. Two earthqaake real time histories, Taft and El Centro, were normalized to ground surface accelerations of 0.125g (D9E) and 0.06g (OBE), deconvoluted to bedrock and amplified to the reactor foundation. The results of the free-field and reactor analyses are shown in Table 2.4-1 and 2.4-2 At the request of the NRC two additional analyses are conducted on small strain (Gmax) values of plus and minus 50 percent. Both the free-field and reactor containment were analyzed using techniques described above. The results of these analyses are preser.ted in Tables 2,4-12 thru 2.4-15.
2261 331
TADIE 2.4-1 1.9 -
S114AIN COHa*ATilll2 SUIL 31turiJtTIES 1.11 Gmax race riend - Elevation 735 1.11 DiiE = .325 g OBE = 0.06 g __
1.16 Tags Luw Staain Tutal Shear Hudulus Shear Hodulus 3.1 F Thick- ui _Vahes Unit As[3 pampin frat io ik31) _ {u_mplirj . t a t i n 1.18 tayer ness La yer C63 Hij Taft ElCentao Aver- Tatt E1 Centro Aver- Taf t EXCent ro Aves- Tait ElCent au Aves - 1.19 th*. Eftj_ Elev. tipst (kef t Haterial S69E 1940 NS a_g t $698 1940 pS_ age _ S693 1940 HS gge_ $69 E 20_jg_ a.no 1.23 1 to 735 600 .325 Sa nd 1095 1091 1093 .041 .041 041 1242 1240 1241 .025 .026 .026 1.34 2 10 725 800 .125 Sand 1728 1701 1715 .054 .055 .055 2074 2062 2068 .033 .034 .0 34 1.36 3 10 715 950 .125 Sand 2369 2285 2327 .057 .060 .059 2859 2813 2836 .036 .038 .017 1.38 4 to 705 950 .125 Sand 2114 1979 2047 .068 .074 .071 2685 2624 2655 .043 .046 .045 1.40 5 5 695 1100 .125 Sand 3024 2820- 2922 .062 .069 .066 3724 3612 3668 .040 .043 .042 1.42 6 5 690 1100 .125 Sand 2880 2696 2758 .066 .073 .070 3637 3529 3583 .042 .046 .044 1.44 7 to 685 1100 .325 Sand 2694 2564 2629 .073 .077 .075 3520 3434 3417 .046 .049 .048 1.46 8 . 10 675 1100 .336 Sand 2837 2714 2775 .076 .079 .078 3766 3702 3734 .048 .050 .049 1.48 9 10 665 1200 .336 Sand 3490 3417 3454 .073 .075 .074 4538 4471 4505 .046 .048 .047 1.50 10 to 655 6200 .336 Sand 3327 22m7 3297 .077 .C79 .076 4420 4396 4412 .C49 .050 .050 1.52 I? 10 645 1200 .136 Sand 3207 3192 3200 .080 .080 .080 4342 4322 4332 .051 .052 .u52 1.54 12 to 635 1200 .136 Sand 3124 3142 3333 .082 .082 .082 4277 4270 4214 .053 .051 .051 1.56 13 5 625 1200 .136 Sand 3083 3119 3101 .083 .082 .083 4239 4257 4248 .054 .053 .054 1.58 14 Me 620 5000 .360 Rock 2.2 parrE 2.4 Ground water table at El. 675 2.6 N
N O 1 ut 1 U
N o
h- 18 700 34 -48 05/I M 9 tat: AVER VALt.EY g STATION, UNIT 1 TABLE 2.4-2 1.8 STRA1H CtMPATIBI.E SO!!. I'ItOP1JtTIES 3.10 CENSX Reactor nu11 ding 1. 12 DitE = .125 g ODE = .06 q 3.15 Top Low Strain Total Sinear Hudulus Stacar Modulus 3.16 Tt:1ck- of Values Unit (kall _ Damping Ratio Ikall ___pgating_Eatto 1.37
!ayer ness layer qd Mgj Tatt Eltentro Aver- Taf t ElCentro Aver- Tatt ElCentro Aver- Tait ElCentro Aver- 1.88 H=> . li t t Elev. jlig ,1]Lg Q Material 5698 1940 tas age 569E 1940 NS age E69E 1940 NS age S695 1940 HS anet 1.19 1.33 1 10 735 1091 .438 Rea ctor Du11 ding 1.34 Pseudo- 3.35 soll 1.36 2 10 725 1091 .138 Reactor 1. 18 Building 1.39
- 1 Pseudo- f soll 1.41 3 10 715 1093 .138 Reactor 1.43 Building 9.44 Pseudo- 1.45 soll 1.46 4 10 705 1G39 .1?d B ea ctor 1.48 Building 1.49 Psaudo- 1.50 soll 1.51 5 10 695 1093 .138 Reactor 1.53 pu11 ding 1.54 Pseudo- 1.55 soit 1.56 6 4 685 1091 .138 Rea ctor 1.58 Building 2.1 Pseudo- 2.2 soli 2.3 I\.)
