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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
, .
'A@
ouquesneuet m ae Nuclear Construction Division Telecopy 29
$t$u' g"O'l'is"2Os " *""* ' March 5, 1985 United States Nuclear Regulatory Comission Washington, DC 20555 ATTENTION: Mr. George W. Knighton, Chief Licensing Branch 3 Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 PSB Mechanical Responses Gentlemen:
This letter forwards revised PSB Mechanical responses which were accepted at a meeting held or 7.5ruary 11,1985, and an informal meeting held on February 28, 1985. FSAR changes described in these revised responses will be incorporated in an upcoming amendment. The following responses are attached: 430.25, 430.55, 430.59, 430.107, 430.117, 430.122, 430.123, 430.125, 430.126, and GDC 5 for comunications systems.
Please note, the response to question 430.25 is being revised in response to question 430.54.
DUQUESNE LIGHT COMPANY By (
E. J. yooievef jf Vice-President //
GH0/wj s Attachment cc: Mr. B. K. Singh, Project Manager (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
SUBSpRIBED AND SWORN J0 BEFORE ME THIS
-W DAY OF ')2&uf _ , 1985.
xll in) bk C l Notary Public l
ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY '
\
I MY COMMISSION EXPIRES OCTOBER 20,1986 8503110353 850305 PDR ADOCK 05000412 A PDR
ITnited'Stctes Nuclear Reguletory Commission Mr. George W. Knighton, Chief PSB Mechanical Responses Page 2 COMMONWEALTH OF PENNSYLVANIA )
) SS:
COUNTY OF ALLEGHENY )
The Manager, Regulatory Af fairs, Eugene F. Kurt z, Jr. , being first duly sworn, deposes, and says: that he is the Manager, Regulatory Af fairs, Nuclear Construction Division, of Duquesne Light Company; with legal author-ity to sign of ficial correspondence on behalf of the Vice President - Nuclear Construction Division, Earl J. Woolever, in relation to licensing for Beaver Valley Power Station, Unit 2 and therefore authorized to submit the foregoing on behalf of the applicant.
3~ YW ,,
/ v v Date Managecf Regulatory Af fairs Swogn and subscribed before me, this
,6dd day of %,u L , 1985.
L. itb /> YLL Notary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986 3
a
. BVPS-2 FSAR NRC Letter: August 31, 1983 .
s Q estion 430.25 (SRP 8.3.1)
C ction 6.4.2 of IEEE Standard 387-1977 requires, in part, that the lead acceptance test consider the potential effects on load -
acceptance ;fter prolonged no load or light load operation of the diesel generator. Provide the results of load acceptance tests or analysis that demonstrate the capability of the diesel generator to accept the design accident load sequerce after prolonged no load operation. This capability should be demonstrated over the full range of ambient air temperatures that may exist at the diesel engine air intake. If this capability cannot be demonstrated for minimum ambient air temperature, conditions, describe design provision that will assure an acceptable engine air intake temperature during no load operation.
Response
In accordance with Section 8.3.1.1.15, the emergency diesel generator is capable of operating for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at rated speed, no load, without any deterioration in its load acceptance or load carrying capability.
The emergency diesel generator manufacturer (Colt Industries) has performed an analysis which confirms that the only limitation to prolonged (greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) operation, at ne load or light load
pressure alarm setpoint with regard to the capability to start the diesel once ,
a low pressure alarm condition exists. This concern was raised at a -
meeting between the NRC' (Power Systems Branch), DLC, and SWEC on 3; March 6, 1984. -
(
Amendment 7 Q430.107-1 -
July 1984
- i i
- -
y----d-- ?- g v , , - - _ , - - - - , . - -,..-_,-.% -,,mw, , w,,_,_-e--- -,.-%.,-p*+a.w-.-,-+---gs----+---.---_g --m---ws-m.-----------wryw----wm--4 -s.---e ,,ew
BVPS-2 FSAR Refer to revised Tables 9.5-10 and 9.5-11 Amendment 7, for low pressure alarm setpoints, diesel starting times, and associated system pressures. . y de low pressure alarm setpoint is 375 psig. Based on the data t presented in Table 9.5-11, one receiver can start the diesel four l times (in less than 10' seconds) after it has reached its alarm setpoint. For two receivers in service, the starting capability would be enhanced such that more starts would be available. \ '
l Tha low pressure alarm seepoint is 375 psig for each air receiver; in the case of a compressor failure or a.avstem leak causing the_ low ,
pressure alarm point to be reached fod oc& air receiver, the pTl416.R air receiver for that diesel generator would still be at normal . _
pressure (395 - 425 psig) .- Based on the data presented in Table ,
9.5-11 one receiver can starc the diesel five times (in less than 10 seconds) from the low poinc in its normal operating range.
