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MONTHYEARML20059A6661993-12-21021 December 1993 Forwards Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) Project stage: RAI ML20140B9781997-03-25025 March 1997 Forwards Summary of Thermo-Lag Ampacity Derating Methodology in Response to RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Response to RAI ML20210T1971997-08-29029 August 1997 Forwards RAI Re Thermo-Lag Ampacity Derating Issues & Preliminary Review of Beaver Valley Fire Barrier Clad Cable Ampacity Evaluation Methods, Rept Project stage: RAI L-97-039, Provides Notification of Completion of Corrective Actions for Thermo-Lag 330-1 Fire Barrier Systems at BVPS,Unit2,as Requested in GL 92-08.Response to 970829 RAI Re Ampacity Derating Issues & Calculation DE&S-SR/EM01,also Encl1997-10-13013 October 1997 Provides Notification of Completion of Corrective Actions for Thermo-Lag 330-1 Fire Barrier Systems at BVPS,Unit2,as Requested in GL 92-08.Response to 970829 RAI Re Ampacity Derating Issues & Calculation DE&S-SR/EM01,also Encl Project stage: Other L-98-023, Informs That Util Received Results of Chemical Composition Analysis & Results Favorable Re Thermo-Lag 330-1 Fire Barrier Issues at Plant1998-02-11011 February 1998 Informs That Util Received Results of Chemical Composition Analysis & Results Favorable Re Thermo-Lag 330-1 Fire Barrier Issues at Plant Project stage: Other ML20217N1171998-04-0606 April 1998 Informs That Licensee Provided Info Requested in GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217.However,there Remains Open Issues Involving Ampacity Derating of Thermo-Lag 330-1 Fire Barriers Protecting Conduits Project stage: Other 1997-03-25
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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
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UZn7. /%.n October 13,1997 L 97 039 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Thermo-Lag 330-1 Fire Harrier Upgrades and l Resporse to Request for Additional Information Regarding Thermo Lag Related Ampacity Derating Issues at Heaver Valley Power Station, Unit No. 2 (TAC No, M85517)
As requested in Generic Letter 92-08, "Thenno-Lag 330-1 Fire Barriers,"
notification is being provided relative to the completion of corrective actions for the Thenno-Lag 330-1 fire banier systems at BVPS Unit 2. liardware modifications and engineering analyses to assess the Thermo-Lag 330-1 fire barrier systems at BVPS !
Unit 2 have been completed with the exception of receiving the results of the chemical composition analysis of the final Thermo-Lag samples. The upgraded Thenno-Lag fire barrier systems utilized at BVPS Unit 2 for the protection of post fire safe shutdown circuits on electrical conduit raceways, boxed enclosures and their associated supports provide the required fire resistance capability based on qualified, tested configurations.
Minor anomalies or differences with tested configurations were evaluated and justification provided in supporting engineering analysis. Attachment I provides a summary status of the Thenno-Lag fire barrier systems at BVPS Unit 2.
This submittal also forwards the Duquesne Light Company response to the Nuclear Regulatory Commission's request for additional infonnation dated August 29, 1997, regarding Thenno-Lag related ampacity derating issues at Beaver Valley Power Station, Unit No. 2. The attached enclosure (Auschment 2) provides the response to the NRC questions and a copy of the Duquesne Light Company calculation of the effect on cable ampacities in fire-wrapped conduits. In addition, a copy of Okonite Bulletin EHB 90 is provided as requested in the RAl. This completes the ampacity evaluation perfonned for Beaver Valley Power Station, Unit No. 2 associated with the Thermo Lag installati ns as requested in Generic Letter 92 08. i 9710220149 971013-PDR ADOCK 05000412 P PDR hfh
Beaver Valley Pcwer Stati:n, Unit No. 2 BVPS Unit 2 Thermo-Lag 330-1 Fire Barrier Upgrades and Response to NRC RAl: Thermo Lag Ampacity Derating issues Page 2 If you have any questions regarding this submittal, please contact Mr. J. Arias at (412) 393-5203.