pgj 7 6 6M1 1500 .125 Sand 2416 2111 2264 .082 .092 .007 3319 3232 3276 .052 .055 .054 2.5 8 10 675 1900 .136 Sand 2651 2366 2509 .081 .090 . 08 6 3616 3529 3573 .052 .055 .054 2.7 9 to 665 1200 .136 Sarid 3352 3090 3221 .076 .083 .080 4416 4295 4356 .049 .052 .051 2.9 3111 .083 4340 4207 4274 .053 2.11
} to 10 655 1200 .336 Sand 3392 3030 .080 .085 .051 .054 l/4 11 to 645 1200 .136 Sand 3045 3030 3037 .084 .005 .085 4266 4133 4200 .053 .056 .055 2.13 1 of 2
la- l l 700 34 -4 8 05/l W 042 DEAVEk VALLEY ltW1.R STATION, Util? I TADIE 2.4-2 (Cont)
IIDE = .j25 en ODE = 0.C6 et Tuga low Staaln Total Slicar Nxtulus Sisear Moelulus Thick- of _Valuce Unit Lksfl (Anmelys Ratio iksfl I Ammeltwa Itat hs layer ness layer qsa 4(d Taf t EXCentro Aver- Taf t ElCent ro Aver-S69E Taf 1940 t ElCentro NS age Aver- Tatt ElCentzu Aver-S69E 1940 NS gy_
Ho. titL Elev2 j[psl (kett Material S69E 1940 HS ge_ S69E 1940 NS age 2945 3039 2992 .087 .084 .086 4212 4079 4146 .ust .057 .056 2.15 12 10 635 1200 .136 Sand 290s 3008 2955 .088 .085 .087 4182 4071 4127 .055 .05s .057 2.17 13 5 625 1200 .136 Sand 2.19 14 (O 620 5000 .160 Rock 2.29 tott:
2.23 Czound water table at El. 675 N
N Ch -
4 ~
c.
2 ut 2
Gmax + 50% - Free Field - Elevation 735 Top Total Shear Modulus -
Thick- of Low Strain Unit (ksf) Damping Ratio Layer ness Layer Values Vt Taft E1 Centro Aver- Taft E1 Centro Aver-No. (ft) Elev, G(Psf) (Fcf) Material 112E 1940 NS Agi__ 112E 1940 NS age 1 10 735 2097 .125 Sand 1791 1794 1793 0.031 0.030 0.031 2 10 725 3726 .125 Sand 2870 2882 2876 0.043 0.042 0.043 3 10 715 5255 .125 Sand 3891 3747 3111 0.047 0.046 0.047 4 10 705 5255 .125 Sand 3586 3670 3628 0.056 0.053 0.055 5 5 695 7046 .125 Sand 4977 5096 5037 0.052 0.050 0.051 6 5 690 7046 .125 Sand 4838 4985 4912 0.055 0.052 0.054 7 10 685 7046 .125 Sand 4646 4843 4745 0.059 0.055 0.057 8 10 675 7046 .136 Sand 4940 5159 5050 0.062 0.057 0.061 9 10 665 7667 .136 Sand 6054 6195 6125 0.058 0.056 0.057 10 10 655 9123 .136 Sand 5798 5973 5886 0.063 0.060 0.062 11 10 645 9123 .136 Sand 3604 5749 5677 0.066 0.064 0.065 12 10 635 9123 .136 04nd 5484 5566 5525 0.068 0.067 0.068 13 5 625 9123 .136 Sand 5394 5452 5423 0.070 0.069 0.070 14 625 Rock EqII:
Ground water table at El. 735 N
N Ch N
U Ln
Table 2.4-13 .
