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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L4271990-09-0707 September 1990 Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications ML20059G0821990-09-0404 September 1990 Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8 ML20059F7551990-08-29029 August 1990 Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining ML20059F1501990-08-29029 August 1990 Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829 ML20028G8731990-08-29029 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71 ML20059D3761990-08-24024 August 1990 Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant ML20028G8881990-08-24024 August 1990 Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned 05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990 Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued ML20058P7651990-08-14014 August 1990 Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc ML20059E0571990-08-10010 August 1990 Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4)) ML20059E7631990-08-0101 August 1990 Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory ML20059B8141990-08-0101 August 1990 Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations ML20056A3471990-07-31031 July 1990 Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed ML20056A1841990-07-27027 July 1990 Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon ML20055H2581990-07-25025 July 1990 Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b) ML20055F7061990-07-0909 July 1990 Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage ML20055D3871990-07-0202 July 1990 Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results ML20058K5031990-06-29029 June 1990 Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria ML20044A3661990-06-21021 June 1990 Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue ML20043G6811990-06-14014 June 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown ML20043H9341990-06-14014 June 1990 Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04 ML20043G5981990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1 ML20043G6851990-06-12012 June 1990 Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp ML20043G7941990-06-12012 June 1990 Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl ML20043G8001990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d ML20043H0291990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program ML20043F5251990-06-0707 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl ML20043F1361990-06-0404 June 1990 Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002 ML20043B5971990-05-18018 May 1990 Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531 ML20043B0511990-05-15015 May 1990 Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario ML20043B1921990-05-11011 May 1990 Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14 ML20042G9761990-05-0808 May 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601 ML20042G8541990-05-0303 May 1990 Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests ML20042G9071990-05-0101 May 1990 Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b) ML20042F1381990-04-30030 April 1990 Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990 ML20042F0991990-04-20020 April 1990 Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program ML20012F5951990-04-10010 April 1990 Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990 ML20042E1471990-04-0404 April 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization ML20012F6021990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed ML20012E3091990-03-23023 March 1990 Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation ML20012E3451990-03-23023 March 1990 Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl ML20012D6491990-03-19019 March 1990 Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus ML20012E4091990-03-16016 March 1990 Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI ML20012D6181990-03-15015 March 1990 Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled ML20042D7401990-03-14014 March 1990 Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89. ML20012D5801990-03-13013 March 1990 Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index ML20012D6221990-03-13013 March 1990 Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events ML20012C1791990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled ML20012E0911990-03-0505 March 1990 Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2) ML20012B7051990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G 1990-09-07
[Table view] |
Text
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.-- a Wiley Power $tation
' $Nppingport. PA 4077-0004
, P, t Neer Group p M6m June 29, 1990 j U. S. Nuclear Regulatory Commission Attn: Document Control Desk l Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 and No. 2 )
BV-1 Docket No. 50-334, License No. DPR-66 '
BV-2 Docket No. 50-412, License No. NPF-73 SBO - Alternate AC load Management i
Gentlemen:
By letter dated March 30, 1990, we provided a supplemental-response to Station Blackout'(SBO) relative to the NUMARC guidance !
issued January 4, 1990. As part of our response, we requested a-90-day extension l to work with NUMARC and the other utilities '
affected by the guidance provided by your staff relative to the ;
- use of emergency diesel generators (EDG's) as an Alternate AC. ;
(AAC) source at multi-unit sites.
We. have evaluated our EDG load management methodology to 1
- ensure it meets the following criteria: i
- 1. Margin of safety shall not be degraded
- 2. Operator burden shall not be increased
- 3. The potential for common cause failure shall be minimized The margin of safety normally available during a safe shutdown non-DBA at the Non-Blacked Out (NBO) unit is not reduced as a result of the cross-tie. The normally available margin of safety-W is maintained by ensuring that: !
- 1. The steady state and dynamic loads imposed by operation of the necessary NBO and SBO unit AC systems does not exceed the capacity of the EDG being used-to supply AAC power.
- 2. The resulting configuration does not involve an unreviewed safety question as defined by 10 CFR 50.59.
g 9009060205 900629 0 PDR ADOCK 050003P4 i p FDC 1
\.
