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MONTHYEARML20072H5481983-03-25025 March 1983 Forwards Response to 821210 Generic Ltr 82-28, Inadequate Core Cooling Instrumentation Sys, Consisting of Upgraded Subcooling Margin monitors,core-exit Thermocouples & Reactor Coolant Inventory Tracking Sys Info Project stage: Other ML20204G1181983-04-21021 April 1983 Forwards Supplemental Response to Generic Ltr 82-28, Inadequate Core Cooling Instrumentation Sys & NUREG-0737, Item II.F.2.W/one Oversize Drawing.Aperture Card Is Available in PDR Project stage: Supplement ML20080G9641983-09-13013 September 1983 Advises That 830325 Commitment to Install Reactor Vessel Level Indication Sys Hardware Met,Per Generic Ltr 82-28 & NUREG-0737,Item II.F.2 Project stage: Other ML20080E8631984-02-0303 February 1984 Responds to 831216 Request for Addl Info Re Proposed Inadequate Core Cooling (ICC) Instrumentation,Per TMI Item II.F.2.Meeting Scheduled for 840301 in Bethesda,Md to Discuss Technical Issues Re ICC Instrumentation Project stage: Meeting ML20214P5671986-11-12012 November 1986 Requests Listed Addl Info Re Inadequate Core Cooling Instrumentation Design Changes,Including Projected Implementation Date for Changes,Including Tech Specs.Info Requested within 45 Days of Ltr Receipt Project stage: Other ML20207P9141987-01-12012 January 1987 Forwards Update to 860124 Submittal Re Inadequate Core Cooling Instrumentation Sys,Per NRC 861112 Request & Brief Comparison of Unit 1 & 2 Sys Project stage: Other ML20205F1411987-03-18018 March 1987 Forwards Addl Info to Clarify Existing Inadequate Core Cooling Instrumentation & Proposed Upgrade Described in Util 840426 & 870112 Submittals,Per 870303 & 11 Telcons W/Nrc Project stage: Other 1984-02-03
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L4271990-09-0707 September 1990 Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications ML20059G0821990-09-0404 September 1990 Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8 ML20059F7551990-08-29029 August 1990 Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining ML20059F1501990-08-29029 August 1990 Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829 ML20028G8731990-08-29029 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71 ML20059D3761990-08-24024 August 1990 Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant ML20028G8881990-08-24024 August 1990 Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned 05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990 Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued ML20058P7651990-08-14014 August 1990 Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc ML20059E0571990-08-10010 August 1990 Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4)) ML20059E7631990-08-0101 August 1990 Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory ML20059B8141990-08-0101 August 1990 Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations ML20056A3471990-07-31031 July 1990 Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed ML20056A1841990-07-27027 July 1990 Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon ML20055H2581990-07-25025 July 1990 Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b) ML20055F7061990-07-0909 July 1990 Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage ML20055D3871990-07-0202 July 1990 Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results ML20058K5031990-06-29029 June 1990 Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria ML20044A3661990-06-21021 June 1990 Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue ML20043G6811990-06-14014 June 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown ML20043H9341990-06-14014 June 1990 Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04 ML20043G5981990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1 ML20043G6851990-06-12012 June 1990 Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp ML20043G7941990-06-12012 June 1990 Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl ML20043G8001990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d ML20043H0291990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program ML20043F5251990-06-0707 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl ML20043F1361990-06-0404 June 1990 Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002 ML20043B5971990-05-18018 May 1990 Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531 ML20043B0511990-05-15015 May 1990 Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario ML20043B1921990-05-11011 May 1990 Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14 ML20042G9761990-05-0808 May 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601 ML20042G8541990-05-0303 May 1990 Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests ML20042G9071990-05-0101 May 1990 Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b) ML20042F1381990-04-30030 April 1990 Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990 ML20042F0991990-04-20020 April 1990 Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program ML20012F5951990-04-10010 April 1990 Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990 ML20042E1471990-04-0404 April 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization ML20012F6021990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed ML20012E3091990-03-23023 March 1990 Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation ML20012E3451990-03-23023 March 1990 Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl ML20012D6491990-03-19019 March 1990 Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus ML20012E4091990-03-16016 March 1990 Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI ML20012D6181990-03-15015 March 1990 Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled ML20042D7401990-03-14014 March 1990 Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89. ML20012D5801990-03-13013 March 1990 Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index ML20012D6221990-03-13013 March 1990 Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events ML20012C1791990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled ML20012E0911990-03-0505 March 1990 Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2) ML20012B7051990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G 1990-09-07
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?Af Telephone (412) 393-6000 Nuclear Division P.O. Box 4 Shippingport PA 15077-0004 April 21, 1983 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission l Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Generic Letter No. 82-28; Supplemental Response on ICC Instrumentation System Centlemen:
This submittai is being provided to complete our response to Generic Letter 82-28, Inadequate Core Cooling Instrumentation System, dated December 10, 1982. Included is an Attachment which provides informa-tion relative to items 4 and 5, II.F.2 Attachme^t 1 and Appendix B (of UUREG-0737) as included in Generic Letter 82-28.