BEAVER VALLEY POWER STATION, UNIT 1 STRAIN COMPATIBLE SOIL PROPERTIES - DBE Gmax Plus 50% - Reactor Building Top Low Strain Total Shear Modulus Thick- of Values Unit (ksf) Damoinz Ratio Layer ness Layer G Ut Taft ElCentro Aver- Taft E1 Centro Aver-No. (ft) Elev. (ksf) (kef) Material 119E 1940 NS ggg__ 112E 1940 NS age 1 10 735 5101 .138 Reactor Building Pseudo-soil 2 10 725 5101 .138 Reactor Building Pseudo-soil 3 10 715 5101 .138 Reactor Building Pseudo-soil 4 10 705 5101 .138 Reactor Building Pseudo-soil 5 10 695 5101 .138 Reactor Building Pseudo-soil 6 4 695 5101 .138 Rea:ter Building Pseudo-soil 7 6 681 7046 .125 Sand 4215 4103 4159 .069 .071 .070 rs) 8 10 675 7667 .136 Sand 4564 4435 4500 .069 .072- .071 665 9123 .136 Sand 5658 5487 5573 .065 .068 .067
) 9 10 10 10 (~5 9123 .136 Sand 5380 5231 5306 .070 .073 .072 (s. 11 10 645 9123 .136 Sand 5171 5019 5095 .074 .076 .075
.076 .079 .078 f(( 12 10 635 9123 .136 Sand 5058 4850 4743 4954 4843 .078 .081 .080 13 5 625 9123 .136 Sand 4943
Top Low Strain Total Shear Modulus Thick- of Values Unit (ksf) Dampine Ratio Layer ness Layer G Ut Taft E1 Centro Aver- Taft E1 Centro Aver- .
.j!L_ (ft) Elev. (ksf) (kcf) Material S69E 1940 NS age S69E 1940 tis age 14 620 .160 Rock NOTE:
Ground water table at El. 735 s
N O
N
STRAIN COMPATIBLE SOIL PROPERIIES - DPE .
Gmax Minu, 50% - Free Field - Elevation 735 Top Total Shear Modulus Thick- of Low Strain Unit (ksi) Damoine Ratio Layer ness Layer Va kes Ut Taft ElCentro Aver- Taft E1 Centro Aver-No. (ft) Elev. G(Pst) (kef) Material Ek2E 1940 NS age 112E 1940 NS axe _
1 10 735 699 .125 Sand 450 454 452 .062 .061 .062 2 10 725 1242 .125 Sand 605 653 629 .Gd6 .080 .083 3 10 715 1752 .125 Sand 79L 883 840 .092 .084 .088 4 10 705 1752 .125 Sand 684 722 703 .109 .102 .106 5 5 695 2349 .125 Sand 1028 1069 1049 .094 .092 .093 6 5 690 2349 .125 Sand 988 1014 1001 .099 .096 .098 7 10 685 2349 .125 Sand 960 968 964 .103 .102 .103 8 10 675 2349 .136 Sand 1073 1070 1072 .099 .100 .100 9 10 665 2556 .136 Sand 1436 1422 1429 .089 .090 .090 10 10 655 3041 .136 Sand 1442 1435 1439 .089 .089 .089 11 10 645 3041 .136 Sand 1482 1470 1476 .086 .087 .087 12 10 635 3041 .136 Sand 1475 1494 1485 .087 .086 .087 13 5 625 3041 .136 Sand 1411 1494 1453 .090 .086 .089 14 620 Rock 11 0 I 1 :
Ground water table at El. 735 N
N Ch
Table i.4-1$ .
