Letter Sequence Request |
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MONTHYEARML20195E5231984-09-19019 September 1984
Notifies of 840926 Meeting W/Util in Bethesda,Md to Discuss Generic Ltr 84-08 Issues.Agenda Provided
Project stage: Meeting
ML20093K5931984-10-12012 October 1984
Forwards Responses to Draft SER Issues 46 & 74 Re Loose Parts Monitoring Sys & Primary Component Cooling Water Isolation from Reactor Coolant Pump Thermal Barriers, Respectively
Project stage: Request
ML20101F7361984-11-0606 November 1984
Application for Withholding Study Re ESF Actuation Sys Setpoint Methodology (Ref 10CFR2.790)
Project stage: Request
ML20099G5331984-11-20020 November 1984
Forwards Positions on Backfit Requirements.Further Clarification & Justification to Facilitate Meaningful Appeal Meetings for Evaluating Postulated Increase in Plant Safety Requested
Project stage: Request
ML20112G8191985-03-27027 March 1985
Forwards Revised Power Sys Branch Mechanical Responses Previously Submitted Informally & Discussed in 850325 Telcon.Fsar Changes Will Be Incorporated in Upcoming Amend. Discussion of Lighting & Communication Included
Project stage: Request
ML20126M3041985-07-11011 July 1985
Forwards Decision on Appeal of Requirements on Fire Suppression in Cable Spreading Room.Implementation of Certain Human Factor Recommendations Requested
Project stage: Other
ML20151N8801985-12-24024 December 1985
Forwards Comments on SER (NUREG-1057).Sys Will Be Implemented to Track Resolution of Comments & Future SER Changes.Statement on Page 2-46 Re Susceptibility of Soils Around Intake to Liquefaction Should Be Expanded
Project stage: Other
ML20207L5331987-01-0606 January 1987
Forwards Updated FSAR Fire Protection Matl in Preparation for Upcoming NRC Fire Protection Audit.Submittal Contains Info for Resolution of SER Open Item 5 & Confirmatory Item 48c.Matl Will Be Incorporated Into Amend 14 to FSAR
Project stage: Other
ML20207N1901987-01-0808 January 1987
Notification of 870129 Meeting W/Util in Shippingport,Pa to Conclude 4-day Site Review of Fire Protection Issues.Issues Identified as Confirmatory Issue 48 & Backfit Issue 7 in Sser 3
Project stage: Meeting
ML20213A5671987-01-27027 January 1987
Requests Security Passes Be Provided to Personnel for 4-day Site Review to Begin on 870108 Re Fire Protection Issues
Project stage: Other
ML20209G4371987-01-28028 January 1987
Forwards Addl Info Re SER Backfit Item 7 (Fire Suppression in Cable Spreading Room),Per NRC Request in SER Section 9.5.1.6.Response to Item 4 Provided in Jj Carey , Per Sser 3
Project stage: Other
ML20155H2511987-02-0505 February 1987
Summary of 870130 Meeting W/Util & S&W in Bethesda, MD to Conclude NRC Fire Protection Site Review of 870127-29.List of Attendees Encl
Project stage: Meeting
1985-03-27
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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
n . _
e
'AFN Duquesne Udit RMg,os6
- 2) 923-1960 Nuclear Construction Division Robinson Plaza, Building 2, Suite 210 elecon W 2) 787-2629 Pittsburgh, PA 15205 March 27, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. George W. Knighton, Chief Licensing Branch 3 Of fice 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 res pons es which were previously provided informally and subsequently discussed in a telephone conversation on March 25, 1985. FSAR changes described in these revised responses will be incorporated in an upcoming amendment. The following responses are attached: 430.53, 430.58, 430.74, 430.79, 430.116, 430.119, 430.124, 430.127, 430.138, 430.144, a general discussion of lighting and communication, and a general response on the air dryer issue.
DUQUESNE LIG COMPANY By Ji J Carey Vic President GH0/wjs Attachment cc: Mr. R. DeYoung, Director (3) (w/a)
Mr. B. K. Singh, Project Manager (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
INPO Records Center (w/a)
NRC Document Control Desk (w/a) 1 1 %
SUBSCRIBED A EWORN TO FORE ME THIS g /, DAY OF M/r , 1985.
