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
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'Af 2NRC-7-026 Beaver Valley No. 2 Unit Project Organization Telecopy ( 1 ) 64 0 Ext.160 S.E.G. Building P.O. Box 328 February 11, 1987 Shippingport. PA 15077 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Peter Tan, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Infonnation Related To NRC/NRR Fire Protection Site Visit
REFERENCE:
DLC Letter 2NRC-7.n!7, dated January 28, 1987, Mr. J. J. Carey to Mr. Harold R. DentM Gentlemen:
In accordance with discussions between DLC and the NRC Fire Protection reviewers during the NRC Fire Protection Site Visit which occurred on January 26-30, 1987, the following information is attached:
Aeditional information related to SRP deviation on structural steel Revision to SRP deviation on conduits / penetration seals (FSAR Page 9.5A-121)
Revision to SRP deviation on one-hour fire wrap of ductwork (FSAR Pages 9.SA-124 and 125)
Vendor Justification of thickness requirements for HVAC ductwork fire wrap Revision to SRP deviation on modified fire doors (FSAR Pages 9.5A-126 and 127)
Revision to SRP deviation on new fuel area (FSAR Page 9.5A-162)
Additional SRP deviation on fire hydrant spacing
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United States Nuclear Regulatory Commission Mr. Harold R. Denton, Director Information Related to NRC/NRR Fire Protection Site Visit Page 2 During observation of the BVPS-2 Control Roan Shift Supervisor's Office, tne NRC Fire Protection Reviewers noted that the smoke detector is located in an apparently restricted space above the solid suspended ceiling of the office.
DLC plans to renove the existing steel wall which separates the BVPS-2 and BVPS-1 Shift Supervisor's Of fices creating one conmon office. DLC is evalua-ting the effectiveness of smoke detection currently provided on the BVPS-1 portion of the office (at ceiling level) in detecting smoke due to fires below the ceiling of the conbined office. The results of this evaluation will be avail able by March 9,1987.
During their review of the BVPS-2 smoke detector spacing, the NRC review-ers noted three locations where they felt detectors should have been installed and were not. Therefore, the reviewers requested that DLC perfonn a review to ensure that detectors have been installed where required. The results of this review are to be documented in a letter to the NRC. DLC has begun the review and final results will be available by March 9,1987.
Based on recent discussions with BVPS operations personnel, the response provided in the noted reference for Iten 3 (Fire Brigade Training)is being clarified. The response should read as follows:
Prior to fuel load all fire brigade members who would be expected to respond to a fire at BVPS-2 will undergo training specifically related to firefighting in the BVPS-2 Cable Spreading Roon. This includes all BVPS-2 licensed operators, all shif t radiation technicians, all shift cheni sts, and all non-licensed BVPS operators. Not included in this training are BVPS-1 licensed operators who would not ce expected to respond to a fire at BVPS-2. The training will incluoe walkthroughs of 1 the Cable Spreading Roan in full brigade gear.
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United States Nuclear Regulatory Cannission Mr. Harold R. Denton, Director Information Related to.NRC/NRR Fire Protection Site Visit Page 3 The FSAR revisions noted in this submittal will be incorporated into a f uture FSAR anendment. Any questions on this submittal may be directed to Mr.
J. D. O'Neil of our Regulatory Aff airs Department at (412) 393-7843.
DUQUESNE LIGHT COMPANY By
- 7. JVCarey Senior Vice President-JD0/ijr NR/JD0/ SITE /VIS Att ents AR AR cc: Mr. P. Tan, Project Manager - w/ attachments Mr. J. Beall, NRC Sr. Resident Inspector - w/attachnents Ms. A. Asars, NRC Resident inspector - w/ attachments INPO Records Center - w/attachnents NRC Document Control Desk - w/ attachments
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United States Nuclear Regulatory Commission Mr. Harold R. Denton, Director Information Related to NRC/NRR Fire Protection Site Visit Page 4 COMMONWEALTH OF PENNSYLVANIA )
SS:
r.0VNTY OF BEAVER On this // [ day of -
/((/>4%4[/ [/(( , before me, a ,
Notary Public in and for said Commonwealth dnd County, personally appeared J. J. Carey, who being duly sworn, deposeo and said that (1) he is Senior 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 statenents set forth in the Submittal are true and correct to the best of his knowl edge.