._ _ . _ . . ~ _ ___ _ _
s
- edvCr Valloy Pow 0r Station, Unit No3. 1&2 B
Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 SBO - Alternate AC Load Management Page 2 The actions necessary to provide power to the SBO unit will not increase the burden on the NBO unit's operators based on:
- 1. Operator actions necessary to ensure the process of supplying AAC power to the SBO unit is held to a minimum and does not endanger-the reliability and dependability of the NBO unit's Emergency AC (EAC) power supply, i
- 2. Manpower _ requirements to manage loads at the NBO unit can be
~
accomplished with the normally available staffing level.
- 3. Operators are not required to take actions that could damage or permanently disable components that are needed to respond to a normal loss of off-site power (non-DBA).
This criteria does not preclude operators from taking reasonable actions, as may be required and permitted under 10 CFR 50.54(x) and (y), should plant conditions depart from the assumptions and considerations defined for a station blackout.
NUMARC 87-00 Appendix B provides criteria for minimizing the risk of dependent failures. We have evaluated the proposed Alternate AC configuration against the guidance in NUMARC 87-00 Appendix B. An
' evaluation, demonstrating the criteria requirements are satisfied, is available on site for review.
Design features and design control measures will be implemented to ensure the EDG is capable of powering the full complement of loads that are normally required during a safe shutdown (non-dBA). Loads for cystems whose function would only be needed during a design basis .
accident are not considered since the NBO unit is assumed to maintain a normal (non-dBA) safe shutdown.
Protective features will be implemented to ensure that electrical faults in the SBO unit will not propagate to the NBO unit, and that the necessary static -and dynamic loading will not prevent the AAC power source from performing its intended safety function.
The UFSAR will be revised to reflect the final design loading scheme and protective measures for SBO. This revision will be submitted as part of the annual update following completion of the p modification. The UFSAR revision will identify the complete L complement of equipment needed to achieve and maintain a loss of L off-site ~ power safe shutdown as identified in Tables 1 and 2 of-the Enclosure. This revision will not affect in any way the components necessary for responding to a DBA. A safety review will be performed in accordance with the requirements of 10 CFR 50.59 as part of the UFSAR revision process.
i e
i
4 ' i
.. Beivcr Vcllcy Pow 3r Stttion, Unit Nos. 1 & 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 SBO - Alternate AC Load Management
,Page 3 Enclosure 1 "AAC Load Management Scheme for Beaver Valley" provides the methodology for achieving AAC for both Beaver Valley Unit 1 and Unit 2. The proposed load management scheme ensures the non-blacked out unit is brought to and maintained in a safe shutdown condition which meets the SBO regulatory requirements.
Differences in the assumptions for loss-of-offsite power loads from those currently specified in the UFSAR have been identified with justifications provided in the enclosure.
The- modifications and procedure changes associated with the AAC cross-tie will be completed. within two years after the notification provided by the Director, Office of Nuclear Reactor Regulation in accordance with 10CFR50. 63 (c) (3) . Since our Alternate AC (AAC) power source will involve cross-tieing busses between Units 1 and 2, installation and testing will require refueling outages at both units to fully implement the cross-tie.
capability. Therefore, the schedule for completion-may need to be extended, dependent on the NRC approval date and the scheduled l
refueling outage dates for both Unit 1 and 2. Presently, the l schedule for Unit 2's 3rd Refueling Outage is March 1992, and Unit l's 9th Refueling Outage is September, 1992.
If there are any questions on this matter, please contact my i office. ,
Very truly yours, L h I
- d. D. Sieber l ' ice President Nuclear Group '
l l
cc: Dr. T. Murley, Director of Office of NRR Mr. J. Beall, Sr. Resident Inspector Mr . 10. T. Martin,.NRC Region I Administrator l Mr. A. W. DeAgazlo, Project Manager Mr. R. Saunders (VEPCO)
NUMARC l
l l
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ENCLOSURE I i Page 1 l ALTERNATE AC LOAD MANAGEMENT SCHEME FOR BEAVER VALLEY Beaver Valley.is a two unit site utilizing an EAC source available from the non-blacked out unit (NBO) as an Alternate AC (AAC). The system meets the AAC criteria discussed in Appendix-B of NUMARC 87-00, and is capable of supplying the necessary safe shutdown loads of both units. Since the Unit 2 diesels are considerably larger, a substantial amount of excess AAC power is available to I cope with a blackout in Unit 1. For this reason, this discussion focuses on the more limiting scenario where the excess capacity from the Unit 1 diesel will be supplying AAC power for Unit 2.
