Letter Sequence Other |
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Results
Other: ML20196A234, ML20207L533, ML20209F820, ML20211B995, ML20213A567, ML20214J698, ML20214J930, ML20214J973, ML20234C463, ML20234E291, ML20235J298
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MONTHYEARML20138D9431985-10-17017 October 1985 Notification of 851022 Meeting W/Util & S&W in Bethesda,Md to Discuss Fire Protection Deviation Requests Project stage: Meeting ML20206J0051986-06-23023 June 1986 Forwards Documentation of Attendees at 841130 & 1207,850117, 0820,0919 & 1022 Meetings W/Util Re Structural Engineering, Geosciences Issues,Pressure Isolation Valves,Power Sys, Computer Code Multiflex & Fire Protection,Respectively Project stage: Meeting ML20215K7361986-10-23023 October 1986 Notification of 861105 Meeting W/Util in Bethesda,Md to Discuss Issues Re Fire Protection,Including Util Deviations from Staff Technical Position Project stage: Meeting ML20214D3181986-11-18018 November 1986 Summary of 861105 Meeting W/Util,Stone & Webster & Franklin Research Inst Re Fire Protection Issues.Draft Sser 3,list of Deviations from SRP 9.5.1,agenda & List of Attendees Encl 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 ML20209F8201987-01-30030 January 1987 Forwards Amend 14 to Fsar,Consisting of Updated FSAR Fire Protection Info Provided in Author .Info Affects Section 9.5.1 of SER 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 ML20211B9951987-02-11011 February 1987 Forwards Addl Info Re Fire Protection,Including Info Re SRP Deviation on Structural Steel & Vendor Justification of Thickness Requirements for HVAC Ductwork Fire Wrap,Per NRC 870126-30 Fire Protection Site Visit Project stage: Other ML20210C3141987-04-30030 April 1987 Forwards Request for Addl Info Re Confirmatory Issue 46, Fire Protection Deviations & Confirmatory Issue 46, Control Room Isolations on High Radiation Signals. Encl Provides Background Info for Telcon.No Response Required Project stage: RAI ML20214J6981987-05-18018 May 1987 Describes Fire Detection & Suppression Sys at Facility (Ref NRC ).Present Capability of Sys Adequate & Overall Plant Safety Would Not Be Significantly Increased by Modifying Suppression Sys Alarm Circuits.W/Four Figures Project stage: Other ML20214J9301987-05-18018 May 1987 Forwards Changes Expected to Occur in Next Rev to Amend 18 of Fsar,Section 9.5 Re Fire Protection Project stage: Other ML20214J9731987-05-20020 May 1987 Provides Compensatory Measures to Deal W/Fire Zones Containing Equipment Necessary for Tech Spec Equipment Operability Where fire-rated Assemblies Incomplete.Hourly Fire Patrols Conducted When Necessary Project stage: Other IR 05000412/19870371987-05-28028 May 1987 Insp Rept 50-412/87-37 on 870420-0501.No Violations Noted. Major Areas Inspected:Preoperation & Startup Test Program, Startup Test Procedure Review,Qa Interfaces & Emergency Diesel Generator Instrumentation Vibration Project stage: Request ML20234C4631987-06-24024 June 1987 Forwards Util Comments on Low Power License for Facility, Including Discussion of Fire Protection & Plant Safety Monitoring Sys.Util Will Work W/Nrc Project Manager to Resolve Comments Project stage: Other ML20235J2981987-07-0606 July 1987 Responds to Questions Posed by D Kubicki in Telecon Re Fire Protection Supervisory Circuits & Schedule for Completion Project stage: Other ML20235Q7051987-09-30030 September 1987 Forwards Testing Status of CO2 Fire Suppression Sys. Overpressure Problems Associated w/CO2 Discharge Testing Eliminated by Installation of Back Draft Dampers.Expected Completion Date Revised to 871231 Project stage: Draft Other ML20234E2911987-12-31031 December 1987 Advises That CO2 Concentration Testing Successfully Completed for All Eight Zones,Per 870930 Commitment to Provide Schedule for Completion of Unfinished Fire Protection Items Project stage: Other ML20196A2341988-06-20020 June 1988 Concludes That Based on Licensee Annual Rept of Facility, Changes,Tests & Experiments & 880608 Site Visit, Changes,Tests & Experiments Meet Criteria in 10CFR50.59. Lists Improvements Recommended to Licensee During Visit Project stage: Other 1987-02-11
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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
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2NRC-7-13I (412)393 7546 Beaver Valley No. 2 Unit Project Organization Telecopy (412) 393-7889 S G
.Bof " May 18, 1987 shippingport, PA 15077 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Beaver Valley Power Station Unit No. 2 Docket No. 50-412 FSAR Amendment 18 Changes - Section 9.5 Fire Protection Gentlemen:
Attached is a copy of changes which are currently expected to occur in the next revision to the Beaver Valley Unit 2 FSAR, Amendment No.18. The formal FSAR Amendaient will be the same or very similar to the attached copy.