/
4 h* Notary Public 412 5HillA N. FATTORE. NOTARY PUBLIC PDR $HIPPINGPORT JORO. SEAVER COUNTY 4 NY Commis5104 iXPIRf 5 SEPT.16,1985 N'h. Pennsylvania Association of Netnie-
E Unitcd Stctss Nuclacr R gulctcry Commission Mr. G:crga W. Knighton, Chicf PSB Mechanical Responses Page 2 COMMONWEALTH OF PENNSYLVANIA )
) SS:
COUNTY OF BEAVER )
On this j // M day of {td) ,
/ 9((, before me, a Notary Public in and for said Commonwealth and County, personally appeared J. J. Carey, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge.
$.l /
Notarv Public SHEllA N. FATTORE, NOTARYPuttlC
$HIPPl#GPORT BOR0.SEAVER COUNTY NT CONNIS$ ION EXPIRES SEPT.16,1985 Member. Pennsylvania Association of Notaries I
l I
sw- - -
s BVPS-2 F5AA-i l
NRC 1.etter: September 19, 1983 question 430.53 (Section 8.3)
Proy1de a detail. discussion (or pla'n) of the level of trainsnq -
proposed for your operators, maintenance crew, quality assurance, and supervisory personnel responsible for the operation of the emergency diesel generators.
Identify the number and type of personnel that
. will be dedicated to the operations and maintenance of the emergency from diesel generators and the number and type that will be assigned i
your general plant operations and maintenance groups to assist when l
needed.
In your discussion identifT the amount and kind of training of that will ongoing be received by each of the above categories and the type training progran pt -W to assure optimum availability of the emergency generators.
Also discuss. the level of education and minimum experience -
maintenance requirements for the various categories of operation and personnel associated with the emergenoy diesel generators (5RF 8.3.1, I Parts.II and.II).
Response
') The. training program 19er Dr.c maintemense per'sennel whe:DLC om.the emergensT diesel.generstnre is provided # the Department in. a, trainias medale titled.
Personnel fee maintensame verte em Diesel tagine the emergensT perform work Training Maintenance.
diesel gaaerators be ~4 M free the Otc Maintenasse Department or constructiori crafts, in menors and skills, auM4e4=== to perform the scope of will Maintenasse personnel ineelved, will innind. 9 -4 eat.
work. required, and electrical, and instrumentatism Le ,. #=, as dedicaciasm of' spesial perseasel to emergency diesel generator-Comples work and-nota *- is not necessesy or required.
inspostiam en, the emergensT diesel :: '
generatses. will be performed in 7; under the direction of a asserdamse with,=4: 2 Vender FinLd Empresentative.
ETPS-2 will meet the requirements of Training AMEZ.13.1 - lS71 in salaattag and. hiring personnel.
progress alas asist for qualier centrol, operating operations, and supervisory personnel receive ,
personnel. Lirsmeed.and tr=4-4-~ non-licensed and. requalificacian trainiaq on electrical "
{
detailed syst s 'T RA lp ir4 and emergency diesel generator system operacian. ft LTdov6t/
?
th W S,nw ARC war A v A n t. A ',M- F uLsun T rire vc a't.ciQ W . '
f LAMS T3 brOCLof[ f .TQQ g p uo(, fQc5llAM on5g% 9pg ggn,gygQ
'OT919th to/li% 9Edbc/t TRa m nS6 ' of bc_ PE/Lso usc.< , .
D EVEL0f E M(pr Op- f4 7,M g pipG f/2 c Gf/r/fsf IM C ill A M o t7 (I f A VE5ft.of Ser/ttd PE06/2/)41 O M N IS C0 pt i ST E pT WTH OCJ P CP' co syt. w i u. (t.C e c i vc. EQm y,K e g y ,za gg l D6. -
O Amendment. 4 Q430.53-1 December 1983 J
-*----.y *--.--+gy w w.,,..-.,-w.-- ,9- g_a
430.58 Description of interplant (plant-to-offsite) comunication system (9.5.2) inacequate.
7 c
Description inadecuata. of interplant (plant-to-offsite) connunication systara is -
(Seqtion 9.5.2.2) (0 pen: Category 3a) '
W ..
- .:;? .
a g
3
. T da .
y .
- .- , .. *. 9
.,~ lI. [.x. W ,
5.f' y .
3,.i The applicant isas requested to provide a detailed descrip' tion for each Qw
. Y -
$,, . interplant communicatfort system listed in Section 9.5.2.2 'of..'the'.(,SAR. s u.<
1 s i. ?
Theket'ailehgde[cription.was to include an identification
-v. - .. s 3 -.
anb'~ y?,
9
'eih desebption of' escit%:^r a p-ar :::. c, a descript1on'of sabs,l . ,' ~ . $ .,
r_
.n 7 .y 3 components (headsetsihandsets,. switchboards,ampliffers,J
~
O ; & 4.- - -e .