As defined in Appendix A of NUMARC 87-00 document, Station Blackout (SBO) is the complete loss of AC electric power to the essential and nonessential switchgear buses in a nuclear power plant (i.e., loss of off-site electric power system concurrent with turbine trip and unavailability of the on-site emergency AC power system). SBO does not include the loss of available AC '
power to buses fed by station batteries through inverters or by Alternate AC power sources, nor does it assume a concurrent single failure or a design basis accident. At a multi-unit site with normally dedicated emergency AC power sources, station blackout is assumed to occur in only one unit.
The excess capacity that may be used as AAC power for.an adjacent
-blacked out unit is defined as the capacity, within the allowable EDG rating, for the expected SBO duration but above the power requirements for normal Loss of Offsite Power (LOOP) safe shutdown functions. Electrical loading necessary to support the normal LOOP safe shutdown functions may vary during the required SBO coping duration.
The maximum AC power requirements needed during a LOOP are shown in UFSAR ' Table 8.5-1 for Unit 1 and Table 8.3-3 for Unit 2. The Unit 1 proposed safe shutdown methodology during a LOOP concurrent with a station blackout in Unit 2, is generally consistent with the FSAR discussion. For the most part, all systems indicated in the FSAR table are expected to be available during a station blackout of the adjacent unit. However, some of the equipment listed in the table are not generally powered within the expected duration of the station blackout or do not have a safety function during a loss of off-site power. The NBO unit's safe shutdown capability is not degraded by employing this shutdown methodology. In addition, the flexibility normally available to the operators is not expected to be constrained.
The sections below describe the proposed load management scheme in detail highlighting an; differences from the load list shown in the FSAR. Three time periods are discussed: (i) the first hour, (ii) the following three hours, and (iii) an extended duration
.beyond four hours. As discussed in NUMARC 87-00 and Regulatory Guide- l'.155, AAC power only needs to be available during the second period (item (ii)).
ENCLOSURE I Page 2 i
ALTERNATE AC LOAD MANAGEMENT SCHEME FOR BEAVER VALLEY i The loss of off site power load management scheme is summarized in !
Table 1. This loading is sufficient to maintain the NBO unit in a ,
safe shutdown condition for an extended duration well beyond four j hours. Beyond the duration of the SBO, the NBO unit will retain. '
the capability to support its loss of off site power safe shutdown !
loads. The AAC power system is adeq.,'aly sized to carry the required shutdown loads for the requAred coping duration ,
maintaining voltage and frequency within limits consistent with the ect ablished industry standards. Also, the loading arrangement i will not degrade the performance of any shut down systems or components.
Loads Available During The First Hour l During the first hour of the event, all' applicable loads identified in the FSAR table may be powered. This includes all loads that are automatically loaded onto the diesel generators as indicated in Table 8.5-1 of the FSAR.
t Loads Available After One Hour and Before Four Hours I After the first. hour, a degree ci load management is necessary to ensure adequate Alternate AC power is available to the blacked out ,
unit. These loads fall into three categories: (a) loads that are not generally powered within the expected duration of the. station blackout, (b) loads that are not required to ensure safe shutdown capability, and (c) loads that do not have a safety function.
- a. Loads that are not aenerally oowered within the exoected duration of the station blackout i
It is important to note that some safe shutdown loads are only normally needed during the first hour of the transient, or l considerably after four hours. These loads include motor operated valves, and the spent fuel pool cooling system.
Power for motor operated valves, will only be needed during i
the first ten minutes to realign safety systems. Since these components are not normally energized after the f'.rst hour of the event, they do not need to be powered after the first hour, i
i The spent fuel pool cooling pumps will not need to be powered l until after the coping period for a loss of off site power.
l Thus, it is not necessary to consider this load during the four hour duration of a station blackout.