For two receivers in service,. the startig capsbility would be enhanced such that more starts would' be available.
a Amendment 7 Q430.107-2 July 1984
y SU.95-2 FSAR
,f'
/
NRC Letter: September 19, 1957 Question 430.117 (3ection 9.5.7)
You state in Secticn 9.5.7.1 of the FSAR under " specific design criteria" that "the temperature of the lub ricatir.g oil is automatically maintained above a minimum value by means of an independent recirculation loep including'its own pump and heater, to enhance first try s:arting reliability of the engine in the standby condition." The rocher arm lubrication system is an independent subsystem of the diesel lube oil system which is connected to the main system by a flos: valve in the rocker arm oil reservoir. From the inferma:lon available it appears that the lube o:1 :.n the rocker arm lubricatien system will never be preheated unless the cil level is low enough to open the fica: valve. If this is the case what means have you prosided for preheating the rocker arm lubricating oil er justify why preheating is unnecessary. (Refer to Question 430.128 for ccnditions when preheating may be necessary.) (SRP 9.5.7, Parts II and III).
Response
The rocker arm lubrication system is not preheated. The first-try starting reliability of the diesel engine without rocker arm lube oil preheating has been demonstrated by the test program described in Section S.3.1.1.15.
Because of the large total surface area of crankshaft and connecting rod jou nal bearings, when compared, to the small total surface area of rocker' arm bushings, it is evident that rocker arm resistance is an insignificant contributor to cranking resistance and that heating of crankcase oil alone is sufficient. SRP 9.5.7 recognizes the insignificance of rocker arm lube oil heating by stating that the design should contain "an independent circulation loop to ma:.ntain the temperature of the crankcase oil above a minimum value during the standbv mode." ine svn-z diesel generator buildings are heatec to -
provi$ a ia e ambient te conditions, which further assures prop oT1cm-,ho^graturereTI~able starting (nfer hh reyw
)
Q Tbe e a AieSe.l f en Ner 3^f f *'R O rc <lesIyc h E '~ _
bu%; ni,; J- kpa c.u%s as low as mE
% o.c.c cdce w.$ $$ as. cs t&c5 & enf "* i
- ,,%.k s spee;[y -iU- % ~gv,a be I k u fed 'u'M Sk 5 3 a,l.C 4.aL ,F sw 30 all ~ p~ r .p
\
a ecc.e-
\ & / t.r a e of
'-w \ f
/
Amendment 7 Q430.117-1 July 1984 m .e-- e m m ee
BVPS-2 FSAR PRC Letter: September 19, 1983 Question 430.122 (Section 9.5.8)
Provide the results of an analysis that demonstrates that the system design function of your diesel engine air intake and exhaustan extent which prevents developin will not be degraded to of any eng:.ne rated power or cause engine shutdown as a consequenceInclude in your discussior meteorological or accident condition. (gaseous) medium.
potent:.a1 and effect of fire extinguishing recirculation of diesel combustion products, or other gases including to a fire that may intentionally or products of comoustion due on site, on the performance of the diesel accidentally be released generator (SRP 9.5.8. Parts II and III).
Response
The effect of fire extinguishing (Co ) amedium, releasedresconses in the diesel to p g E/l T k building will be =Adressed in the generator 430.124 and 430.129 M he effects of products of comcustion [M 60.13~'4 on m - Question 430.126.
_ @ue to a fire will be addressed in the response to An. analysis has been perfomed to evaluate the effects of accidenta'i l
releases of gases stored. onsite- and the recirculation of diesel ,
exhaust gases orr the function of the emergency diesel generators.
The accidental:- reletae of ' gases. or liquids. capable of producing of their a.
gaseous cloud ort the BVPS-2. site was. evaluated. in.' terms potential to reduce the oxygen content of the diesel intake air below acceptable levels. The onsite stored chemicals and their quantities are shown 'in Table 2.2-9 and their- locations are indicated on Figure 6.4-5. Since the carbon diczide tanks are stored inside the auxiliary building (two 10-ton tanks) and the . turbine building within the (7.5-torr tank), any accidental releases will be confined buildings and released over a period of' time through the normal the effects of
- ventilation system from rooftop vent. Therefore, carbon dioxide releases from these. sources on diesel generator performance is not significantT The"YemEining onsite chemicals' were analyzed by calculating the m ximum concentration expected to occur. -
at the diesel air intakes using the conservative methodology outlined .'
in NUREG-0570.