Sincerely, Sushil C. Jain c: Mr. D. M. Kem, Sr. Resident inspector Mr.11. J. Miller, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager
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A'ITACilMENT 1 Status of Thermo-Lag 330-1 Fire Barrier Systems at HVPS Unit 2 Thenno Lag 330-1 fire banier systems are utilized at BVPS Unit 2 for fire protection of safe shutdown circuitt on electrical conduit raceways, boxed enclosures (electricaljunction boxes and pull boxes) and their associated supports. 3M Interam fire protection system was also utilized to protect portions of the conduit support system, flexible conduits and is used for protection of the cable trays. Thenno Lag is not used to protect cable trays at BVPS Unit 2 Based on the results ofindustry testing, the boxed enclosures utilizing Thenno Lag 3301 fire barrier systems cwdited for post-fire safe shutdown capability were either upgraded orjustified to meet the required 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire resistance capability. Engineering analyses were also perfonned to assess both the upgraded and non upgraded boxed enclosures. The upgrades were perfomied in two phases using industry testing to provide the basis for a 1-hour fire rated banier. These upgrades, utilizing additional Thenno-Lag trowel grade material and stress skin along the butted seams, were completed during the third quarter of 1996.
Duquesne Light Company has been actively pursuing a resolution to the Thenno-Lag fire barrier issues for BVPS Unit 2. As noted in our previous submittal dated February 14, 1997, a conservative decision was made at that time to upgrade an additional 900 feet oflarge size conduits (3" to 6" diameter) encapsulated with Thenno-Lag 330-1 fire banier systems which are credited for post-fire safe shutdown capability.
The larger size conduit raceways (3" to 6" in diameter) encapsulated with Thenno-Lag 330-1 fire banier systems were, at that time, in the process of being evaluated by comparison to industiy testing which had successfully qualified as a 1-hour fire rated assembly. One of the parameters previously credited in the engineering analyses based on a sampling ofinstalled Thenno-Lag was the installation method of pre buttering the joints with trowel grade material vs. post-buttering after the assembly is configured. In December of 1996, during the upgrade project for small size conduits, a 2" diameter conduit was discovered to be void of the trowel grade material along the seam of the pre-fonned half shell installation. Acceptable industiy testing on 3" diameter and larger sized conduits has been based on utilizing pre-buttered joints. Industiy testing of post-buttered joints on smaller sized conduits (two tests of 2" diameter conduits) had mixed results. The discovery that post-buttering was used on certain installations at DVPS Unit 2 had a direct impact on the acceptability of the engineering analysis efforts that were being developed for justification of the as-installed 3" to 6" diameter conduit configurations encapsulated in Thermo-Lag.
Approximately 400 feet of the smaller sized conduit (1%" and 2" diameter) encapsulated in Thermo-Lag 330-1 fire banier systems ciedited for post-fire safe shutdown were upgraded to meet the required 1-hour fire resistance capability. This was
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Attaciunent 1 Progress Sununary of Thenno Lag 330-1 Fire Barrier issues at BVPS Unit 2 accomplished by adding an additional 3/8" thick Thenno Lag pre-shaped half shells with I additional trowel grade and stress skin material on top of the original baseline existing Thenno Lag installation. The larger sized conduit (3" to 6" diameter) encapsulated in Thenno Lag 330-1 fire barrier systems were upgraded with a 3/8" (minimum) layer of Thenno-Lag trowel grade material, overlaid with stress skin material, which was added to the original baseline installation.
The Duquesne Light Company objective has been to ensure a 1-hour fire rated barrier utilizing Thenno-Lag 3301 fire barrier systems by bounding our installations at BVPS Unit 2 to a qualified, tested configuration. Minor anomalies or differences with tested configurations were evaluated and justification provided in supporting engineering analysis. Engineering analysis providingjustification of the Thenno-Lag installations at BVPS Unit 2 including ampacity derating evaluations have been completed. As noted in Generic Letter 92-08, all analyses associated with the Thenno Lag 330-1 fire barrier systems ul be retained for future NRC audits or inspections.
The results from final chemical composition testing, have not been received from the test agency. Compensatory measures (fire watches) will remain in piece until satisfactory results are received.
Page 2 of 2 e
NITACllMENT 2 IIVI'S UNIT 2 ItESI'ONSE TO TIIE NitC ltEQUEST I<Olt ADDITIONAL,INFoltMATION Dated 8/29/97 (TAC NO. M85517) l
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l.0 llACKGROUND This is the response to the NRC Request for Additional infonnation [Ref.1] regarding the heat transfer model used by Duquesne Light Company to calculate the ampaity derating factor at lleaver Valley Power Station Unit 2 (llVPS2)[Ref. 2). The NRC stairs request for additional information and Duquesne Light Company responses are provided in the paragraphs below
} following a briefintroduction of the revised methodology adopted by the Duquesne Light Company.