GJ Notary Public SMatA s. FAngtL MA2Y PUBUC SilPrilNiPORT B03. SEAVER CDefft FmWicios EIPigf5 0CT. 23.1989 u
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. . , , . ,..--,--------_m--- -, . - , _ . . , . . . . - _ , - _ , . . - . - _ . - . - - - m - -- -
Clarification of Structural Steel Deviation The NRC Fire Protection Reviewer requested addi tional infonnation to ensure that failure of unprotected structural steel in the upper elevations of the Service and Auxiliary Buildings (Fire Areas SB-5 and PA-5) will have no adverse impact on the safe shutdown capability.
Response
FSAR Appendix 9.5A provides results of the fire protection safe shutdown ana-lysis for these areas and concludes that safe shutdown can be achieved assuning loss of all safe shutdown cables and equipnent located in these areas.
FSAR Table 3.2-2 provices a sunmary of Seismic and QA Category I structures.
As indicated in the referenced table, the Seismic Category I seisnic and torna-do missile barrier is located at the 780' elevation for the Service Building and- at 773'-6" for the Auxiliary Building. These are the floor slabs in Fire Areas 58-5 and PA-5.
Failure of the structural steel above the tornado missile barriers will not cause danage to cunponents below as the missile boundary is capable of with-standing collapse.
In addition, FSAR Section 3.68.1.3.4.3 states in part for the Service Building that ". .
.- if non-seismic Category I portions of the structure fail, no adverse effects on adjacent Seisnic Category I structures or conponents will occur."
In conclusion, the above infonnation provides adequate justification for the
- SRP deviation on unprotected structural steel.
i
{
BVPS-2 FSAR
SUBJECT:
Conduits / Penetration Seals Item C.S.a(3):
The Standard Review Plan states that openings inside conduit larger than 4 inches in diameter should be sealed at the fire barrier, and that openings inside conduit 4 inches or less in diameter should be
- sealed at the fire barrier unless the conduit extends at least 5 feet on each side of the fire barrier and is sealed either at both ends or at the fire barrier with noncombustible material to prevent the passage of smoke and hot gases, w; S + 5 te. Se A.
Differences from the SRP: g derdl. Cow kined.
- a. Openings inside conduit / greater than 4 inches in diameter may be sealed at the first @peninolon one side of the fire barrier with fire-wrap material encasing the conduit from the fire seal to the barrier.
The4 of b s e ecco foInY b.
dloeninal inside conduit 4 inches or less in diameter which xten less than 5 feet beyond the fire barrier may be sealed at
_ Gen s withcioncomoustible materiaD to prevent the passage of smoke 7 and hot gases when a seal at the barrier is not feasible.
Justification: A "' 38 Cri
[inE ACClif PomY ^
C>ehs indds caU greder % + intLns in cVns ntee esh sida of L byr;<r
- a. hese_ openings)will be sealed at the barrier where possible. Due to clearance problems, there are specific cases where this cannot occur. For these cases, the installation of a fire seal at the first opening on one side of the barrier, combined with fire wrap from the seal to the barrier, effectively extends the fire barrier. This method provides the same degree of protection as would sealing at the barrier.
- b. Since seals at the fire barrier or at distances greater than 5) 7 feet from the fire barrier are considered to pr:/ide adequatej protection with respect to the passage of smoke and hot gases, seals between these two points would provide at least the samej (degree of protection._ _
' G A ;}s 4 inc$al or leSS in CAiawr$te A A %WA. mb burk< w;ll k .Se&L. n u.L. siL & L bs<< ev- cd +L.
N access poiM Mt 4. red cd A 6arrlv h noi -fe a tif, le .
%et n s:S<. sglae: Rc 41<a 4-e.s + ve sa ( h , % sed > a a I-tm3i[L rtd b f redM CLd4 f proftc.k h WM ff 3f'f b Pas t 9 e f AL<_ a J. k.P gare.r .
Amendment 14 9.5A-121 February 1987
BVPS-2 FSAR
SUBJECT:
One-Hour Fire Wrap of Ductwork Item C.5.a(4):
The Standard Review Plan states that penetration openings for ventilation systems should be protected by fire dampers having a rating equivalent to that required of the barrier (see NFPA-90A, " Air
- Conditioning and Ventilating Systems"). Flexible air duct coupling in ventilation and filter systems should be noncombustible.