' consoles? handheld. radios,. etc.) location of major components. (powe'r
< gy4 {4 e.y
\ sources consoles, etc.) and interfaces between the various. systems. ,The. ,
applicant hIs nodprovided this information for the g@rowere!_oraystani g gpe.toge,honems,st.m+ .
g.
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@ ~e W Poesc: rap Neacuuc siwa os oso uvaa. mses as n g
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' 160 n1224106srashg 07/12/S4 BUPS-2 ESAR indicates that the emergency preparedness licensing branch shouldl4.8 their as part of review plant-to-offsite communication responsibility under SKP 13.3. No acceptance criteria or review 4.9 procedures applicable to plant-to-offsite ecmmunications systems are : 4.10 provided in SRP 9.5.2' and conclusions presented in the " Evaluation Findings" section of SRP 9.5.2 pertain only to the areas of review I 4.11 c
already performed under SRP 13.3.
4.12 .
The plant-to-offsite ecmmunications consist of the following separate and diverse systems: commercial telephone land-line system, plant- 4.15 to-offsite radio ' system. microwave system, system operator telephone lI 4.17 system. and PAX telephone system.
4.19 Conumercial Telephone Land-Line System Selected locations in the plant are provide
- with , commercial 4.21 Components 4.25 telephone company voice circuits and telephone handsets.
of this system are the handsets and their cabling system throughout the plant. The main control roomr. Shift Supervisor's office. plant 4.26 offices, and security office are also served by the Bell Telephone 4.27 .,
system. The Bell system cables are in separate manholes and are 4.23 The talk circuit and ringer 4.30 independent. of the DLC telephone system.
power for single lines is from- the Bell system's central office. 4.31 4.32 Power for lights. and ringer on key set telephones is from the- BVPS-2.
essential bus.
4.34-Plant-to-Offsite Radio System The main _ components of the systest are described in Section 4.35 -
- 9. $ . Z. %.Z. Z. z .
This radio system is. powered. froar the 48 V de dedicated conununication 4.37
~
4.38 battery / charger system. .
Y 4.40 Microwave- Systear microwave system is a shared facility with BVP5-1. It is 4.42 The- 4.44 comprised of microwave- radios (located. at the switchyard relay house) and their affiliated circuits.
The microwave radios are powered from a BVPS-1 48 V de dedicated 4.45 switchyard battery / charger system. }4.46 4.48 a System Operator Telephone Systme The system operator telephone is located on the communication console- 4.49 ~
)roterawave in the main control raalo,] to theroom. It is a direct Itlink.
OLC dispatcher. via hardwire is. separated from all@4.53.52.
4.54 other telephone systems and powered by two dedicated No. 6 dry cells.
Ieptemcer M24 Amendment 3 420.53-5 g @ $t-TW6 coemme,triog censon.r.
BVPS-2 FSAR The radio transceivers are located in the radio building, sdjacent to the site, with remote control consoles in the main control room and with a remote handset provided at the ESP. These rad..o stations,
~
h provide links to the OLC maintenance and cperation vehicles in the area. In addition, two mobile radio transceivers are provided in the plant. The system is designed to provide reliable radio .
communications.
9.5.2.2.2.3 Microwave System The system consists of a multiplexed microwave network and is used f for relay protection, telemetering, load program control, and voice functions. The microwave system is an expansion of the existing system at BVPS-1 to include BVPS-2.
9.5.2.2.2.4 System Operator Telephone.
A system operator telephone is provided on the main communicatio console. The telephone is a direct link, connected via hardwire ;
micenuava rarH o3 to the DLC dispatcher. It is independent of all other telephone systems and powered uy two dedicated Number 6 dry cells.
9.5.2.3 Design Evaluation t,
-A failure of one communication system does not affect the operation g of the other types of communications systems since they are of W, V
diverse types and are independent of one another.
9.5.2.3.1 Intra-plant Communications A loss of electric power does r.ot cause a common mode failure of intra-plant communications. The PPS and PAX systems are powered from separate reliable power supplies that ultimately derive power from the station or from communication batteries. The portable radio system is battery powered and independent of plant electric power-except for recharging of batteries. The calibration jack, PPS, and PAX systems generally de not share common raceways.
9.5.2.3.2 Plant-to-Offsste Communications j The plant-to-offsite ccmmunications systems provided use a diverse 7 mix of the major types of approaches which are available (commercial 7 telephone, microwave, radio, and system operator telephone) to ensure that under the most adverse circumstances, communications will be '
maintained. .