The subject calculation [Ref. 2) has been superseded in its entirety by a new calculation [Ref. 3) which follows the same basic heat transfer concept as the superseded calculation but employs a different set of heat transfer equations to calculate the pmtected cable ampacity and the corresponding ampacity derating factor ihr the fire protected raceways at 11VPS2. The essential features of the heat transfer model used in the new calculation are summarized below:
The heat transfer model is developed from basic heat transfer principles and correlations fbr conduction, convection, and radiation that can be found in popular heat transfer text books such as incropera [Ref. 8), Otisik [Ref. 9), and Iloiman [Ref.10]. Where uncertainties exist, effbrt has been made to bias the model toward calculating a higher thermal resistance so that the calculated ampacity is lower, and therefbre, a conservative ampacity derating factor is calculated. The heat transfer model has been verified by comparing its predictions against industry test data. In addition, sensitivity studies have been performed tojustify the assumptions and approximations used in applying the model to the raceways at IIVPS2. The heat transfer model has the following essential features:
- 1. The model treats a protected conduit in distinct regions starting with the cable conductors where the heat is generated and ending with the ambient where the heat is dissipated. The model has the ibilowing elements.
. Ileat generation rate in the conduit Ileat transfer from the cables to the conduit wall
. Ileat transfer in the air gap region between the conduit wall and the fire barrier
. Ileat transfer through the fire barrier wall Ileat transfer from the fire barrier to the surrounding
- 2. The conduit wall is not treated separately in the model for two reasons. First, the thermal resistance of the conduit wall is negligible due to the high thennal conductivity of the metal wall. Second, the thermal resistance of the region from the cable conductor to the conduit wall is back calculated using the IEEE/NEC [Refs. 4,5] baseline ampacity data which includes the thermal resistance of the conduit wall itself.
- 3. The wetted perimetsr approach followed in the original calculation [Ref. 2] and the equation Ibr the overall heat transte coefficient (U,. defined by Equation 4 in Ref. 2] are not used.
Response to the NRC RAIITAC NorUi7) Page 2 of 7
2.0 RESPONS13 TO Tile QUESTIONS 2.1 Ileat Trainfer Ratefrorn Ihe Cable Conductor to the Conduit \\'all and the Recornmended Options.
l With regard to the wetted perimeter approach and the equation Ibr the overall heat transfer coefficient (U, on page 3 of the calculation [Ref. 2] ) it should be noted that neither the wetted perimeter approach nor the equation for U, are used in the revised calculation.
The revised method calculates the cable ampacity without Thermo lag material from the cable conductor to the conduit wall using NiiC 1993. The ampacity is considered base line ampacity. The cable thermal resistance is calculated from cable conductor to conduit wall using baseline ampacity data. This thermal resistance accounts Ihr the resistance of the cable bundle in the conduit, the resistance of the air space between the cable bundle and the conduit wall, and the resistance of the conduit wall itself. The applicable equations are given below:
lleat generation rate in the conduit:
l q, = n,(n,,l'R) / C (1) where q, heat generation rate per unit length of the raceway, Blu/hr fl C unit conversion constant,0.2931 W hr/ Btu
/ conductor baseline current, Amps R conductor resistance per unit length, ohm /11 n,, number of conductors per cable n, number of cables in the conduit c subscript for cablu n subscript for conductor r subscript for raceway (i.e., conduit) lleat Transfer from the Cable Bundle to the Conduit Wall:
q, = U,(nd,)(1; - T,) (1) where U, overall heat transfer coellicient (conductor to conduit wall), Btu /hr-ft2 ,7 T,, conductor temperature, T T, conduit wall temperature, T d, conduit outside diameter,11 Response to the NRC RAI(TAC No 833I7) Page 3 of 7
lleat Dissipation from the Conduit Wall to the Ambient:
q, = t nd, )(h, .,,, + h,,,,s. ,,, )( T, - T,, ) (3) where h,., convective heat transfer coefficient from the conduit to the ambient, Btu /hr f1' *F h,,,,,, radiative heat transfer coefficient from the conduit to the ambient, Btu /hr-ft' *F T, ambient temperature, *F Equations 1,2, and 3 are solved for the overall heat transfer coefficient U, and the raceway surface temperature T,. Since the heat transfer coefficients h,.,, and h,,,,,, are temperature dependent, the solution is achieved by iteration.