" Toxic Vapor concentrations. in the control Room Following a Postulated Accidental Release" (Section 2.2.3.1.2). '
accident- the entire contents of the largest single In a postulated or plume-storage cor.tainer are released, resulting in a vapor cloud
- which is conservati'ely v assumed to be- transported byThe the wind most directly toward the- diesel generator" air intakes. '
conservative meteorological condition is assumed for the eelculation.
a wind speed of which consists of Pasquill Class G stability,It is further assumed 0.5 m/sec, and an ambient temperature of 40*C.
that the release point and diesel air intakes are both at ground .
i July 1984 Amendment .7 Q430.122-1
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o BVPS-2 FSAR level and that the puff or plume cent erline tirectly impacts the intake. Only the outside air concentration of each chemical is calculated with no further dilution In of thethe cast chemical inside the of nitrogen anddiesel generatorreleases, building being considered.the presence of the turbine building directly in hydrogen is accounted for by using the ne path of the puff (see Figure 6.4-5) expression for building wake effect from Regulatory Guide 1.145:
(430.122-1) x/Q = L Q (w67 jr A/2) is concentration (g/m ), Q is emission rate (g/sec), u is 3
wnere x, mean wind speed (m/sec). 6 and 6 2 are lateral and vertical and A is the building cross-sectional dispersion coefficients (m)7 ,
combined with area normal to the wind direction. This expression, included (X/Q =
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the dispersion equation without building wake effect., to the 1/uwd (1 + A/276ydz)-1 y dg) and yields the correction factor concentration calculated by the NUREG-0570 methodology whichwas does not used consider building wake effects. A building area of 1519 m:
Ln the calculation.
The result of the analysis is shown in Table 430.122-1. which indicates the maximum chemical concentrations at the diesel air intake in g/m3 and percent by volume, and the corresponding oxygen .
concentrations of the intake air assuming an ambient air oxygen content of 21 percent -by volume. Based on a lower limit of
's 17.5 percent oxygen by volume in the intake air for full engine rated l '
power to be achieved, accidental releases of gaues stored onsite will not degrade the intake air to an extent that diesel operation will be adversely affected.
Likewise, an analysis of the recirculation of diesel exhaust from the-roof in ths lee of the diesel generator building indicates The analysis no estimates impairment of the diesel generator operation.
diesel exhaust concentrations at the air intakes on the downwind side of the diesel generator building based on wind tunnel tests performed
- by Wilson (1976). which producedroof" K isopleths for three different exhaust locations, where building shape.s and seveYaL L = length K = CUL/2/Q, and where C = concentration, a a wind speed, scale, and Q = tmission rate. The K isopleths represent the case of _
Even though the no plume rise, w1ich is the most conservative case.toward the roof, the exhaust diesel exhaust is directed downward temperature of 1,000*F will most likely result in some taoyancy- -
induced plume rise, which leads to added conservatism of the i analysis. The wind tunnel boundary layer is typical of. a suburban or ! -
- ;-ntly built-up urban area which is reasonably representative cf the f
1*:71-2 site area. .
Based on the X isopleths for t'he building shape and exhaust vent locations most representative of the diesel generatur butiding a K value of L exhaust and intake design (Figure 7 in Wilson, 1976$. k was conservatively chosen for the analysis. The concentration of l July 1984 Amendment 7 Q430.122-2
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BVPS-2 FSAR s then C = Q/UA, where A =L2 diesel exhaust (C) at the air intakes Bastd on a design exhaust flow (building area normalato the wind).
building area of 319 m2 (A), and an issumed of 42 m3/see (Q),
10 m/sec wind speed (U) for dcwnwash conditions, the diesel exhaust ,
concentration at the air intakes is 1.3 percent by volume. This 20.7 percent oxygen content of the ~
concentratton translates to a intake air. which is well above the minimum percentage of 17.5.
Reference for Question 430.122 Wilson. D.J. 1976. Contamination of Air Intakes frcm Roof Exhaust Vents, ASHRAE Transactions 82, Part 1, 1024.
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l TABLE 420.122-1 ESTIMATED CHEMICAL CONCENTRATIONS AT DIESEL GENERATOR I.1R INTAKES Diesel Intake Concentration Oxygen Content Chemical tg/m 3) (*5 by Volu.e)m T5 by volune)
Ammonium hydroxide 24.8 1.8 20.6 Mitrogen 171.9 15.8 17.7 Hydrogen 4.5 5.8 19.S Chlorine 201.7 7.3 19.5 Hydra::ine 0.1 0.01 21.0 Morpholine 0.1 1.5 x 10-3 21.0 Sulfuric acid 2.4 x 10-5 6.3 x 10-7 21.0
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- ' n1224106sts5ah BVPS-2 F3AR NRC I.etter: September 19. 1993 1.9 1.13 Question 430.123 (Section 9.5.8)
Discuss the provisions made in your design of the diesel engine. 1.14 combustion air intake and exhaust system to prevent possibis 1.15 clogging. during standby and in operation, dust from abnormal climatic storms, ice and snow 1.16 conditions (heavy rain, freezing rain, drtits. and snow) that could prevent operation of the diesel 1.17 generator on demand (SRP 9.5.8.. Parts II and I!!).