Differences from the SRP:
- a. Certain fire dampers were located outside of fire barriers and the ductwork portions from the dampers to the barriers are protected with a 1-hour fire-rated material.
r
- J Ventilation ductwork passing through fire barriers is protected on both sides of the barrier with a 1-hour fire- a rated material and tutomatic detection instead of fire dampers installed at the barrier.
{ g J Ventilation ductwork passing through fire barriers is protected on the outsides of the barrier with a 1-hour fire-rated material and automatic detection and suppression instead of fire dampers.
Justification:
- a. Due to changes in boundaries of a portion of the plant's fire areas it became necessary to install fire dampers in completed ventilation systems. Extensive redesign and field i
modifications would have been required to locate the fire dampers inside the barrier.
The fire dampers are located as close to the fire barriers
, as possible and the ductwork from the fire dampers to the barrier is wrapped with a 1-hour fire-rated material. Fire wrap is also installed on the ductwork beyond the fire damper to the first support if required to ensure the ductwork's integrity.
l The fire severity in these areas is less than 1 hour on both sides of the barrier or automatic suppression and detection has been provided.
I L j,, y,, ou of Mu H<nc dae}r ln Fure Aver. of a.
3 1,,u,.- epshled paw e& sed.t 1.acks ego ve. m f. <_, ba rr r, ss-4, e uppe, Ja ,p, ie Zou His p,Nevlar ins /n, A .L inca. poem,,. of LefuerL w,'ll nd be urated. wVL n 4 < urne Maferia.[
Amendment 14 9.5A-124 February 1987 9
, . - - . - - . - - , - - _-_-,--,.. -,n.- ,- , , - - , _ , , - -
BUPS-2 FSAR The fire dampers are used as fire barriers between:
Opposite Side Located in 3
- 1) PA-3 (less than I hr) and PA-5 (less than I hr)
- 2) PA-4 (less than I hr) and PA (less than 1 hr)
- 3) SB-3 (less than 2 hr and SB-4 (less than 1 hr) with suppresion)
- 4) SB-4 (less than 1 hr) and SB-5 (less than 1 hr)
, 5) PT-1 (less than 1 hr) and SG-15 (less than 1 hr) c, q@ Due to plant layout the ventilation ductwork for the battery room exhaust system was required to pass through other fire areas (SB-1, SB-2, SB-4) not serviced by this system. In order to ensure the system availability in the event of a fire in an area not using this system, the ductwork was protected.with a 1-hour fire-rated material and fire dampers were not installed in the fire barriers. The fire severity in these areas (SB-1, SB-2, SB-4) is less than 1 hour and automatic general area fire detection with local and control room alarms has been provided.
- d. -*@ Due to plant layout the ventilation ductwork for the emergency switchgear ventilation and the battery room exhaust system were required to be installed in other fire
{ areas (CV-1, CV-3, SB-3) not serviced by this equipment. In order to ensure the system availability in the event of a fire in an area not using these systems, the ductwork was protected with a 1-hour fire-rated material and fire dampers were (CV-1, notCV-2, installed in the fire barriers. These fire areas and CV-3) are provided with automatic suppression and detection with local and control room alarms.
- b. Dw. Jo Re(A ideeferws, Are. wy moderi4 cann.} L<
placaA e JJ siAs af Au .z-iner. for+/en et L daduo, L.