If you should have any questions, please call Mr. R. W. Roth at (412) 643-5200, Extension 154.
DUQUESNE LIGHT COMPANY l
By J. Q/ Carey V Senior Vice President RWR/ijr NR/RWR/AMND/18 Attachments AR/NAR cc: Mr. P. Tam, Project Manager (w/a)
Mr. J. Beall, NRC Sr. Resident Inspector (w/a)
Mr. L. Prividy, NRC Resident Inspector (w/a)
Mr. William T. Russell, NRC Region I Administrator (w/a)
INP0 Records Center (w/o/a) 8705280256 870518 2 [
PDR ADCCK 0500 sj i
United States Nuclear Regulatory Commission FSAR Amendment 18 Changes Page 2 COMMONWEALTH OF PENNSYLVANIA )
) SS:
COUNTY OF BEAVER )
On this / - day of [4/p , /k[ , before me,- a Notary Public in and for said Commonwedith and County, personally appeared J.
J. Carey, who being duly sworn, deposed and said that (1) he is Senior Vice
, President of Duquesne Light, (2) he is duly authorized to execute and file the
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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.
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Notary Public sumA S. FAITSEE,30fARV PUEUC suirrimsresiese,sEMER COestV rY cossessies EIPseES SCT. 23,1950
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SUBJECT:
Modified Fire Doors Q/ 947/ [/C ,
Item C.5.a(5):
The Standard Review Plan states that door openings in fire barriers should be protected with equivalently rated doors, frames, and hardware. that have been tested and approved by . a nationally recognized laboratory. Such doors should be.self-closing or provided with closing mechanisms and ~ should be inspected semiannually to verify that automatic hold-open, release, and closing mechanisms and latches are operable. (See NFPA 80, " Fire Doors and Windows.")
Differences from the SRP:
, a. Fire door assemblies have been modified from their tested configuration by the addition of security hardware and alarm equipment as required.by NRt: regulation,
- b. Rolling steel fire doors in the safeguards building have had the lower jam modified fre n the tested configuration to allow for the installation and removal of equipment. The rolling steel door separat.ing the turbine building and South office Shops Building (SOSB) is not fire-rated,
- c. Special purpose-type door assemblies (containment access doors / hatches) are not UL rated.
, Justifications:
- a. These modifications were made following the guidelines suggested by Underwriters Laboratories. They are similar to those made on BVPS-1 which were reviewed and found acceptable by the NRC. The door areas have either automatic detection and suppression or manual fire fighting equipment available in the areas. The security alarmed doors also have remote monitoring -capability via the security system video monitors and the alarm function in the event the door is left open, which would alert personnel of an abnormal condition in these areas.
N -
- hac.c.L,ik Fire door assemblies in fire barriers separating safety- N
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[W4 54-% related areas will bear a UL label denoting the required fire rating or the door will have certification from the
( vendor identifying the fire rating. ,
Table 9.5A-2 provides the list of fire doors with security modifications including the fire severities and methods of fire suppression for the areas separated by these doors.