1.18
Response
1.19 Abnormal climatic conditions to be considered snow drifts, and snow.
at SVPS-2 would include Heavy .1.21 heavy rain, freezing rain, ice and rain, freezing rain, and snow cannot impair the functioning of diesel intakes and exhausts because of'the downward facing openings of the 1.22 labyrinths which are designed to protect the exhausts and intakes ;
from tornado missiles. Drifting snow cannot restrict intakes due to 1.24 their elevation, which is greater than 25 f t. above the ground (refer to Figure 3.8-43). Blockage of diesel exhausts by drifting snow is 1.26 prevented. by the. location and' configuration of the concrete hoods (refer to Figur .8-4 .-
Since each; hood has two downward facing 1.2S openings, one o the- north side of the center supporting pedestal and one on the south side of the pedestal,~ blowing snow from the north or 1.29
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south will not. significantly- drif t. ~ at- ' least one opening on esca 1.30 diesel exhaust because of shielding by the . pedestals and/or the adjacent. diesel exhaust hood. Snow blown from the- east or west will 1.31.
not drif t.significantly because the north opening of the "8" diesel exhaust and the south opening. of the "A"~ diesel ~ exhaust permit 1.32.
f blowing snow to freely pasa under the overhanging a openings. Q 1.33 addition, the area of the openings (over 50 ' fe ) f ar exceeds the- area 1.34 ,
of the exhaust pipe (less than 8 f ta) and. would permit significant 1.35 screen blockage before diesel performance would be impacted. Snow depth can reach 51 inches average at the- dtesel exhausts and still maintain the- 8"fta total opening area, assuming the exhaust flow does 1.36 not blow or melt nearby snow (which it certainly would) .
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BVPS-2 FSAR NRC I.etter: September 19, 1983 Question 430.125 (Section 9.5.8)
Experience at some operating plants has shown that diesel engines other have failed to start due to accumulation of dust and ~
deleterious material on electrical equipment associated with starting control of the diesel generators (e.g.. auxiliary relay contacts, switches. etc.). Describe the provisions that have been made in your electrical starting system, and diesel generator building design.
combustion air and ventilation air intake design (s) to preclude this condition to assure availability of the diesel generator on demand.
will be Also describe under normal plant operation what procedure (s) used to minimir.e accumulation of. dust in the diesel generator room; specifically address concrete dust control (SRP 9.5.8, Parts II and III).
Response: .% ~
NEMA Type 12 enclosures are used the for all enclosed diesel generator equipmentelectrical against panels. and are designed to protect dirt and dust.
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_'the current in-place station administrative procedures require that a.
housekeeping program exist to ensure that tne quality of safety--
, related items is not degraded as, a result of housekeeping practices.
- A senior supervisor, siong with other plant supervisory personnel.
' the station housekeeping committee, and employees are responsible to ensure housekeeping requirements. are properly implemented. This i program is in accordance with Regulatory Guide 1.39.
To minimize the entry of airporna particulate meterial from the VT outside, the boter.ms of the ventil(Tation air intakes for the diesel
~
generator rooms are located 27 feet above grade. elevation (paragraph III.4 of SRP 9.4.5 specifies a minimum of 20 feet for this distance). ,
_a, , _
M Concrete is proportioned, placed, and cured suc.t that the existence of Leose concrete -
M dist on formed and floor surfaces is prevented. Personnel foot traffic into the diesel C generator building is expected to introduce small amounts of mud, dirt and dust origin _
f ating from other areas, principally the yard area. This debris, in conjunction with normal foot traffic, will act as an abrasive, thus loosening a small quantity of add-itional dust from concrete floor surfaces. The total duat produced, however, will be
' adequately addressed by the housekeeping program and other measures described herein. e Finally, NIMA Type 12 enclosures are used for all diesel generator electrical panels and are designed to protect the enclosed equipment against dirt and dust. .