Co d us4ifis loadiq W#i, sB (4-E. hour) 4 /est 4f m 4L yx/ Q of L /cww d y e whiel is /ecaded In /-ls- be ryle c. AJJikJQ A*s area- is provik A uoA QlAkDY5 htC-l$en Web loCA$ & Cm-{rk YCom Ya rms, 1
l l
Amendment 14 '9.5A-125 February 1987 1
l l
01/29/87 16:34 3t1 BUILD:NG 20~ f NO.010 001 -
Cerosite Meteriale Department /SM 3M Center 8t. Paul- Minnesote 551441000 etaass'tuo = l 2W \
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January)29,1987 ^:
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,.-n ,- A T31 INITIAL. g ;
Mr. F. J. (Jack) DeTsuple Beaver Valley Power Station II Stone & Webster Engineering Ca pany Pest Office Box 186 shippirgport, k nnsylvania. 15077-0186
Dear Jack,
Justification for the layer and thickness requirements when fire protecting heating ventilation and air conditioning (HVAC) ducts-with 3M Interam* E-50 Series mat can be found in several places:
'IVin City Testing Corporation Final Report 4414186-969 -
September,1986 "Walification Fire Tests of the 3M Interam' D-50 Series Fire Protection Mat for 1-Hour Rated Electrical Raceways" Ch page 7 of this-report it-is shown that a very lightly loaded cable' tray had.aimaximtsu cable tenperature of 343'F, an
_,_ .. . average cable tesperaturetof 294*F (typographical error in
-C me shounds204*JJvardia, minimum cable tamperature of. m - .
W' -
c-
, c3%j4.w@F%wAMtaigeratqwyeyafher
- Cm2 one, with onellayer"of hour-on;a (noninal.
Interam*:.e-54W. cable tray
~.4" :- c
; ??.Mgr Tlapre.oE5InterenCE-53A-(nani~nal .3" thick)'.
~-
. . . r y.A - qualification test with representatives from I- & Me6 ster, Twin ~ City Testing, and 3M. Our with'several hundred fire tests over the past years has invariably shown that larger objects with n W thermal mass (e.g. large HVAC ducts) heat up more slowly.
3M Interam" E-50 Series Fire Protection Mat Installation Booklet, Issue #5500-004, dated September 30, 1986 Section III.G. on page 5500@-7 of this booklet states that using two layers of Interam" E-54A (ncminal .8" total thickness) would be a conservative approach to fire protecting HVAC ducts. This very conservative approach was mentioned as a possibility to insuru that air and objects within the HVAC would not exceed 325'F maxinum temperature. When no critical electrical cables lay within the ductwork, the 325'F
I OL 29 8" N:35 31 EU:LD:tG 207g C.0:0 00 Stone & Webster January 29, 1987 Phge 2 requirement seems very conservative. General structural steel and supports fire protection requirements are to keep the maxinum tanperature below 1200'F and the average teqperature below 1000*P.
Coincidentally, M Fire Test #87-14 was just run on January 28, 1987 which indicated a cold side maximum tenperature on 18 gauge galvanized sheet metal of 283'F after one hour. This sheet metal was fire protected with one layer of E-54A and one layer of E-53A secured with 1/2" wide stainless steel banding at 8" spacing. Preliminary results are attached.
I hope this information is useful to you, sincerely, Randall G. Koza senior Fire Protection Engineer 612/733-4554 RGKamz Encl.
01.29 8~ M:25 2t1 9J:LD:tG 20~ - NO.010 002 3M FIRE TEST INFORMATION FIRE TEST NUMBER: 7-/4 _
FIM EST ME: / - 7O ~ h 1 FIRE TEST CBJECTIVE: Tis R'7ftsua ti 3 hsELaj$ D / M 7tia(OM oa MmL C u n n.e at mwnern unrw 2. <_.A vaa. a .
e-su na 1. wnme. a a- s1 A : n cas m a c,se 7mnw 1 7-Mt Isthamn nant w it.t L.A nadL Rn utam rb 6'%+-u.in im Fat +s i A ru Ttt & ditAWa A oits eiv 81.si r+ = b _ )tAIc %
Jnw$ yo :G O C H A M M JM iMM S kAlb daMMS197 .GnhiET=
mTE OF ReoOEST i-2.8 -87 --
FURNACE 'IO BE USED: 3(.-06, fob bM A4l b d. A 4 E TYPE OF FIRE TEST: b " //T REQUESHD LENGIM OF FIRE TEST: ~70 M /NU7Tf5 REQUESTED LENGDI OF WATER HOSE SUEAM TEST: hlCMC kdOO #
ARE PHOIOGRAPHS REQUIRED?
[ ] No N Yes; prints / M Partial " [ ] Conplete
[ ] Yes; slides [ ] Partial [ ] Complete
[ ] Yest video tape ( ) Partial [ ] Conglete TAs hosea-wt
!g 4,8C"Tr%OY,y 2. A rs FA r 7e ARE WEIGfrS OF 'IEE FIRE PROTECTION MATERIAL 5 REQUIRED 7
[ ] No
() Yes; 4" x 6" sangles CMlI Yes; individual pieces v
() Yes; conpleted system i
ARE SIZES OF THE FIRE PROTECTION MATERIALS REQUIRED?