- b. The rolling steel doors in the north and south safeguards areas are not used to separate adjacent fire areas but are used to separate the stairwell within a fire area from the Amendment 16 9.5A-126 April 1987 4
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BUPS-2 FSAR
-*g
SUBJECT:
Safe Shutdown Components Item C.S.b The Standard Review Plan states that one of the redundant trains is to be free of fire damage so that safe shutdown can be . achieved.
This can be a,chieved by: '
a) Separating redundant trains by a fire barrier having a 3-hour rating.
b) Separating redundant trains by a horizontal distance of more than 20 feet with no intervening. combustibles or fire hazards. In addition, fire detectors and an automatic fire suppression system should be installed in the fire area.
c) Enclosing one redundant train in a fire barrier having a 1-hour rating. In addition, fire detectors and an automatic fire suppression system should be installed in the fire area.
Differences from the SRP:
The following safe shutdown components have not been provided with edequate separation as noted above:
DESCRIPTION MARK NUMBER FIRE AREA (1) Charging Pumps 2CHS*P21A,B,C PA-3 (2) Component Cooling Water Pumps 2CCP*P21A,B,C PA-3 (3) Boric Acid Transfer Pumps and 2CHS*P22A,B PA-4 Storage Tanks TK21A,B PA-4 (4) Charging System Control Valves 2CHS*LCV1158,D .PA-3 2CHS*FCV113A PA-3 2CHS*MOV350 PA-3 (5) Emergency Switchgear Supply 2HVZ*FN261A,8 CV-4 and Exhaust Fans 2HVZ*FN262A,5 CV-4 (C) Emergency Switchgear Supply 2HVZ* MOD 21A,8 CV-4 and Exhaust Dampers 2HVZ* MOD 22A,B (7) Emergency Exhaust Fans CV-4 2HVP*FN264A,8 PA-4 (8) Auxiliary Feedwater Control Valves 2FWE*HVC100A,B,C,D,E F SG-15 (9) Atmospheric Steam Dump Valves 2SVS*PCV101A,B,C MS-1 2SVS*HVC104 4y7 MS-1 (10) Main Steam Isolation valves 2 MSS
- 1A,B,C . MS-1 (11) Equipment inside containment (Various) RC-1 Justifications:
- 1. The charging pumps (2CHS*P21A,B,C) are located in three cubicles adjacent to each other in the auxiliary. building, el. 735 ft-6 in. The. communicating walls between the
?
Amendment 14 9.5A-129 February 1987 I
EVPS-2 FSAR j cubicles are 2-foot-thick concrete _ walls with " all penetrations sealed with 3-hour fire seals.
4 any Ds** / 9.S- H
e west wall of each cubicle is composed of a 4 roos- m T concrete block wall with a small' opening at the top for the crane . rail to pass through. The wall is built up of removable concrete - sections to facilitna --- -I ^F a-(
(\
charcina pump for maistenance T The- east wall of each cubicle is a 2-foot-thick concrete wall and has a labyrinth-type opening for missile and radiation scatter protection.
Charging pumps are arranged such that the "A" pump is separated by more than 20 feet from the "B" pump with the "C" pump (swing pump) in between. Walls extend from a 3-hour rated floor to a 3-hou'r rated ceiling. Power cables to l' redundant pump trains are provided with full 3-hour
- separation. A curb.is provided in each opening to contain
' any oil spills within the cubicle. Each cubicle is provided with a drain to prevent accumulation of spilled oil.
i Additionally, the entire area of PA-3 including the cubicles is protected by an early warning smoke detection system.
.The total combustible loading for the PA-3 area in which the-three cubicles are located is less than 1-hour duration.
Each charging pump contains 51 gallons of lube oil which equates to a less than 1/2-hour fire duration.- Note that this assumes a total burnout of the entire inventory of oil which could only be coincident with a total failure of the cubicle drainage system.
Cable insulation composes the majority of the fire loading in PA-3. All cables not in conduit are IEEE-383-1974 rated, which inhibits fire spread. This cable will not propagate fire even if its outer covering and insulation have been destroyed in the area of flame impingement. BVPS-2 postulates the worst possible fire in ~ 'thi's area to be a slow-developing cable type of fire. This type of fire would be detected in its incipient stages by the early warning smoke detection system and responded to by the plant fire brigade prior to the development of any major fire involvement.