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1 ENCLOSURE I l Page 3 H f ALTERNATE AC LOAD MANAGEMENT SCHEME FOR BEAVER VALLEY 1
The Leak Collection exhaust fans, although automatically loaded on the EDG for a loss-of-offsite power event, are I primarily to prevent radioactive' leakage from the containment and contiguous areas following -a DBA. The system provides L ventilation to the- Aux FW-pump room which was analyzed for a loss of ventilation under SBO criteria. Therefore, this load is not needed for normal safe shutdown following a loss-of- <
g offsite power event with no concurrent failure or DBA type .(
l events.
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- b. Loads that are not reauired to ensure safe shutdown canability Several loads are not needed for normal safe shutdown following a loss of off site power. These include the L
containment air recirculation fans, and the containment instrument air compressors. The unavailability of' these systems during this period will not reduce the information available to the operators to monitor the safety related conditions of the plant, nor will it impair or damage the NBO unit in any way, b.1 Containment ventilation cooling water is not safety related at Beaver Valley. Thus, the containment recirculation fans would not serve their cooling function and would only add to the heat generation. This condition- has been ' analyzed and verified during plant operation. Containment temperatures have been shown to not- increase beyond 110*F during the first four hours of the event. This temperature is considerably below the EQ' operability limit of 135'F.
b.2 Similarly, cooling water for the containment instrument air -compressor is not safety related, and consequently is normally unavailable during a loss of off-site power.
For this reason, the compressor must be disabled since operation without cooling results in an electrical trip of the component. Existing plant procedures for coping with a LOOP event direct operators to disable the compressor for a loss of cooling water resulting from the loss of off-site power. This system is not required to ensure safe shutdown capability.
I LER 84-07 Loss of Containment Cooling
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ENCLOSURE I I I
Page 4
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ALTERNATE AC LOAD MANAGEMENT SCHEME FOR BEAVER VALLEY
- c. Loads that do not have a safety function The turbine generator bearing lube oil pump, and the turbine bearing oil lift pump are used during and after turbine coastdown (approximately thirty minutes). However, these are non-safety related loads and are not required for the safe shutdown of the plant. The turbine turning gear drive, which is used to prevent turbine shaft warpage, is also not required for safe shutdown. The turning gear.will not be available unless Emergency Diesel Generator No. 1 is op3 rating since power is provided from only one emergency potter train.
Loads Available After Four Hours The station blackout rule only requires Alternate AC power to be provided for the station's required coping duration. Thus, after '
L four hours, Unit i no longer needs to supply AAC power to Unit 2.
However, as discussed above, the proposed loading arrangement is !
sufficient to maintain the station in a safe condition for an extended duration beyond four hours.
EOP Develooment and Methodolocy Procedures (EOP's) will be developed to allow for discretionary
. loads- for operator flexibility of load management dependent on sufficient EDG capacity. The addition of a high-head charging.
pump to the blacked-out unit would be one such example.
Both- beaver Valley units are equipped with 100% capacity turbine driven AFW pumps. -Irrespective of the turbine driven AFW pump, sufficient design capability is available to power the motor-driven AFW pump at' the HBO unit during this event. (See Table 1). ,
Eggmary and Conclusion J.
The load management scheme discussed above ensures the NBO unit is brought to and maintained in a safe shutdown condition for an extended period well beyond four hours. No component is permanently disabled or in any way degraded. In fact, load management is needed to ensure long term operability of equipment. On this basis, we find that this arrangement meets the current SBO requirements.