! ] No
><3 Yes IS CIRCUIT CONTINUITY TESTING REQUIRED 7 No Y[ ] Yes Page 1 of 10
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v raa ww -ums n e O U29 87 16:38 2t1 EU:LD:tG 20t t10.010 005 0
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' ' ,() 103 1710*F 107 264'F 117 337'F .. l 104 1696*F 109 271'F 119 351'P 110 275'F 120 350.'F '
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! 102 1732'F 106 2DO'F 116 350*F '
[ () 103 104 1717'F 1765'P 107 109 267'F 117 341*F l 275'P 119 332'F i
110 281'F 120 352'F
() 111 266'F 121 343'F 112 253'F 122 341'F '
113 270'F 123 375'F
() ......
114 261'F 124 395'F 1721'F 269'F 361'F O
60 Minutes Furnace: 1709 E119: t/co
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() 103 104 1706*F 107 269'F 117 344'F 1692'F 109 275'F 119 355'F 110 283*F 120 356'F
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BUPS-2 FSAR i
i
SUBJECT:
Modified Fire Doors 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.")
j 7he rollo'ng she/ Ort. deet Safsm N N *, L Differences from the SRP: g,.g;
' (.ro te )
y 4 gA gg g gy;/g/
- a. Fire door assemblies have been modified from their tested configuration by the addition of security hardware and alarm equipment as required by NRC regulation.
w # e. Safeguardt Sw'IAm,t i b. Rolling steel fire doors have had the lower jam modified from the tested configuratio[n to allow for the installation
' Q and removal of equipment, &r the dood is not fire-rated.
__SI i c. Special purpose-type door assembliesC(for example, oversized W f oors. pressure-resistant doorTN_ (containment access doors / hatches) ed water-tight doors]) are not UL rated.
Justifications:
t
- 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 ,
j .bscr/ 4 video monitors and the alarm function in the event the door is left open, which would alert personnel of an abnormal
) (pg,9,g.my) condition in these areas.
! b. The rolling steel doors in the north and south safeguards l areas are not used to separate adjacent fire areas but are i
' used to separate the stairwell within a fire area from the l remainder of the area. Since the safeguards areas are normally unoccupied and the fire severity is less than 1/2 i
l hour, this arrangement is acceptable.
! The rollinghteelJoorbetweentheturbinebuilding(TB-1) l and thersourn n"i e= waansuildina]EsoSafin the railway
' bay, is not a fire-rated door because the door was purchased and installed as an exterior door to the turbine building 4
before the 505B was envisioned. When the 505B was added, the railway bay was separated from the remainder of the SOSB i
i Amendment 14 9.5A-126 February 1987 I
t
BVPS-2 FSAR by a 3-hour fire-rated barrier. Since the rolling steel door has sprinklers on both sides, a fire in the immediate area of the door would not affect safe shutdown, and there are minimal combustibles in the area of the door, this arrangement is acceptable.
con Mnme** f a ves bre-
- c. These[special purpose-type door assemblies are capable of providing adequate fire protection for Rheir resDeCtlV g urposes/ locations. HoweverJ no U -rated doors for these purposes e gurchased) available. etIt tne ume enese coors wer m ___
gre j C+h. a rer . 7%. Lerz ro aL- r pressars bevery Znseef h" (4,- Pap 9.su-i.u.)
Fk Aor- assentlias a fir < bamari s4avJ;>,g sakly -reIded areas will bear a Ul. la4d Aedi ,eck & rdag er K dC,or w.YI have carlitica.km q A.,Grep n ,%. vm /* e
{&/o'& okg & $ e4 Yal*hy-Gl4 / pn>daes & /W or &<. 4,,vr w,# .ucar,1 7 moti4Ju ihA & b '> s . Severo'hes hk. Ool1 of hr<. .s g resJ' b r- N a reas CyArdtA SJL hors.
Amendment 14 9.5A-127 February 1987
= _ _ - - .