Since our initial response to NUREC-0737, dated December 31, 1980, we have been reviewing our existing core exit thermocouples (CETC's) agains t the design and qualification criteria contained in NUREG-0737.
The purpose for this review was to determine if the CETCs could be up-graded to NUREG-0737 criteria, what would be involved in the upgrade and the benefit gained through the upgrade with respect to providing the plant operators an absolute means by which they could identify the approach to inadequate core cooling. We have concluded that the up-grading of CETCs will not result in sufficient improvements to plant safety to justify the costs associated with pursuing a goal for qualifica-tion which has not been proven to be attainable.
Beaver Valley, Unit 1, uses the Westinghouse supplied CETC system.
This system includes chromel-alumel thermocouples in stainless steel sheaths which extend from the core exit region to penetrations in the reactor vessel head. At these penetrations, thermocouple extension wires connect with the CETCs and go to a Reference Junction Box. The reference junctions permit use of conventional copper wiring from the junction boxes through the containment penetrations to the thermocouple readout devices. Refer to Figure 5 for a simplified sketch of this system. The i original installation requirements for these CETCs did not include environ-mental or seismic qualification or the separation requirements as specified for lE systems. The results of our review has concluded that this system 0305020359 830421
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,, Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Generic Letter No. 82-28; Supplemental Response j on ICC Instrumentation System '
Page 2 l
will not be capable of providing the operator absolute information regarding core exit temperatures and may still not meet the complete design criteria of NUREG-0737 following extensive ef forts to upgrade this system. The most useful information the operator could obtain f rom this system is trending information and it has been determined that the CETCs did provide trending information at TMI.
Our containment design and equipment layout makes the task of attempting to upgrade this system extremely dif ficult. Extensive cable and conduit routing and cabinet replacement or relocation would be required to satisfy all lE and separation criteria. Even with these modifications, separation criteria cannot be met in the area of the reactor vessel head. We estimate that costs in excess of 4 million dollars could be expected if we were to pursue this upgrade and the results would j still produce an indication that the operator could not take as absolute, i From a technical perspective, the small EMF produced by the CETCs can still be significantly influenced by changing containment temperatures affecting the isothermal assembly in the reference junction box or from electromag-netic interference. While the Reference Junction Boxes sre temperature compensated, accuracy of the CETC would deviate during LOCA induced envir-onmental conditions within containment. Additionally, when considering accuracy over an extended range, the non-linearities of the transducers, wiring, pre-processing electronics stability and scale compression all contribute to degrade accuracy. We have concluded that even with a system for which an upgrade has been attempted, any signal interference will result in degrading loop accuracy and resolution, and that the best we can expect to obtain is trending information.
From an operating perspective, the absence of environmental quali-fications on the incore thermocouples can be evaluated appropriately by determining what potential non-conservative actions could be taken by the operator if anomalous indications were being given by these devices during a safeguards system actuation. The BVPS Unit I design does not provide for remote throttling of high head safety injection flow during the injection phase below the capacity of a single 100% high bead charging pump.