DLC administratively controls all flammable liquids. For radiological reasons, these cubicles are restricted access and out of normal travel routes.
Therefore, considering the original des'ign philosophies, the type of fire hazard, the worst postulated fire, the separation of the cubicles, the smoke detection system, and the lack of transient combustibles, this configuration i ensures that at least one train will be free of fire damage !
to achieve safe shutdown. i I
Amendment 14 9.5A-130 February 1987
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- 4. Charging System Suction Valves-The charging system is used to previde borated water to the reactor coolant system using the charging pumps. The charging pumps are provided with four suction paths for safe shutdown. Two paths are from the refueling water storage tank (suction isolation 2CHS*HOV350 and 2CHS*FCV113A). The refueling water suction valves (2CHS*LCV115B and D) are located together in the valve cubicle on the 718 ft-6 in.
d elevation of the auxiliary building. The boric acid storage tank suction valves (2CHS*MOV350 and 2CHS*FCV113A) are located together on the 710 ft-6 in. elevation of the auxiliary building. These valves are not separated by 3-hour fire. barrier and there is approximately 15 feet between the 2CHS*LCV115B and D valves and the 2CHS*MOV350 and 2CHS*FCV113A valves. For radiation hazard reasons, these areas are restricted access and are out of normal plant travel routes. The only combustible within the area are the motor cperators on the valves. The motors are totally enclosed and a total burnout of one motor would not affect the operation of the other motors. The valves can be ppened manually if required and the cables to 2CHS*LCV11$Dhavear 15 been protected in place by a 1-hour' fire-rated material.
Due to the fact that only one out of the four valves has to operate, the area contains negligible combustibles (all cables'in the area are in conduits), and the area is provided with general area fire detection and hose racks and portable fire extinguishers, a fire in the area will not prevent safe shutdown.
- 5. Emergency Switchgear Room Supply and Exhaust Fans (2HVZ*FN261A,B and 262A,B)
The supply fans (2HVZ"FN261A,B) supply air to the emergency switchgear rooms (SB-1 and SB-2). These fans are axial fans and are located (along with the motors) in the ductwork in the cable vault rod control area, el 773 ft-6 in. (CV-4).
The fans are parallel to one another and only one fan is required for shutdown. The motors for the fans are totally enclosed motors and the cables for 2HVZ*FN261A are protected in place with a 1-hour fire-rated material in the area outside of the ductwork.
Based on the design of the ductwork, the negligible combustible loading (all cables are in conduits in this area), the fire detection system, and manual hose racks, adequate protection is provided to prevent the spread of a fire from one fan to the other.
Amendment 14 9.5A-132 February 1987
SUPS-2 FSAR
/(/f/dy'
- 8. The auxiliary feedwater control valves are located is'the south safeguards building (SG-15). These valves.are hydro-electrically operated, normally open valves, that on loss of electrical control fail as is, and on loss of hydraulic oil,
' auxiliary feedwater flow will open the valve (the desired position). The combustible loading in SG-15 is less than 1/2 hour. Throttling.on the discharge valve for auxiliary feedwater pump 2FWE-P238 can be done to achieve shutdown.
- 9. The atmospheric steam dump. valves (2SVS*PCV101A, B, and C
' and 2SVS*HCV104) are all located in the main steam valve house and have not been provided with 3-hour separation.
They are partially separated by concrete walls which extend at least 2 feet beyond the valves. The valves are' located approximately 25 feet above the floor. The main steam valve house has a combustible loading of less than 1/2 hour.