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[ TABLE 1 Alternate AC Lond Management Scheme For Seaver YetLey
!. (Total Londs on Unit i EDC) i UNIT 1 UNIT 2
. COMPONENT LOADS (kW) LOADS (kW)
- NBC Unit 80 Unit Remarks 0 to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to- After 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to i hour 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 heure 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
[ Charging-Ni Need S a f e t.y 442.0 442.0' 442.0 *(477) l Infection Pumn River Water Pumn 338.0 338.0 338.0 (+) + Cross-tie RUS Stoes Generator AFW 302.0 302.0 302.0
'Puno Primary ~ Plant component- 221.0 221.0 221.0 j' Esolina Water Pumn
' Turbine Bearing Ott' 13.0 0.0 0.0 See section C Lift Puno Motor Onorated Vatves _
53.0 0.0 ,
0.0 , see section a EQorgency Diesel 28.0 28.0 28.0 l Auxillaries l Turbine. Generator 39.0 0.0 0.0 See section C l
Liarina Lube oft Pump Turbine-Turning Gear 39.0 0.0 39.0 grive _ _ ,
Pressurizer Nesters ** 0.0 216.0 216.0 ** One hour detav Boric Acid' Transfer Puen 13.0 13.0 13.0 ,
Boric Acid T a fi k Nesters 15.0 15.0 15.0 Battery Charmers 38.0 14.6 3 8 . 0 __ 3821__
Ecorgency Lighting 5.0 5.0 5.0
'Suontementat __
l Ecorgency Lighting 28.0 28.0 28.0 j sunotementet containment Air 283.0 0.0 0.0 See Section b.1 Recirculation Fans Control Room Air 48.0 48.0 48.0 Sucoly Fans control Roos Air Return 25.0 25.0 25.0 fans control Room AC 61.0 61.0 61.0 gamoressors t -Control Room AC 4.0 4.0 4.0 Condenser circulating Pumps Lock Cottection Exhaust 115.0 0 0 See section a
- j. Fans I' Safeguards-Area Sump 4.0 4.0 4.0 L Egan Ecorgency Swgr & 8.0 8.0 8.0 Battery Room Exhaust Fan Ecorgency Swgr & 13.0 13.0 13.0 sottery Room Supply Fan Fuel Poot Coottna Puno 2 0. 0_ _ 0.0 20.0 Sye section o
- Intermittent Lomd; Pressurfter heaters to be de-energized when starting discretionary load (cherging pump) et eV-2. To be proceduralty addressed.
t.
TAELE 1 (Cent.)
Alternate AC Loed Management Schsee For Beaver Vattey (Total Loeds on Unit 1 EDG)
UNIT 1' UNIT 2 COMPONENT. LOADS (kW) LOADS (kW) l ,
NB0 Unit 50 Unit temarks 0 to I hour to After 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to j 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> see '
Control Rod Cooting 81.0 81.0 81.0 56.0 Fan Miscettaneous Fans, 13.0 13.0 13.0 Damners. and Punos Miscettaneous Fans, 10.0 10.0 1 0 . .'
Despers_ and Punos Ll o e Neat Tracina 60.0 60.0 60.0 Ploe Meat-Tracina 60.0 60.0 60.0 Vital Bus ioads 50.0 50.0 50.0 N!scelteneous Neaters 62.0 62.0 62.0 Miscelteneous Neaters 12.0 12.0 12.0 Ecorgency AC 11.0 11.0 11.0 D i s t r i b u t ', o n Panels
'Ecorgency AC 22.0 22.0 22.0 Distribution Panets containment Instr. Air 17.0 0.0 0.0 See Coction b.2 Comoressor LLaguter Inverter 17.0 17.0 17.0 48 Volt Battery Charmer 5.0 5.0 5.0 Additional SB0 loads for B0 Unit Control Room MVAC 27.4 Fan-only Unit (BV-2)
Lead & Cooling System 49.0 Losses AC Dist. Transf.
AC Dist. Transf. 0.3 AC Dist. Transf. 3.1 AC Dist. Transf. 0.3 I AC Dist. Transf. 5.1 ;
Vital Bus Rect. 2-3 8.8 Vital Bus Reet. 2-1 14.0 l Bettery Room Enhaust 6.2 Fan l AC Distr. Infr 2.9 AC Distr. aufr 2.1 l ljTAL LOADS 2585.0 2222.0 2396 666.8* tincludes TOTAL LOADS ON Chg Pump)
UNIT 1 EDG 2585.0 2888.8 2396 j 1
1 NOTE: Olesel generator 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> capartty = 2950 kw.(Ref. UFSAR-1, Fig. 8.1-1
' Design capability does exist for powering the discretionary load j (charging pump) at the 5.0. Unit.
I l A single CRDM shroud fan is sufficient during the first four hours for upper-head cooling per E0Ps and engineering evaluation.
Reference EM No. 22241.