A direct approach to estimate the cable geometry parameters and calculate a heat transfer coeflicient U, based on first principles is not followed due to its complexity and the uncertainties in the arrangement of the cables in the conduit, the contact area. and the contact heat transfer coefficient. A method that accounts for these details is described by Neher-hicGrath [Ref. I l], and is adopted by IEEE [Ref. 4] to develop ampacity tables for conduits with various cable sizes and cable fills. The conduit heat transfer model used for IWpS2 takes advantage of these published ampacity tables and back calculates an overall heat transfer coefficient U, from the cable conductor to the surface the conduit wall, The method of back calculation, while indirectly complying with the methodology described by Neher-hicGrath (Ref. I 1], also ensures consistency with the IEEE ampacity tables, i.e., in the absence of any fire barrier, the ampacity calculated by the method matches the IEEE ampacity value.
2.2.a Valklation Case and the Use of TUE Test Data The revised heat transfer model was validated against test data from TVA [Ref.13] and TUE test programs [Ref.12]. Two validation cases were used from the TUB test program: a 2 inch conduit with 3/4": nominal barrier thickness and a 5" conduit with 1/2' nominal barrier thickness. The barrier thicknesses used in the TVA validation problem are based on the actual measured values reported in the test report [Ref.13] Attachment A of the Themo-lag ampacity derating analysis [Ref. 3] compares the analytical .nodel versus test cases.
2.2.b Cable Fill Datafor Conduit 2CL6070D The cable fill for 2CL6070D consists of three 3/C 4AWO cables and one Triplex 250hiChi cable. The calculation for 2CL6070D in the revised calculation is based on these cables.
Respome to the NRC R.4I(TAC No 833I7) Page 4 of 7
2.3 Justification)or the Ampacity Loadsfor the Cables in the Conduits 2CL21JND and 2CL6070E The conduits 2CL213ND and 2CL6070E were analyzed using the heat transfer method described in Section 1.0 above. The results, based on the assumption that all of the cables in these conduits are loaded at their protected ampacity, indicated that some of the cables are overloaded beyond their rated ampacity. A supplemental calculation was performed for these raceways by considering the diversity of the tables installed in them.
Itaceways 2CL213ND Examination of the full load currents for the cables in conduit 2CL213ND has indicated that some cables are lightly loaded while the others are heavily loaded. When this diversity of loading is considered, and a heat balance for the entire set of cables in the raceway is performed, it was seen that the thermal conditions at the " required" current are mere favorable than the themial conditions at the " rated" current (i.e., "motected" ampacity).
This is demonstrated in Table 1 below where the total heat genued at the maximum required current is compared with the total heat at the protected ampacity. The total heat generated at the maximum required current is less than the total heat generated at the protected ampacity. Since the cable conductor temperature at the rated current conditions is 194 T, this implies that the ceble conductor temperature at the maximum current will be less than the cable conductor temperature at the protected ampacity (i.e.,194 T). It has, therefore, been concluded that the cables in raceway 2CL213ND have su0icient diversity so l
that overloading of the two cables (2SCANNLO25 and 2SCANNLO26) is compensated by the underloading of the remaining three cables. DLC has initiated condition report 971661 to evaluate the life expectancy for the cables listed in this paragraph.
Raceways 2CL6070E The situation with 2CL6070E is similar to the situation with 2CL213ND discussed above.
Ilowever, there are only three cables in this raceway with two of them heavily loaded. One of the heavily loaded cable (211VSAOL210) is used to power a heater and is normally not energized. This cable is energized automatically on high moisture content (70%) at the intake of Supplementary Leak Collection and Release System (SLCRS) fan and initiation of CIA signal. The low moisture signal is annunciated in the control room. A supplemental calculation was donc for raceway 2CL6070E with cable 211VSAOL210 deenergized. Under these conditions, the remaining heavily loaded cable (211VSAOL200) has approximately 2 percent ampacity margin, in addition to the 2 pere:nt ampacity margin, there is sunicient diversity to prevent overheating of this cable. This is demonstrated in Table I below where it is shown that the heat generated at the maximum required current is less than the heat generated at the protected ampacity. Okonite bulletin EllB 90 states that " operation at emergency overload temperature of 130C (266F) shall not exceed 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> in any twelve consecutive months nor more than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> during the life time of the cable". The heater is energized during Operation Surveillance Testing (OSTs) for approximately half hour per OST, twelve times a year. DLC system engineering records shows that the heater was automatically operated once when the moisture detector went out of calibration in 1995 and second time during calibration process the heater was energized by I & C Tech in 1997.