In order to satisfy the procedural requirements for termination of safety injection, the following conditions must be satisified:
- normal indications for the containment sump level and sump temp-e ra tu re normal pressure and radiation levels in containment
- normal radiation levels in the steam generator blowdown and air ejector effluent reactor coolant pressure greater than 2000 psig and increasing
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.. Bezver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66
- ' Generic Letter No. 82-28; Supplemental Response on ICC Instrumentation System Page 3 pressurizer level greater than 22%
- 50*F subcooling l
350 gpm of auxiliary feed flow into the steam generators, or narrow range level in nt least one steam generator 2 20%
Noting that the only time during the termination that the thermo- I couples could be used is in determining the subcooling margin. If all other termination criteria are met, then the wide range hot leg temp- ,
erature indications would provide the equivalent information and also indicate the onset of an inadequate core cooling (ICC) condition as they did at TMI at two hours into the event.
If the readings from the thermocouples were inconsistent due to any hypothetical accident induced fault, then it would not be possible to meet all safety injection termination criteria and the operator would be forced to maintain full safety injection flow to the coolant system.
As detailed in the Kemeny Report, (Reference 2) "if the safety injection flow was not throttled, a stable condition would have been achieved with no damage to the core", therefore, we have concluded that there is no substantial basis to justify upgrading the incore thermocouples at BVPS Unit 1. The fact that a particular instrument responds to an event should not be the sole consideration for requiring qualification of the device for the full LOCA envelope of operating conditions. As is the case of
, the TMI incore thermocouples, (Reference 1), we would expect that the majority of our 51 thermocouples would survive a similar event. It is i also evident (Reference 1) that the hot leg temperature indication properly responded to the onset of the ICC condition and provided equivalent infor-mation when the indicators went off scale at 700*F. Licensed operators at Beaver Valley have been trained on the expected response of these and other instruments during requalification training, i Since termination of safety injection is not keyed strictly to performance of the thermocouples and core damage would be precluded by maintaining full high head injection in the absence of meeting the subcooling criteria, we do not believe that upgrading the thermocouples to meet the full regulatory requirements of NUREG-0737 and Regulatory Guide 1.97 is justified.
l If you have any questions, please contact myself or members of my staff.
Very truly yours, J
! J. J. Carey Vice President, Nuclear
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Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Generic Letter No. 82-28; Suppleuental Response on ICC Instrumentation System Page 4
References:
(1) NSAC 80-1, March 1980, Analysis of Three Mile Island Unit 2 Accident (2) Report of the President's Commission on the Accident at Three Mile Island, October 1979 Attachment cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555
e COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNT ( OF BEAVER )
0 this d/ day of 14 6 ,
/ f M , before me, L /> 7//. J/fie/tt , a Notary /Public in and for said Commonwealth and County, personally appeared J. J. Carey, who being duly sworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) tre statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
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n' ATTACHMENT Supplemental Response to Generic Letter 82-28 Inadequate Core Cooling Instrumentation System dated December 10, 1982 Checklist for Plant Specific Review of Inadequate Core Cooling (ICC) Instrumentat1on System For: Beaver Valley Power Station, Unit No. 1 Docket No. 50334 Operated by: Duquesne Light Company Reference Devia tions Schedule
- 4. Prov$de a table or description covering the evaluation of con-formance with NUREG-0737: II.F.2, Attachment 1, and Appendix B (to be reviewed on a plant spec-ific basis)
Response
This evaluation of conformance is provided in the attached TABLES.
- 5. Describe computer, software and display functions assoc 1-ated with ICC monitoring in the plant See Below No Complete
Response
The following is a description of the plant computer and subcooling margin monitor microcomputer which serve as components of the ICC Instrumentation System.
DESCRIPTION OF MAIN COMPUTER The Beaver Valley Power Station Main computer is used for the moni-toring of primary and secondary plant parameters. The computer obtains data by scanning analog and digital sensors. It then logs data, performs data analog and digital trending, performs alarm limit supervision and annunciates off-normal conditions. Also included are reactor control and protection system monitoring, secondary plant performance calculations, and core physics monitoring. The power supply for this system is provided via the emergency busses.