9.5.2.4 Inspection and Testing Requirements The design of the communications systems permits routine testing and inspection without disrupting normal communications. Degradation of m any systems which are in daily use can be identified and corrected. O b
9.5-44
=
Draft Response to R.G. 1.26 Backfit Issue (Q430.74)
In conversations with the diesel generator vendor in February and March, 1985, the vendor confirmed that non-ASME piping on the BVPS-2 diesel generators is manufactured to the sane quality standards and is of the sane materials and schedules as similar diesels already accepted by the NRC. This would include such plants as Millstone 3, Hope Creek, and Seabrook. ASME piping is shown on FSAR Figures 9.5-7 through 9.5-12.
- ~ - . - . , , . . , - , . , . . - . - , - . , , , . , , ,
. . , . - . . . . - . - . _ , . .-~ . . .-.
. BVPS-2 FSAR NRC Letter: September 19, 1983 d
Question 430.79 (Section 9.5.4)
Assume an unlikely event has occurred requiring operation of a diesel generator for a prolonged period that would require replenishment of fuel oil without interrupting operation of the diesel generator.
What provision will be made in the design of the fuel oil storage fill systems to minimize the creation of turbulence of the sediment in the bottom of the storage tank? Stirring of this sediment during addition of new fuel has the potential of causing the overall quality of the fuel to become unacceptable and could potentially lead to the degradation or failure of the diesel generator (SRP 9.5.4, Parts I, II, and III).
Response
Revised Section 9.5.4, Amendment 4, discusses design features which minimize stirring of sediment. Additionally, should stirred sediment be a problem, it would not affect diesel operation. As shown on Figure 9.5-7, strainers will prevent significant amounts of sediment from being transferred to the day tank while a duplex filter protects the engine from particles transferred from the day tank.
Alarms are provided for high differential pressure on the strainers.
In the event a strainer is seriously restricting flow, a low level in the day tank will cause the backup transfer pump (with its own d,
)
strainer) to start. Restriction of the duplex filter will result in an alarm, which would allow the valving in of the clean filter element, to replace the clogged one while the engine continues running. 10 9'liblT10 h 'rHE TE.c d osc y? t s PE C IFi c A re c tJS DQc t s?g 6 7 'b6 V WEL 6lC 60/ fly FOIA 600N h366/IL G E o E / M r o R . Tils g o g m g t 9/19C ricC of:- Ol2bE/2@6 Fugt OIL wHGO Tn 9k L rf v'E L 15 GMRoxlM GTrCLV
'h w W IAETuceD fo"- ? <cr="7 (nPfilcmeTcid 47 ,
.t! nd rv)d rse 7bnv t)gE6i' ceM)o 608[ d L.E L/ 6Ls) I b. 8 MTIE PSD IID To /S E l'/26cTicED h /2. p G P R.0 L CIO6 d3) \lESfEL 08E/2r) Tick E.06 d assufn,fgg, O kELM 19 MLIV 64-T bMOVSIE OF f 0 0/2_ 17.-0 #4D /CNb r T10 Al5 (scc THC REsrcosec To caGSTad Mc 'D j A Sf64for TA n r( LF UEL tt 43Sul24) TO MIMtm t 26 6T 1/24WC- oF S/DimEWTi '
Amendment 8 Q430.79-1 September 1984 )
BVPS-2 FSAR NRC Letter: September 19, 1983 Question 430.116 (Section 9.5.7)
Assume an unlikely event has occurred requiring operation of a diesel e: generator for a prolonged period that would require replenishment of 4 lube nil without interrupting operation of the diesel generator.
Provide the following:
- 1. What provision will be made in the design of the lube oil system to add lube oil to the sump. These provisions shall include procedures or instructions available to the operator on the proper addition of lube oil to the diesel generator as follows:
- a. How and where lube oil can be added while the equipment is in operation,
- b. Particular assurance that the wrong kind of oil is not inadvertently added to the lubricating oil system, and
- c. That the expected rise in level occurs and is verified for each unit of lube oil added.
- 2. Verification that these operating procedures or instructions will be posted locally in the diesel generator rooms. ,,
f
- 3. Verification that personnel responsible for the operation and maintenance of the diesel are trained in the use of these procedures. Verification of the ability of the personnel on the use of the procedures shall be demonstrated during preoperational tests and during operator requalification.