BEAVER VALLEY POWER STATION, UNIT 1 STRAIN COMPATIBLE SOIL PROPERTIES - DBE Gmax Minus 50% - Reactor Building Top Low Strain Total Shear Modulus Values Unit (ksf) Damping Ratio Thick- of Layer ness Layer G Mt Taft E10entro Aver- Taft ElCentro Aver-No.. (ft) Elev. (Psf) (Fcf) Material 112E 1940 NS agg 112E 1940 NS agg_
1 10 735 5101 .138 Reactor Building Pseudo-soil 2 10 725 5101 .138 Reactor Building Pseudo-soil 3 10 715 5101 .138 Reactor Building Pseudo-soil 4 10 705 5101 .138 Reactor Building Pseudo-soil 5 10 695 5101 .138 Reactor Building Pseudo-soil 6 4 685 5101 .138 Reactor Building Pseudo-soil 7 6 681 2349 .125 Sand 859 972 916 .116 .101 .109 I\3 8 10 675 2556 .136 Sand 972 1058 1015 .112 .101 .107 rs.)
C7s 9 10 665 3041 .136 Sand 1290 1341 1316 .098 .094 .096
~~~
10 10 655 3041 .136 Sand 1332 1286 1309 .094 .098 .096 l 11 10 645 3041 .136 Sand 1334 1250 1292 .094 .102 .098 U
s43 12 10 635 3041 .136 Sand 1312 1241 1277 .096 .103 .100 13 5 625 3041 .136 Sand 1268 1245 12S7 .100 .103 .102
RESPONSE SPECTRA AT BASE OF CONTAINME]h BEAVER VALLEY POWER STATION - UNIT NO 1 The ground response spectra at the base of the reactor contain-ment structure was calculated and plotted using SHAKE. The artificial earthquake developed for the Beaver Valley sito was normalized to the Deisgn Basis Earthquake (DBE) maxt=um acceleration of 0.125g and input at the ground surface of the free-field profile. The earthquake motion was deconvoluted to the base of the profile and the computed motion at elevation 681 ft, the contain=ent founding grade, was used to compute the real velocity and acceleration response spectra and the tripartite plot of real displacement, pseudovelocity, and pseudo-acceleration vs. frequency. These spectra are plotted for damping ratios of .5.1.0, and 3.0 percent.
Response spectra were calculated for three soil profiles, represent-ed by the shear modulus (Gmax) calculated from seiLmic cross-hole surveys, Gmax plus 50 percent, and Gmax minus 50 percent. The spectra for each soil profile are plotted on Figures 1, 2, and 3, respectively. Also plotted on these figures is the ground response spectra for .5 percent damping presented in the Beaver Valley Unit No.1 FSAR.