Ao/
, 10. The mainsteamisolationvalves(2 MSS 9([FICIA,B,andC)are located in the main steam valve house. The valves are-
'f(
required to close to provide isolation for the steam generators.
ine main steam valves are normally latenen open-a w-f during p operation. The valves are closed by springs f when the latch is released.. Only one out of the three solenoid operated valves per main steam valves is required to operate to close .the main steam valve. . Two of the edG/ j$ solenoids are designed *n Am-enorcize while the third 1 3/
desianed to energize.1 The main steam valve house.has a fire l Skete/ severity rating of <1/2 hour and automatic fire detection 1
ggj_jyy with hose racks and portable fire extinguishers has been; 4#'*~ provided. Therefore a fire in the area will not prevent the main steam isolation valves from closing.
I
- 11. The following systems have equipment located in the primary-3 reactor containment (RC-1):
- a. Reactor Coolant System (RCS) Letdown j b. RCS Depressurization i
i
- c. Process Instrumentation
)
j d.* Residual Heat Removal (RHS) e' . Safety Injection Accumulator Isolation / Venting The following assumptions were used in evaluating system i
availability and dictating manual actions.
- a. The plant experiences a fire in Fire. Area RC-1.
! b. The fire is localized in nature and fires are not postulated from transient sources.
l l
Amendment 14 9.5A-134 February 1987
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- t BVPS-2 FSAR
/. [
SUBJECT:
Safe Shutdown Circuitry, ,
Item C.5.b: ,
h The Standard Review Plan states that one of the redundant trains is to be, free of fire damage so that safe shutdown can be achieved.
This can be achieved by:
i .
a) Separating redundant trains by a fire barrier having a 3-
, hour rating. 1 b) Separating redundant trains by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards. In addition, fire detectors and an automatic fire suppression system should be installed in the fire area.
c) Enclosing one redundant train in a fire barrier having a 1-hour rating. In addition, fire detectors and an automatic fire suppression system should be installed in the fire area.
Differences from the SRP: ,
The following areas have redundant circuitry and do.not meet the j guidelines of C.S.b, nor is alternate shutdown capability provided (1) Cable Vaults (CV-4 and CV-5)
(2) Primary Auxiliary Building (PA-4)-
(3) South Safeguards Building (SG-15)
(4) Service Building Normal Switchgear (55-4)
C5 CAs p.;.p .s~ pas s .G- sehe om (M-tJ Justif cation:
3,5 (1) Fire Areas CV-4 and CV-5 contain redundant circuitry for various components of the emergency switchgear ventilation systems. The i
combustible loading for each area is less than 1/2 hour. All cables in these areas are routed in conduit. In addition, orange 4
' cables for the equipment have been protected using a 1-hour fire-wrap material. Fire detection for these areas consists of area i
ionization detectors which alarm locally and in the control room.
Portable fire extinguishers are located in these areas with manual hose stations located immediately adjacent to these areas.
Based'en the low combustible loading fire detection present, and the fact that redundant cabling required for shutdown has been provided with additional protection, the means of suppression is adequate to protect the hazard and provide the required separation. N _
(2) The auxiliary building, elevation 755 ft-6 in contains redundant circuitry for various shutdown components. The combustible !
loading for this area is less than 1/2 hour. This area is compartmentalized for radiological and safety-related concerns.
Various cabling has been protected using a 1-hour fire-wrap Amendment 16 9.5A-144 April 1987 i
._ . , - - _ ~
BVPS-2 FSAR f[
material. Fire detection for these areas consists of area ionization detectors which alarm locally and in the control room.
Portable fire extinguishers are located in the' -area and manual hose stations are located in the stairwells adjacent to this area. Based on the low amount of combustible loading, the fire detection present, and the fact that redundant cabling required ;
for shutdown has been provided with additional protection, the means of suppression available is adequate to protect the hazard and provide the required separation.
(3) The south safeguards building contains redundant circuitry for !
various components of the auxiliary feedwater system. The I loading for the combustible fire area is less than 1/2 hour.
Purple cables for this equipment have been protected using 1-hour fire-wrap material.
Fire detection for this area consists of area ionization detectors which alarm locally and in the control room. Portable fire extinguishers and manual hose stations are located in this area. Based on the low combustible loading, the fire detection present, and the fact that redundant cabling required for shutdown has been provided with additional protection, the means of suppression is adequate to protect the hazard and provide the required separation.