DLC has initiated a condition report CR 971662 to evaluate the cable life expectancy.
Respome to the NRC RAI(TAC No 855l') Page 5 of 7
Talite 1 Evaluation of Raceways 2CL213ND and 2CL6070E Ilused on llent Generation Rate (details are given in Reference 3)
Racew ay Ampacity Catile No. llaseline Protected Required lleat lleat Generated No. Detating Arnpacity Ampacity Ampacity Generated at Required r l' actor (Arnps) (Amps) (Amps) at Protected Ampacity Ampacity (litu'br ft)
(lituhr ft) 2CL213ND 15.79 2LAl'NNL010 65.0 54.8 29.8 4.5 1.3 2SCANNLOl6 65.0 54 8 8.3 4.5 0.1 2SCANNL017 65.0 54 8 9.8 4.5 0.1 2SCANNLO25 37.5 31.6 44.6 3.8 7.5 2SCANNLO26 37.5 31.6 $ 1.5 38 10.0
'I otal lleat Generated 20.9 19.0 2CL6070L 26 0'e 2LilSAOL245 253 6 187.7 90.1 21.4 4.9 2ilVSAOL200 307.2 227.3 223.3 23.0 22.1 2ilVSAOl.210 0.0 0.0 0.0 00 0.0 Iotal lleat Generated 44.3 27.1 Respome to the NRC RAI(TAC Nos5517) Page 6 of 7
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3,0 11EFEllENCES
- 1. Enclosure I to the letter from D. S. lirinkman (Omce of Nuclear Reactor Regulation) to J.
- 11. Cross (Duquesne 1.ight Company) dated August 29,1997.
Subject:
Requestfor ildditionalInformation (R.II) Regarding 1hermo Lag Related Ampacity Derating issues -
Beaver l' alley Power Station. Unit No. 2 (BI'PS *J (TAC NOS. AINS$17).
J. Attachment I to the 1.etter from Sushil C. Jain (Duquesne Light Company) to U. S. Nuclear Regulatory Commission dated Alarch 25,1997.
Subject:
"# caver l' alley Powcr Station.
Unit 2 Docket No. 50-.ll2, License No. NPF-73. Response to Requestfor information Regarding Ampacity Derating ofCables Enclosedin 7hermo-Lag 330-1 Fire Harricts. "
- 3. Beaser Valley Power Station Unit 2 Calculation Titled "Ampacity Derating Factors offire.
Protected Cables," Calculation No. DE&S SR/Eh101, Rev.1, October,1997. DE C analysis 10080 l!-138 rev. 2 addenda A2.
- 4. IEEE/lPCEA Standard S-135/P-46-426, Powcr Cab /c Ampacities: l'olume I-Copper Conductors and l'olume II Aluminum Conductors, I984.
- 5. Early, hi. W. et al., National Electric Code //andbook, National Fire Protection Association, 1993.
- 6. ICEA Standard Publication, Ampacities of Cables in Open top Cable Trays,ICl!A P 54-440 (Third Edition), NEh1A WC 51-1986.
- 7. IEEE P848, Draft IEEE Standard titled," Procedure for The Determination of The Ampacity Derating of Fire Protected Cables," Draft 16 January 1,1995.
- 8. Incropera, F. P. and Dewitt, D. P., Introduction to // cal Transkr, John Wiley & Sons,1990.
- 9. Ozisik, hl. N., Baalc // cat Tran3fer, hicGraw llill,1977.
- 10. Iloiman, J. P., Heat Transfer, hicGraw 11i11,1963.
I1. Neher, J.11. and hi 11. hicGrath, The Calculation of The Temperature Rise and Load Capability of cable Systems, IEEE Transactions, Vol. 76, October 1957, pp: 752 773.
- 12. Omega Point Laboratories Report Titled,"Ampacity Derating of Cables Enclosed in l Conduits with Thermo Lag 330-1/7701 Upgrade Electrical Raceway Fire Barrier Systems (ERFDS)," Project Nos. 11960 97337 & 97338. Tennessee Valley Authority. August 21, 1995.
Omega Point Laboratories Report Titled,"Ampacity Derating of Fire Protected Cables,"
Project No. 12340-94583,95165-95168,95246, TU Electric, hlarch 19,1993.
Response to the NRC RAI(TAC No 853 t 7) Page 7 of 7
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