- 4. Verification that the color-coded, or otherwise marked, lines associated with the diesel generator are correctly identified and that the line or point for adding lube oil (when the engine is on standby or in operation) has been clearly identified (SRP 9.5.7, Parts II and III).
i
Response
Refer to revised Section 9.5.7, Amendment 4, which addresses the addition of lube oil, verifies the rise in oil level, and identifies the location for adding lube oil.
All maintenance lubrication on the diesel generators will be performed using approved maintenance procedures. These procedures are specific instructions that are prepared from the Technical Manual. The instructions are formatted to be consistent with the DLC Administrative Manual. Verification signatures are required for O
Amendment 4 Q430.116-1 December 1983 Y,,f
. BVPS-2 FSAR identifying proper oil type and appropriate QC inspection holdpoints are provided. These procedures are reviewed by the site safety 4 committee, and are approved by the Station Superintendent.
Appropriate maintenance personnel of: AuGE cit are trained beA6cG in STn thedb89 usage ep%of(these[Mr#M6cpc proceduresccu & FoA GhiiscQ(
b iscrJS OS AilT CF 6 9 CR-dosM6 Y-AW 8M6 BRogf2 g ,
At present, the Technical Manual issued by the vendor for the emergency diesel generator has two procedures for adding lubricating oil with the emergency diesel generator operating. These procedures +
have been used by other utilities successfully which negates the need for procedure verification and preoperational testing to demonstrate the procedures. One method involves direct addition to the sump.
Local posting of such a procedure is considered unnecessary and undesirable since sufficient time is available to obtain the procedure from controlled manuals at the site. Procedures for 4 woriting. on safety-related equipment are required and available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
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/ Amendment 4 Q430.116-2 December 1983 l
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BVPS-2 FSAR NRC Letter: September 19, 1983 Questian 430.119 (SRP 9.S.7) and 9.5.7.5 of the FSAR you discuss the level i
In Sections 9.5.7.2 alarms associated with the lube oil system. You state that "the -
rocker arm lube oil reservoir level is monitored for high level and the level is maintained by a lever control valve." No mention is -
made of a reservoir low level alarm. A failure of the level control valve to maintain lube oil level in the rocker arm reservoir could result in inadequate or no lubricating oil for the rocker arms, leading to diesel generator unavailability and/or failure. This is an unacceptable condition. Provide a Icw level alarm for the rocker arm lube oil reservoir (SRP 9.5.7, Part III).
Response
The- rocker arm low lube oil pressure alarm is provided to alert the operator of conditions such as low rocker arm lube oil reservoir i level. The level control valve is a float valve, which tends to be .
pushed cpen by inlet oil pressure. Valve opening is further assured by the length of the float rod and weight of the float which provide sufficient mechanical advantage ta force the valve open in a reliable manner when a low lube- oil. level condition exists.
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Amendment 6 Q430.119-1 April 1984
. _ _ _ -. 'd o
BVPS-2 FSAR A
o
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, NRC Letter: September 19,1983g k
e OSb Question 430.124 (Section 9.5.8) } lg 2}W EP Show by analysis that a potential fire in the diesel generator 2yW building together with a single failure of the fire protectiong ~4y systems will not degrade the quality of the diesel combustion air so -
that the remaining diesel will be able to provide full rated 2gd F
(SRP 9.5.8, Parts II and III). power)g y $
Responses k %C 67 o 1-The emergency diesel generator sets are separated by a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire A j {
barrier (FPER Section 1.6.9). Eachdieselgeneratorroomisequippedg with an automatic, double-slot, fixed-flooding CO 2 system (Sectionj , O M 9.5.1.8.9), qW e M
In the unlikely event of a fire in one of the diesel generator rooms,%? u h.
e&
the only vent p th for combustion products is the ventilat g 3 g ust Iy vent. The diesel generatoryugdjng ventilation fans r- <:t r operated'daripers are closed by4 C ategoTy I heat detectors n %jand mt tne event M l-(of a fire (Section 9.4.6Dr- u.ing A Test /62ATv4C OF is'o' 35 WMD The emergency diesel generator combustion air intake is located on the east side of the diesel generator building at approximately elevation 759 feet-0 inches. The diesel generator building ,
ventilation exhaust is located on the west side of the diesel ^
generator building and exhausts at elevation 774 feet-6 inches.
The effect of combustion products and CO 2 gas emitted from.the ventilation exhaust on the quality of the diesel combustion air has been evaluated using the diesel exhaust reci;culation analysis described in the response to Question 430.122, Amendment 7. Although the exhaust is emitted horizontally, it will be deflected upward by the service building a few feet away. Therefore, the recirculation analysis of Question 430.122 is also applicable to this question since the exhaust of combustion products and CO 2 will be effectively released from the western edge of the diesel building roof, not far from the diesel exhaust vent locat'ibn~.'