(4) The service building normal switchgear room contains redundant circuitry for the ventilation systems to the emergency diesel generator. building. The combustible loading for this fire area is less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Orange cables for the equipment have been protected in place using a 1-hour fire-rated material. Fire detection for this area consists of area . ionization smoke detectors which alarm locally and in the control room. Portable fire extinguishers and manual hota stations are located in the area. Based on the low combunible loading, the fire detection present, and the fact that redundant cabling required for i
shutdown has been provided with additional protection, the means of suppression is adequate to protect the hazard and provide the required separation.
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- Amendment 16
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BUPS-2 FSAR
SUBJECT:
Cable Rooms: CO 2 Vs Water !
Item C.S.e(2):
The SRP states that in other areas where it may not be possible because of other overriding design features necessary for reasons of nuclear safety to separate redundant safety-related cable systems by 3-hour-rated fire barriers, cable trays should be protected by an automatic water system with open-head deluge or open directional spray nozzles arranged so that adequate water coverage is provided for each cable tray. Such cable trays should also be protected from the effects of a potential exposure fire by providing automatic water suppression in the area where such a fire could occur. The capability to achieve and maintain safe shutdown considering the effects of a fire involving fixed and potential transient combustibles should be evaluated with and without actuation of the automatic suppression system and should be justified on a suitably defined basis.
Difference from the SRP The following fire areas use CO, as the primary automatic suppressant '
instead of waters a) Control Building' (Fire Areas CB-1, CB-2, and CT-1) b) Cable Vaults (CV-1, 2, and 3)
{ c) Service Building Elevation 745 ft-6 in. (SB-4)
Justification:
The automatic or manual, double-capacity, total flooding CO 2 system, in conjunction with the hose rack stations and portable fire extinguishers, provides adequate protection to extinguish fires and ensure the safety of these areas.
Two potential fires are postulated for these areas: a short-circuit-induced cable fire and a fire involving transient combustibles.
Hazardous quantities of transient combustibles are not expected in these areas for several reasons. First, the areas are not near any major plant traffic route. Second, maintenance and operations in these areas do not involve the use of combustible materials. Third, accessibility to these areas is restricted to personnel performing essential duties. The potential for a cable fir limited by the use of IEEE 363 qualified cable throughout.
dditionally,allpoweb caDAe in enese areas is run in coliauits; only low nower control or/
instrumentation cabling is run in trays. The cable trays ari Ided wittli cable tray covers and/or ottoms to conform with Regulatory Guide 1.75.
i Fire detection is provided by the early warning fire detection system !
which provides fire alarms locally and in the control room. '
Qiuli ply capacIfis~ available for a secoiid shual appli' cati ~o~n,/ o a'The$ l
~
_ __ ~ ~ _ _ 4 4g, 3 9
Amendment 14
- ' ht f'7 9.5A-150 February 1987 l l
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--- - - - - - ;,7 - - -- - --~]
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A q l s / BVPS-2 F5AR f,.,:.n,
'l Coa qsystto is ' f. designed to attain a 50-peident 1 \Q.I concentratten j ,
as
/g f
/
. secommended for cable fires (NFPA-12). Automatic actuation of the CO systes,is provided by the "XL-3" fire detection system which is a
-3 j i_I " Priority
- system with local and cortrol room. alarms. The alarms
.i I
Q enaoLe the.; control room to be aware of the status and availability of
'c /- ,
the con system et all times. A timed delay is provided in the co it.itiation cycle to provide for personnel encuation. co, supply capacity-is available for a sectsd manual application. Co, will y penetrate to *he source of the fire and is less likely to cause
^' . I damage to electrical equipment. Hose racks are provided at the-j entrance to the cak,',.e spreading room, and all trays can be reached by s hose streams'. x /,
'e< j {
Penetruiocs (to. thue areas are sealed to prevent leakage of Coa
~
to occupied spacek Yoperating personnel of Unit 1 have had several 1 years of experien:s with total flooding con systems. All personnel i
are trained in alarn recognition and evacuation procedures. The systems are generally disarmed- only during an outage for major maintenance functions, and a fire watch is posted during the disarmed period. The system is not disarmed during daily operational s activities in the area. In the unlikely event of a fire in this 3',.g/t) area, the fir *>Te9 would be required to have breathing apparatus. .