BVPS-2 FSTA TABLE 1 Fire Doors With Security Modifications Areas Fire Severity Type of Fire Suppression Door No. Separated (hours) Primary 3ackup A-10-1 PA-3 <1/2 Portable ext. Hose rack
- St airwell <1/2 Portable ext. Hose rack l A-12-1 CT-1 <3 Total flood C02 Portable ext. ;
Hose rack i Stairwell <1/2 Portable ext. Hose rack 4
A-18-2 PA-3 <1/2 Portable ext. Hose rack l Stairwell <1/2 Portable ext. Hose rack A-30-1 Hallway <1/2 Portable ext. Hose rack Stairwell <1/2 Portable ext. Hose rack i
A-35-2 CV-1 <2 Total flood C02 Portable ext. .
Hose rack Hallway <1/2 Portable ext. Hose rack i A-35-6 WH-1 <1/2 Portable ext. Hose rack Automatic l sprinkler
, (Radwaste Area) i PA-3 <1/2 Portable ext. Hose rack A-35-7 PA-3 <1/2 Portable ext. Hose rack l
Stairwell <1/2 Portable ext. Hose rack A-45-1 58-3 <1/2 Total flood C02 Portable ext.
Hose rack
- Stairwell <1/2 Portable ext. Hose rack l
A-55-1 CV-3 <2 Total flood CO2 Portable ext.
Hose rack Stairwell <1/2 Portable ext. Hose rack
( A-55-3 PA-4 <1/2 Portable ext. Hose rack i St airwell <1/2 Portable ext. Hose rack I
A-60-1 SB-4 <1/2 Portable ext. Hose rack
. Stairwell <1/2 Portable ext. Hose rack l A-73-3 PA-5 <1/2 Hose rack Portable ext.
- St airwell <1/2 Portable ext. Hose rack i A-74-1 PA-5 <1/2 Hose rack Portable ext.
i WH-2 <1/2 Autonatic Portable ext.
l sprinkler Hose rack ,
9.5A-127 a J
. _ . _ _ , _ . . . _ _ . _ _ . _ . _ _ _ _ . , . . . _ _ _ . _ _ . _ . _ . _ _ _ . . . _ _ _ _. . _ _ _ . . . . _ _ . _. _ l
BVPS-2 FSAR TABLE 1 (Cont.)
Areas Fire Severity Type of Fire Suppression Door No. Separated (hours) Primary Backup 30-1 SB-1 <1 Portable ext. Hose rack Stairwell <1/2 Portable ext. Hose rack SB-30-2 SB-1 <1 Portable ext. Hose rack SB-6 <1/2 Portable ext. Hose rack SB-30 SB-1 <1 Portable ext. Hose rack 58-7 <1/2 Portable ext. Hose rack SB-30-4 SB-2 <1 Portable ext. Hose rack SB-8 <1/2 Portable ext. Hose rack SB-30-5 SB-2 <1 Portable ext. Hose rack SB-9 <1/2 Portable ext. Hose rack SB-30-6 SB-2 <1 Portable ext. Hose rack Stairwell <1/2 Portable ext. Hose rack SB-45-1 SB-3 <1/2 Total flood CO2 Portable ext.
Hose rack Stairwell <1/2 Portable ext. Hose rack SB-45-2 SB-3 <1/2 Total flood CO2 Portable ext.
Hose rack Stairwell <1/2 Portable ext. Hose rack SB-45-3 SB-3 <1/2 Total flood C02 Portable ext.
Hose rack Stairwell <1/2 Portable ext. Hose rack SB-60-2 58-4 <1/2 Portable ext. Hose rack Stairwell <1/2 Portable ext. Hose rack i 58-80-1 58-5 <1/2 Hose rack Portable ext.
PA-5 <1/2 Hose rack Portable ext.
I
! F-35-1 FB-1 <1/2 Portable ext. Hose rack l Outside <1/2 Portable ext. Hose rack i
F-67-1 FB-1 <1/2 Portable ext. Hose rack PA-5 <1/2 Hose rack Portable ext.
i l CV-35-1 CV-1 <2 Total flood CO2 Portable ext.
Hose rack Hallway <1/2 Portable ext. Hose rack I 9.5A-127b l
l t
f' BVPS-2 FSAR TABLE 1 (Cont.)