By assuming that all exhaust fans are running, a maximum exhaust rate of 150,000 cfm (71m3/sec) of combustion proeducts and CO 2 is used in the evaluation. It is also conservatively assumed that there is no oxygen contained in the exhaust although it is diluted with some fresh air. Using the methodology described in the response to Question 430.122, the combustion product and CO2 gas concentration (C) '
at the diesel air intake is calculated as:
C = 71m3/sec = 0.022 (10m/sec) (319m2)
?mendment 7 Q430.124-1 July 1984 s
.. - - _ . , ~
e 4
BVPS-2 FSAR
? ,'
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, - or 2.2 . percent by volume. This concentration tran' slates to a 20.5 4
,, percent oxygen content of the intake air which is well above the minimum of 17.5 percent for proper' diesel operation.
1.
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Amendment 7- Q430.124-2 July 1984 l 2 e
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l l
1 440.127 Capabklity of 3/G to operate under extreme service conditions (9.5.8) and weather ditturbances - response 'nadequ;.ce. j l
- 17. Capability of 0/G to operate under extreme service conditions and .
weather disturbances - response is inadequate (Section 9.5.4.1)
(0 pen: Category 3a)
. t
, -8
\
., b.
The'-applicant has stated that each diesel generator unit is i
capable of operating at Its.rnaximuk rated output under the '
following outdoor service conditicas and for the durations i
\
indicated during the following weather disturbances:
(1) Outdoor Servic.t Conditions i
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Ybbo l 2.~l (1.1) Ambient air intake: -17 to 102*F (1.2) Humidity: maximuin 100%
(2) Weather Disturbances (2.1) A tornado pressure transient causing an atmospheric pressure reduction of 3 psi in 3 s!conds followed by a dse to nont.a1 pressure in 3 seconds; a shorter transient (1.5 seconds) will not affect engine operation and output.
(2.2) A hurHeane or northeastern stonn pressure of 26 in, of mercury for a duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; the engine is capable of continued operation fcr up to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> at 26 in of mercury with na effect on operation and. output.
- u t.
.In a. meeting. wit!r Colt Industries in Philadelphia on June g to 10,-
1982, the diesal engine manufacturer stated that no load and light.
\ load operation of the dieser engines at low ambient temperatures'is The an unacceptable operating condition for Colt engines.
manufacturer stated that, under these environmental conditions, the diesel engine would. fa1T to operate properly because there would be insufficient turbocharger preheating'of the combustion air and -
potential' fuel oil degradation. The diesel engine could fail within a. short period of time. ._
~
Failure'under these environmental conditions could possibly prevent To diesel engine restart upon a subsequent loss of offsite power.
alleviate this condition, the manufacturer reconinends a minimum leading of the engine based on the outside ambient temperatures
1430 1 9 4
(e.g. at -10*F, the diesel would have to be Icaded to between 60%
to 66% of full load to prevent engine failure). This would require the paralleling of the onsite (diesel generator) power source with the offsite pcwer source for extended periods of time. This is unacceptable to the staff and would violate the independence requirement of GDC 17. In letters dated February 1 and 14,1983, Public Service of New Hampshire, which has similar diesel engines at its Seabrook Plant, stated that the diesel engine manufacturer
~
- had advised them that an air temperature of 50*F or greater at the turbocharger inlet would allow continuous no-load and light-load-
' operation- of the diesel generato'rs. Operation with inlet air temperatures below 50'F would require preheating of the combustion air ..
t
, g Based- on preliminary infomation supplied by Beaver, Valley, the manufacturer now states that the diesel e'ngines carr operate at k.
no-load, light-load and rated-load conditions with no degradation
.of the- engine's operating characteristics or ability to accept and The carry Toad-when operated at stated ambient service conditions. ,
applicant has n'ot prodidad femal documentation to substantiate the _
manufacturer's new. statement nor has he- shown that the diesels can accept full load within the required accident load sequence '_
l following such operation as stated in Section 8.3.1 of this SER. -
We are pursuing this issue with the applicant. -
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- required for the system, subsystem, tr ain, component , or device to -
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.h Kev: G11M/1.03534 Line: 1 STOWEEN BSN A CGLTFMPTS EELT BELO FEBRUARY 6. 1985 16 PD 3:45~PM BELOIT. WI ATTN ' LOREN MONTY STCNE AND WEBSTER. BOSTON. MA REFERENCE YOUR TELEX OCTOBER 23. 1984. THERE IS NO DEGRADING OF UNITS RATING UP TO -20 DEGREES F. THE LETTER TO STCNE AND WEBSTER DATED.. APRIL 28. 1983 AS TO THEIR RATING. ALSG AP3 LIES TO' BEAVER VALLEY UNITS.