2261 140
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BEAVER VALLEY POWER STATION UNIT 1 agunsta anTIFIcInt tanin
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BEAVER VALLEY PO*/ER STATION - UNITS 1 STRUCTURAL DAMPDG 2% DBE - FOR ALL CURVES SOIL-MATERIAL DAMPDG ID'd STRAIN G = 5%
G + 50% FROM SHA13 FIRST ITERATION FMM SHAKE V M LAST ITERATION FROM SHAKE G - 50% FROM SHAG J MUIPMENT DAMPDG_
ARS CURVES PROVIDED FOR MUIPMDIT DAMPING CF 0.55,1.0%, and 3.0%
2261 ;44
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-- - - FIRST ITERATION FROM SHAKE LAST ITERATION FROM SH AKE 2261 .345 SEISMIC ANALYSIS OF CONTAINMENT HORi?_0NTAL SSE HORIZONTAL RESPONSE SPECTRUM AT MAT BEAVEa VALLEY POWER STATION - UNIT 1
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FIRST ITERATION FROM SHAKE L AST ITER ATION FROM SHAKE 2261 i46 SEISMIC AN ALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT MAT BE AVER VALLEY POWER STATION-UNIT I
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FIRST ITERATION FROM SHAKE LAST ITERATION FROM SHAKE 2261 .47 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTA'.. RESPONSE SPECTRUM AT MAT BEAVER VALI EY POWER STATION -UNIT I
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- - -- FIRST ITER ATION FROM SH AKE L AST ITER ATION FROM SH AKE 2261 48 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE S PECTRUM AT OPERATING Fi OOR BE AVER VALLEY PCWER STATION - U NIT 1
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FIRST ITERATION FROM SHAKE LAST ITE R ATIO N FROM SHAKE 2261 a49 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT OPERATING FLOOR BEAVER VALLEY POW ER STATION -UNIT 1
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FIRST ITERATION FROM SH AKE L AST ITER ATION FROM SHAKE 2261 350 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT OPER ATING FLOOR BEAVER VALLEY POWER STATION-UNIT 1
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FIRST ITER ATION FROM SH AKE LAST ITERATION FROM SHAKE 2261 j51 SEISMIC AN ALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT SPRINGL'NE BEAVER VALLEY FOWER STATION- UNIT 1
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-- - - FIRST ITER ATION FROM SH AKE LAST ITERATION FROM SHAKE 2261 a52 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAi_ SSE HORIZONTAL RESPONSE SPECTRUM AT SPRINGLIN E BEAVER VALLEY POWEP STATION - UNIT 1
2.50 2 25 DAMP 3.00%
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FIRST ITERATION FROM SH AKE
- L AST ITER ATION FROM SHAKE 2261 '53 SEISMIC AN ALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT SPRINGLINE BEAVER VALLEY POWER STATION - UNIT l'
l 2.50 2.25 DAMP O.5 %
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L AST ITER ATION FROM SH AKE G-507o FROM SHAKE 2261 354 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT MAT BE AVER VALLEY STATION-UNIT 1
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L AST ITER A TION FROM S H A K E G - 507. FROM SHAKE 2261 '55 SEISMIC AN ALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT MAT BE AVER VAL'.E Y POWER STATION - UNIT 1
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LAST ITER ATION FROM SHAKE G - 50 0/o FROM SHAKE 2261 56 SEISMIC ANALYSIS OF CONTAINMENT HORIZONTAL DBE HORIZONTAL RESPONSE SPECTRUM AT MAT BEAVER VALLEY POWER STATION - UNIT 1
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-- -- LAST ITERATION FROM SHAKE G - 50 7o FROM SHAKE 2261 58 SElsMIC ANALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL RESPONSE SPECTRUM AT OPERATING FLOOR BEAVER VALLEY POWER STATION-UNIT I
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L AST ITER ATION FROM S HA KE 2261 360 G - 50 7o FRO M SHAKE SEISMIC AN ALYSIS OF CONTAINMENT HORIZONTAL SSE HORIZONTAL. RESPONSE SPECTRUM AT SPRINGLINE BEAVER VALLEY POWER STATION - UNIT 1
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L AST ITER ATION FROM SH AKE
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-- --- 2 0 MODEL 2262 003 SEISMIC AN ALYSIS OF MAIN STE AM VALVE BUILDING HORIZONTAL SSE EW HORIZONTAL RESPONSE SPECTRUM AT MAT BEAVER VALLEY POWER STATION-UNIT 1
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2 D MODEL 2262 004 SEISMIC ANALYSIS OF MAIN STEAM VALVE BUILDING HORIZONTAL SSE EW HOPlZONTAL RESPONSE SPECTRUM AT TOP BEAVER VALLEY POWER STATION - UNIT I
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--- - D MODEL 2262 005 SEISMIC ANALYSIS OF MAIN STEAM VALVE BUILDING HORIZONTAL SSE NS HORIZONTAL RESPONSE SPECTRUM AT MAT BEAVER VALLEY POWER STATION -UNIT 1
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