Areas Fire Severity Type of Fire Suparession Door No. Separated (hours) Primary 3ackup CV-35-2 Stairwell <1/2 Portable ext. Hose rack Hallway <1/2 Portable ext. Hose rack CV-35-3 CV-1 <2 Total flood CO2 Portable ext.
Hose rack SB-1 <1 Portable ext. Hose rack CV-67-1 PA-5 <1/2 Hose rack Portable ext.
CV-5 --
Portable ext. Hose rack CV-73-1 CV-5 --
Portable ext. Hose rack RC-1 <1 Portable ext. Hose rack (Personnel hatch)
CV-80-1 SB-5 <1/2 Hose rack Portable ext.
Stairwell <1/2 Portable ext. Hose rack DG-32-2 DG-2 <3 Total Flood CO2 Portable ext.
Hose rack Outside 1/2 Portable ext. Hose rack DG-32-3 DG-1 <3 Total flood CO2 Portable ext.
Hose rack Outside <1/2 Portable ext. Hose rack DG-32-4 DG-1 <3 Total flood CO2 Portable ext.
Hose rack Outside <1/2 Portable ext. Hose rack W-22-1 WH-1 <1/2 Portable ext. Hose rack Autonatic sprinkler (Radwaste Area)
Stairwell <1/2 Portable ext. Hose rack W-35-1 WH-1 <1/2 Portable ext. Hose rack Autonatic sprinkler (Radwaste Area)
CP-1 <3 Portable ext. Hose rack W-35-2 WH-1 <1/2 Portable ext. Hose rack Autanatic sprinkler (Radwaste Area)
Stairwell <1/2 Portable ext. Hose rack 9.5A-127c
I BVPS-2 FSAR TABLE 1 (Cont.)
-Areas Fire Severity Type of Fire Sup)ression Door No. Separated (hours) Primary '
3ackup W-44-1 WH-1 <1/2 Portable ext. Hose rack Automatic sprinkler (Radwaste Area)
Stairwell <1/2 Portable ext. Hose rack S-35-68 CB-3 <1/2 Portable ext. Hose rack Stairwell <1/2 Portable ext. Hose rack C-35-4 CP-1 <3 Portable ext. Hose rack Stairwell <1/2 Portable ext. Hose rack C-74-7 CP-1 <3 Portable ext. Hose rack CP-10 <3 Autanatic Portable ext.
(Primary Chem, sprinkler Lab)
GW-35-1 Gaseous Waste <1/2 Portable ext.
Storage Vault Stairwell <1/2 Portable ext.
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! 9.5A-127d
(
BVPS-2 FSAR
SUBJECT:
New Fuel Area Item C.7.1: '
The Standard Review Plan states that automatic fire detection should alarm and annunciate in the control room and alarm locally.
' Difference from the SRP:
Automatic detection in the new fuel storage area is not required.
Justification:
The new fuel storage area is an enclosed cubicle within the fuel building, combustible loading in the area, and the building in general, is extremely low.j alo comousticles are stored in rne area w postulated fire in any area of the fuel building will not impact the ability to safely shut down the plant. Since the fuel building access is controlled, and the building is a low traffic area, potential for accumulation of transient combustibles is negligible.
Fire hose stations and portable extinguishers are provided.
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ALairlrakve con h o ls w ,11 h t 9/ n d e t 4 , L n. w
&d shmy a<a. svek #J L 4..e n.11 it locA.ed mL ce mLas h ue shmp in & a ver all 4 <. prel,ti,t/ed .
i Amendment 14 9.5A-162 February 1987
SUBJECT:
Fire Hydrant Spacing Item C.6.b(7):
The Standard Review Plan states that hydrants should be installed approximately every 250 ft. on the yard main systen.
Difference fran the SRP:
Fire Hydrant No. 16, located outside of the southwest corner of the Turbine Building, . is located 340 feet fran Fire Hydrant No.15 which is located outside of the South Office Shops Building.
Justification:
Fire Hydrant No.16 has been relocated due to field interferences. Sufficient lengths of hose have been providt:d in the associated hose cart houses to pro-vide coverage in the event of a fire. The specific hazards in the area are the Main Transfonner and the two Station Service Transfonners. These transfonners have been provided with autonatic deluge suppression systens.}}