REAGARDS.
JAY. JOHNSON CCLT IND-FAIRBANKS MORSE STOW 5EN BSN A COLTFMPTS BELT-
"ime: 13:59 02/06/85 ???
Connect Time : 103 seconds
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54 n1224106sra8bd 07/07/84 BVPS-2 FSAR NRC Letter: September 19, 1983 1.10 1.14 Question 430.138 (Section 10.3.1)
You state in Section 10.3.1 of the FSAR that the main steam system is 1.15 1 of NUREG-0138, and that 1.16 designed in accordance with Issue No.
3 credit is being taken for all valves downstream of the main steam 1.17 1.18 isolation valve (MSIV) to limit blowdown of a second steam generator in the event of a steam line break upstream of the MSIV. In order to 1.19 line break, confirm satisfactory performance following such a steam you provided a tabulation (Table 10.3-1) in the FSAR of all flow 1.20 the 1.21 paths that branch off the ma'in steam lines between the MSIVs and turbine stop valves. For each flow path originating at the main 1.22 1.23 steam lines, the following information was provided: .
1.29 a) System identification, 1.30 b) Maximum steam flow in pounds per hour, 1.31 c) Type of shut-off valve (s),
1.32 d) Size of valve (s), .
1.33 e) Quality of the valve (s),
1.34 ri
~
f) Design code of the valve (s),
A. 1.25 g) Closure time of the valve (s), and (such as, solenoid- 1.36 h) Actuation mechanism of the valve (s) 1.37 operated, motor-operated, and air-operated diaphram valves).
Sufficient descriptive info rmation was not provided in the FSAR to 1.39 confirm satisfactory performance following such a steam line break.
1.40 1.41 Provide the following:
a) In the event of the postulate,d accident, termination of 1.43 1.44 steam flow from all systems identified in Table 10.3-1, except those that can be used for mitigation of the accident, is required to bring the reactor to a safe cold 1.45 1.46 shutdown. For these systems describe what design features have been incorporated to assure closure of the steam shut
- 1.47 off valve (s). Describe what operator actions (if any) are 1.4S required. '
1.49 b) If the systems .that can be used for mitigation to of theuse 1.50 accident are not available or a decision is made other means to shut down the reactor, describe how these i.5:
systems are secured to assure positive steam shut-off. 1.53 Describe what operator actions ( f any) are required.
L i
430.13S-1 September 1964 Amendment 8 i
I L
54 n1224106sra8bd 07/07/84 BVPS-2 FSAR c) Show that failure to isolate or secure these systems will 1.54 1.55 not result in a blowdown of more than one steam generator.
1.57 If any of the requested information is presently included in the FSAR found 1.58 text. provide only the references where the information may be (SRP 10.3. Parts II and III).
2.1
Response
2.2
! Closure.of steam shutoff valves is not required for any of the branch 2.3 lines off the main steam lines.
2.4 Reheat steam flow to the tube side of the reheater will cease when 2.5 flow from the high pressure turbine exhaust to the shell side of the 2.6 reheater. is terminated by a turbine trip. .
Turbine bypass steam flow to the main condenser is autematically the control 2.8 2.7 controlled. Following Ifa offsite loss of offsite power (LOOP),
power remains available, the valves 2.9 valves will close. 2.10 vill modulate to control the cooldown of the reactor (Section 7.7).
2.11 The flow from all the remaining branch lines in combination is the so 2.12 small that it will have an insignificant effect compared to 2.13 effect of the postulated double-ended rupture of main steam line.
2.14 This flow is less than the flow which would passTherefore, through a main steam 2.15 postulation safety valve or power-operated relief valv4.
(" of failure of a safety or relief valve as the single failure is more 2.16
(
restrictive than postulation of an MSIV failure.
2.17 As stated in Section 15.1.5.2. the most restrictive single failure is 2.18
. assumed to occur in the safety injection system for the analysis of a main steam line break.