Ine cable trays located in these areas are utilized largely for y instrumentation and control cables. These trays will be provided '
with flat, unventilated covers and/or bottoms. dower r =m a = =ra (2n riola conouit.y The presence of tray covers inhibits the ability PN of water to reach potential tray fires. co nby virtue of its gaseous ;
' state, will penetrate into the -cable trays and provide fire suppression' to the fire in its incipient stage and will prevent a deep-seated fire from occurrir.g. Due to the stack arrangements of the cable trays and the fact that the trays are provided with covers 2<
3 e
and/or' bottoms, a ceiling-mounted automatic water suppression system y would not provide adequate
? extinguished. assurance that- a fire will be
'l I. cI i
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i Amendment 16 9.54-151 April 1987 l
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~ - _ _ , _ _ _ _ _ _ _ .. _ _ _ . . _. _ _ _ _ _-__ _ l
l BVPS-2 FSAR '
SUBJECT:
Cable Spreading Room /W51 !
Item C.7.c:
, The Standard Review Plan states thats
- a. The primary fire suppression in the cable spreading room. -
should be an automatic water system.
- b. A 3 feet wide by 8 feet high aisle separation should be provided between tray stacks.
- c. Continuous line-type heat detectors should be provided for cable trays. -
Differences from the SRP:
- a. The primary fire suppression system for the BVPS-2 cable spreading room is an automatic or manual, double-capacity, total flooding CO 2 system. Mose rack stations and portable fire extinguishers are provided as backup suppression.
[ b. There are certain aisles in the cable spreading room which are partially blocked by structural members resulting in 1
aisle dimensions which are less than the 3 feet wide by 8 feet high criterion.
c.
i BVPS-2 has been equipped with alternate means of detecting cable fires.
Justification:
- a. The automatic or manual, double-capacity, total flooding Coa system, in conjunction with the hose rack stations and portable fire extinguishers, provides. adequate protection to extinguish fires and ensure the safety of the cable spreading room.
l
- Two potential fires are postulated for the. cable spreading areas a short-circuit-induced cable fire' and 'a fire involving transient combustibles. Hazardous quantities of transient combustibles are not expected in these areas for several reasons. First, the areas are not near any major plant traffic route. Second,-maintenance and operations 'in these areas do not involve the use of combustible materials.
Third, accessibility to these areas ~is restricted . to - ;
personnel performing essential duties. The potential for a !
cable fire is limited by the use of IEEE 383 qualified cable-throuchout. [Auw haunally, all power cacAe an enese areas is l run in conVuits: only low power control or instrumentati- 4 cabling is run in traysf The cable trays are provided with j Amendment 14 9.5A-158 February 1987 i
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. BUPS-2 FSAR
SUBJECT:
Safety-Related Pumps Item C.7.k:
The Standard Review Plan recommends that pump houses and rooms housing each redundant safety-related pump trains should be separated from other and from other areas of the plant by fire barriers having at least 3-hour ratings.
{
Difference from the SRP:
)
The fuel pool cooling pumps are not_ required for safe shutdown following a fire and are protected by means other than 3-hour barriers. (For safety-related pumps and tanks used for safe shutdown, see Item c.5.b - Safe Shutdown components.) f Justification:
The fuel pool cooling pumps are not required for safe shutdown as a result of fire in any plant area. Fire detection is accomplished by the use of ionization detectors, which have audible alarms locally and audiovisual annunciation in the main control room. Portable extinguishers and suppression. hose rack stations are available for fire These pumps are located in areas with low comhustible loading. Refer J
- to the fire hazards analysis for area (@N, SG-15, au g FB-1. In the event s that both fuel pool cooling pumps are lost, the fuel pool 7 [C can this purpose. with service water through a connection provided for be cooled Amendment 14 9.5A-161 February 1987
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