.. Attachment Generic Letter 82-28 Supplemental Response Page 2
SUMMARY
DESCRIPTION !
The basic equipment, or hardware, of the computer system includes a central processing unit (CPU), an input / output unit, a rapid access disc, an operator's console with output typewriters (OPCON), and a programmer's console.
The OPCON provides the communication link between the station operating personnel and the computer. It is through this console that data may be entered or requested, programs initiated and of f-normal situations annunciated. The console is the only piece of the computer system that is located in the control room. Under normal operating conditions, the OPCON is the only part of the computer with which the station operator will be concerned.
The remainder of the computer system is located in the computer room adjacent to the main control room. The programmer's console consists of a paper tape punch, paper tape reader, and an IBM Model 735 input / output typewriter.
The central processing unit is housed in two cabinets and is the primary controlling element for most system functions. The CPU addresses core memory, acquires and stores information, sequences and controls instruction execution, and controls the exchange of information between core menory and other parts of the system.
Input / output cabinets are also located in the computer room. Each cabi-net houses the various panels needed for communication between the CPU and the monitored processes. Included in the cabinets are analog to digital converters, reference junction boxes, a demultiplexer, and term-inal strips for incoming process signals.
Two (2) six-digit visual display units are provided on the operator's panel. Any analog input or addressable value may be displayed b1 numer-ical engineering units on this display. One such unit displays the input identification, the other displays the value. The program updates the display windows every four seconds.
- INCORE T/C FMP l
l This function permits the operator to obtain any of 53 possible incore thermocouple maps on any of five possible output device combinations.
The 53 incore T/C maps, with their corresponding VALUE 1, (Map Code) and VALUE 3 (Form Code) pushbuttons entries, are:
MAP VALUE 1 VALUE 3 Long-form 1-minute-old map 0 0 Short-form 1-minute-old map 0 1 24 long-form hourly maps 1-24 0 i
L
'. Attachment Cencric Letter 82-28 Supplemental Response Page 3 1
s 24 short-form hourly maps 1-24 1 Long-form current (most recent) map 25 0
. Short-form current (most recent) map 25 1
- History map 26 1
'The five device combinations, with their corresponding VALUE 2, (Device code), are:
Output Device VALUE 2 Trend Typewriter 10 Progconsole Typewriter 20 1,
Progconsole Tape Punch 30
! Trend Typewriter and Tape Punch 13 f
Progconsole Typewriter and Tape Punch 23 DESCRIPTION OF SUBCOOLING MARGIN MONITOR Core Cooling Monitor [SCM-RC-100]
i The primary function of the core cooling monitor is to provide the l operator with indication of the margin to saturation of the primary l coolant in the reactor core.
The monitor can also be used to verify that natural circulation is taking place as well as a digital indication of pressure, temperature, and saturation temperature for existing pressure, i
The core cooling monitor is an 8-bit 8080A based microcomputer dedicated to monitor primary plant pressure and temperature. It is programmed to provide various functions to aid the operator in determining the condition of the core.
The core cooling monitor provides the margin to saturation on an analog remote meter located above the core cooling monitor as well as on a digital display on the monitor itself. The monitor is located i on the vertical board, Section B.
Attachmeat Generic Letter 82-28 l Supplemental Response i l
Page 4 In addition to margin to saturation, the monitor provides caution and alarm status lights and annunciator contacts to warn the operator of an unacceptable margin to saturation or of a monitor malfunction. The monitor also provides the operator with the saturation temperature for the lowest primary plant pressure, core delta-T information for determining natural circulation flow, and access to individual pressure and temperature read-out's for each of the inputs.
The monitor receives its inputs from the same inputs for plant pressure and temperature that the P-250 computer receives. Eight in-core thermocouples, loop A and B wide range RTD's for Th and Tc, loop C wide range pressure, and pressurizer pressure are fed into this monitor. The monitor uses the highest temperature and the lowest pressure to determine the margin to saturation and to provide the ala rms . A front panel indicating light shows which pressure input is being used. The remote meter has a selector switch to allow the operator to display the margin to saturation on the analog meter as determined by the RTD's, or the thermocouples. As a back-up to this monitor, the operator has curves available which depict the margin to saturation and corresponding saturation curve based on plant pressure and temperature.