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TO TWO 6TE9M GEpK/19T046 Sdb G M 4ximVM FfMbwdM/- f TE M96L4 Tw C OF 120', THis ccw ATCG To cJE4TE.E T#,9r) l 170,000 Poupis/mg cf FEFh wGrCA FrouJ. TA6tc 10,3-1 P(LoKDEs sTc A A Ftow s Fct2. m A \ O STCAM LI O & MApC U 1
'0" CGIC ASS , Ey C LO'b I v3(, RE II(E AT STS AM FLbD A d b T U A OIIJ E NPAGS Flow Fo/2 RfE Aso"5 bisc u6 Sr:b A 6 dt//E, TI4E T074c 0F ALL LA/)pCH FL0usS C AD 6C. SCfM TO &E WS.s TIM!d DOMO f0DM/kg, 420.128-: Septembu 6
. Amenddent a
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*n12:4106sraSaf 07/07/84
NRC Letter September 19, 1983 19 1.13 l Question 430.*.44-(Section 10.4.4.4) and initial field 1.14 In Sectien. 10.4.4.4 you have discussed tests inspection but 1.15 inspection inspections at refueling, and iis-sereice not the frequency of in-service testing and inspection FSAR of .he turbine (SRP 10.4.4, 1.16 bypass system. Provide .his informatien in the Part I).
1.17
Response
turbine bypass system- (TSS) is not included in the ASME 1.18 The Inspection Program. During preeperational 1.19 Section X: In-se r/ic e testing to Regulatory Guide 1.68, the TSS centrol valves and centrols The 1.21 will be inspected and tested as described in .Section 14.2.12.
TES. piping is inspected and tested in accordance with Paragraphs 136 and 137 of ANSI B31.1. #MetecC TEST 196 #6 dot O EC E$$ /)/l/ .
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l Septemcer 1924 i Amendment 8 Q4:0.144-1
Lighting and Consnunications The . general bases for the design of the BVPS-2 lighting and communica-tions systems follow the basic design criteria of the BVPS-1 lighting
- and communication systems. The systems are designed to provide ef fec -
tive, reliable communications between the safe shutdown control stations and : other task areas of BVPS-2 during trans ient , fire, and accident conditions, including the loss of offsite power.
- The systes description for communications is < detailed in FSAR section 9.5.2. A listing of station areas and the types of communications systems available in the various areas is given in the response to FSAR
- question 430.56. A discussion of the power supplies is detailed further in the response to FSAR question 430.68. Additional information about
' the communication systems is . given in the responses to FSAR questions 430.57, 430.58, 430.59, and 430.60.
The system description for lighting .is detailed - in FSAR section 9.5.3.
A listing of station areas and the types of lighting systems available in the various areas is given in the responses to FSAR question 430.61.
A discussion of ' r.e power supplies is detailed further in the response to FSAR questiona 430.63 and 430.66. A discussion of illumination levels is given in the response to FSAR question 430.65. Additional information is given in the responses to FSAR questions 430.62, 430.64, and 430.67.
Defense in depth is provided at BVPS-2 by the various types of communi-
' cation system powered by a number of sources which are detailed in FSAR section 9.5.2. Similarly, defense in depth is provided by the various types of lighting systems powered by a number of dif ferent sources, which are detailed in FSAR section 9.5.3. The installation of these integrated lighting and communication systems ensures that BVPS-2 will l
have ef fective and reliable lighting and communications during tran-
! sients, fires, and accident conditions, including the loss of of fsite power.
DLC letter 2NRC-5-024 (dated February 13 , 1985) provided additional l information relating to the non-s afe ty diesel which supplies backup I power to some of the lighting and communication systems. The non-safety diesel building conforms to applicable state, and national building codes. The power cables from this building to the BVPS-2 plant are routed underground. A 30,000 gallon (7 day supply), two fuel pumps, and a 270 gallon day tank provide fuel to the non-safety diesel. NUREG-0696 and NUREG-0737 requirements were factored into the design of the system.
l Many of the attributes were factored into the design of the system.
I Many of the attributes in Reg. Guide 1.137 are paralleled by ERF/TMI
-NUREGS.
Maintenance and testing of the non-safety diesel and batteries will be similar to that pe rformed on comparable safety related diesels and batteries.
The multiple systems, described above and in the referenced documents, together with the diverse, multiple power sources, and the seismic mounting of many components provide a high degree of assurance that sufficient lighting and communications will be available to facilitate safe shutdown even in the unlikely event of a loss of of f-site power j
concurrent with a design basis event.
I I
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Diesel Generator Air Dryer Backfit Issue DLC has requested further information from the diesel generator vendor with regard to this issue. It has been decided that if the requested information shows that the vendor strongly recommends the use of air dryers to obtain adequate reliability, the dryers will be installed at BVPS-2.
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