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- i TABLE 2 Alternate AC Loed Management Scheme For Besver Valtey l (Totat Loeds on Unit 2 EDG) l l
UNIT 2 UNIT 1 COMPONENT LOADS (kW) LOADS (kW) l NBC Unit 80 Unit temarks l 0 to I hour to After 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to l 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l Chorging*NI Need Safety 477.0 477.0 477.0 *(442) l
! Infection Puen
! Service Water Pumn 696.0 696.0 696.0
. Steam Generator AFW 320.0 320.0 320.0 Puen Primary Plant Component 316.0 316.0 316.0 Coottna Water Puen Leak Cotol. Fitter 150.0 150.0 150.0 Exch. Fans Ecore. Supr. Supply 50.4 50.4 50.4 Fans E30rg. Sver. Exch. 44.9 44.9 44.9 Fans pain st;am Fans 62.0 62.0 62.0 ,
cont. .
Rectrc. Fans 154.0 0 0 See section b.1 Lesk Syn. Elec. Wtr. 211.0 211.0 211.0 Press. Nesters 0.0 270.0 270.0 One Nour Detav CRON'throud Fan 56.0 56.0 56.0 81.0 See Note 1' Lood &'Clg. Sys. 49.0 49.0 49.0 l Losses (XFNR)
AC Dist. Transf. (E*S) 0.3 0.3 0.3 SWP Lube Water Strainer 0.5 0.5 0.5 l Intake suontv Fan 4.1 4.1 4.1 AC Dist. TRansf. (E.3) 3.1 3.1 '.1 l-Control Re. AC Unit 27.4 27.4 27.4 61.0 '
Refria. Cond. Unit 50.0 50.0 50.0 AC Dist. Transf. (E-9) 0.3 0.3 0.3 Elec. Heat Xfar. 2.1 2. 2.1 __
Motor Operated Vetves 110.6 0 0 (total)
Fuel Pool Coolina Pump 14.4 0 14.4 cent. Btdg. Air Exch 25.0 25.0 25.0 and Supotv Fan Chg. Pump Cub. 18.0 18.0 18.0 Exch. Fan AC Dist. Transf. (E-1) 5.1 5.1 5.1 NCC Cub.-Emch. Fan 2.8 2.8 2.8 DG Fuet Olt Xtr. Pumps 0.7 0.7 0.7 DG stdg. Supply Fan 33.0 33.0 33.0 (270A)
DG Crank. Lase 1.1 1.1 1.1 Vacuum Pump
TABLE 2 (Cont.)
Attornate AC Lond Nanagement Scheme For Beaver Valley (Total Loeds on Unit 2 EDG)
UNIT 2 UNIT 1 COMPONENT LOADS (kW) LOADS (kW)
Vital Bus Rect. 0.8 8.8 8.8 DE BLde. Supply Fan 30.0 30.0 30.0 (271A)
DG BLda. Exch. Fan 0.7 0.7 0.7 DG Pretube Puan 0.55 0.55 0.55 SG Area A/C Unit 16.5 16.5 16.5 Vital Bua tect. 2-1 14.0 14.0 14.0 CV & RC Area A/C Unit 18.4 18.4 18.4 Boric Acid Trana. Puen 13.16 13.16 13.16 Batterv Room Each. Fan 6.2 6.2 6.2 6.2 Recirc. Puso (25Ws*P25A) 1.0 1.0 1.0 AC Llat. Transf. (E-7) 2.9 2.9 2.9
.AC Olst. Transf. (E-11) 2.1 2.1 2.1 Aux FW Control Valves 1.05 1.05 1.05 ___
Atp. Ste. Dump Valvos (101A.B & C) 1.05 1.05 1.05 Battery Charmer 14.6 14.6 14.6 38.0 River Water Puen (Unit 1) 338.0 Cont. Ra.-Supply & 73.0 Emh. Fans (Unit 1)
E. Swar. & Battery Ra 21.0 Suontv & Euh. Fana. (Unit 1) _
(Inctudes TOTAL LOADS 3015.8 3006.8 3 0 2 1 .'2 1060.2* Chn. Puno)
TOTAL LOALS ON UNIT 2 EDG 3015.8 4067.0* 3021.2 NOTE: Diemet generator 160 hour0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> capacity = 4662 kw.(Ref. UFSAR-2, Section 8.
- Design capability does exist for powering the discretionary Lond (charging pump) at the 8.0. Unit.
' A single CADM shroud fan is sufficient during the first four hours for upper head cootIng per ECPs and engineering evatuation.
Reference EM No. 22241.