~~
July 1984 Amendment'7 Q430.125-1
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p- BVPS-2 F~AR NRC Letter: September 19 1983 Question 430.126 (Section 9.5.8)
Figure 1.2-2 of the FSAR sho.rs system station service transformer 2A located near the diesel generator building . A transformer fire with the right meteorological conditions could degrade engine operation by the products of combustion being drawn into the D/G ventilation system and D/G combusti m air intake system. The same conditions apply for the oil storage laydown area and oil separator no. 22.
located in the immediate area of the diesel generator building.
Discuss the provisions of your design (site characteristics, ventilation system and building design, etc) which preclude this event from occurring (SKP 9.5.8, Parts II and III).
Response
Provisions in SVPS-2 design which preclude degradation of diesel '
performance because of combustion product intake includes .
- 1. A heat detector-actuated. automatic water spray delug5 system and backup fire suppression capability provided by a yard fire hydrant for system station service transformer 2A
- 2. The oil storage laydown area is used only to hold the oil drained from station service transformer 2A during maintenance. This type of maintenance can only be done during a plant shutdown condition.
- 3. 011. separator No. 22 is buried and its vent is supplied with a flame arrestor. Ataj odesLPL4w) Feavvt Tits est IsI%e47>e-Seet 70 W 57ada) Seldwt -s jsTewt W NfutF IT WsNtc A#ri coth riTuTs A Ptd5 ftAydC, SiSTErrl ~
- 1. 'The/tationgervice/ransformers are used to bring of fsite power into the plant and 'would not be transmitting power during normal pucp._ ofcMrd manc conaitions. In the unlikely event of a fire in % M O ,
l jfervice fransformer 2A, plant auxiliary power could be supplied by either the main generator or of fsite power via the redundant sisTEM -
geneientervice/ransformer2B(locatedonthenorthwestside .
of the plant)? In addition, a heat detector-actuated, automatic water spray debge system and backup fire suparession capability -_
from a yard fire hydrant are provided fo tacion /ervice fransformer 2A.
MAIE Ale surmt. N ort ogese# Pen) j SCSI # g T I/44AE*
7tzMitfoames 7 A wouu) **T m"W " A Amendment 7 Q430.126-1 July 1984 l
f GDC 5 Question (Provided Infomally):
. The information submitted by the applicant in Amendment 4 to the FSAR indicates that the communication systems, in particular the page party system, the radio system, the microwave system, and telephone systems, are shared, interconnected in some manner, or can be connected to their counterpart systems in Beaver Valley Unit 1. From the information submit-ted, the staff cannot determine if the communication systems are designed to meet the requirements of GDC 5.
Response
As clearly stated in the standard review plan, there are no general design criteria which apply to communications systems. Therefore, GDC 5 was not considered as a design basis for BVPS communications systems. Regardless of the review criteria being applied here, experience in designing commu-nications systems has resulted in certain independence of communications systems between BVPS-1 and BVPS-2 where it makes engineering sense to do so. The following discussions attempt to answer the reviewer's concern.
The page party systems for BVPS-1 and BVPS-2 nomally operate as two independent systems. The handsets and speakers for each system are located
, only in areas of their respective unit so that messages pertaining to one unit will not be monitored on the other unit. The page party systems of the two units can be combined if desired. This is accomplished by use of
" merge-isolate" switches located at the communications panel in the main control room, at the auxiliary shutdown panel of BVPS-1, and at the alter-nate shutdown panel of BVPS-2. These switches are normally in the " iso-late" position, which allows for independent operation of each unit's system. The " merge-isolate" switches are provided for the purpose of making emergency announcements at both units simultaneously and are returned to the " isolate" mode following use. This will maximize the number of channels available at each unit and will not interfere with p1 ant shutdown.
The radio system consists of several separate elements. Base stations and hand-held units communicate through either of two selected radios (VHF high band and VHF low band) located in the Radio Building. In addition, the control room is provided with a third radio (VHF high band) and a roof mounted antenna should the others be inoperative. These multible radio systems assure that loss of all radio consnunications is unlikely.
. The private automatic exchange (PAX) telephone system is shared between the two units. The telephone lines from the switchboard to various parts of the two units are fed radially and are in separate conduits. This modular construction assures that the loss of a local line does not cause the loss of the entire system or affect other incoming or outgoing calls.
4 x ._.__ _- _ , . _ . -,m_._ __-,._.,,,_._.m - - _ , . _ _ _ _ , . _ _ , _ _ . . . . - , . -- ,_,,_,,e._.__ _., , - , - , _ _ - _ . , , , - _ _
n The microwave system is no longer used for voice communications at BVPS and was never intended to be used for onsite communications. A revised response to Question 430.58 will address deletion of this system.
Based upon the diversity of communications systems provided for BVPS and the design features of each system described above, it can be concluded that failure of a communications system at one plant cannot affect safety at the other.