A pre-programmed read-only-memory (ROM) contains the necessary prodramming and data to provide the functions generated by this monitor. Random access memory (RAM) stores temporary inputs to the monitor for use in its calculation. Pressure and temperature are converted to digital form in an on board analog to digital (A to D) convertor. Outputs to the remote meter are converted to analog form in the computer's digital analog convertor (D to A) .
The core cooling monitor is an Intel 8080A single board computer. It uses national PROM / RAM boards for programming and scratch-pad memory.
Data TRANSLATION in-out (I/0) boards are provided to convert the pressure and temperature inputs to digital form for the computer and to allow the computer to generate a remote analog meter with an on-board power supply.
The monitor receives 120 VAC input power from PNL-AC-E4, an emergency power supply.
It provides outputs to the margin to saturation meter located above the monitor, and to an annunciator panel for caution and alarm conditions.
- 9. Provide a schedule for additional subuittals required ** Complete
.. At tachment Generic Letter 82-28 Supplemental Response Page 5
- II.F.2 Attacheent 1 (for Core Exit Thermocouples)
In response to item 4 in the above checklist, the following materials should be included to show that the proposed system meets the design and qualification criteria for the core exit thermocouple system.
- 1. Provide diagram of core exit thermocouple locations or reference the generic description if appropriate.
Response
Refer to Figure 1 for a diagram of the core exit thermocouple loca-tions. This figure is an example of a core map indicating core exit t empe ra tu res .
- 2. Provide a description of the primary operator displays including:
- a. A diagram of the display panel layout for the core map and description of how it is implemented, e.g. , hardware or CRT display.
- b. Provide the range of the readouts
- c. Describe the alarm system
- d. Describe how the ICC instrumentation readouts are arranged with respect to each other.
Response 2a:
Refer to Figure 2 for a diagram of the primary panel diaplay for any selected core exit thermocouple temperature. A core map, Figure 1, may be printed on demand by the Operator inputing the correct address statement to the computer at the console. The backup display is a Honeywell Precision Temperature Indicator which
! permits selection of a single thermocouple to be indicated using nonlocking key switches on the front of the indicator. The switch must be manually held in positicn to monitor the desired thermocouple.
In addition to this system, the operator may display core exit temper-atures on the subcooling margin monitor. Displays are continuous on demand. Refer to Figure 3 for the location of the CETCs providing l inputs to the subcooling margin monitor.
l There are presently two systems being installed which will enhance the operator's ability to monitor core exit temperatures. A new data aquisition system, referred to as the Plant Variable Computer System (PVS) and the Safety Parameter Display System (SPDS) . Each of these provide the operator a CRT display of each CETC temperature.
The PVS is an alpha-numeric df splay and the SPDS display is similar to that shown in Figure 1. These systems are being installed to enhance our emergency response capability.
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.. Attachment Generic Letter 82-28 Supplemental Response Page 6 Response 2b:
plant computer 0-700*F subcooling margin monitor 0-1650*F plant variable computer system 0-1650*F SPDS 0-2500*F Response 2c: r the plant computer alarms at 700*F and is displayed on the
] computer printer.
4 Response 2d:
refer to Figure 4 - to locate instrument displays i
- 3. Describe the implementation of the backup display (s) (including the subcooling margin monitors), how the thermocouples are selected, how they are checked for operability, and the range of the display.
4
Response
The back-up method for the plant computer system for determining
, core exit temperature was discussed in response ::> item 1 in our original response to Generic Letter 82-28, dated March 25, 1983.
There does not exist a pre-established method of thermocouple selection at the Honeywell Precision Temperature Indicator panel.
Operability is determined when the nonlocking key switch is moved to display a thermocouple reading.
The back-up method for the subcooling margin monitor is by using
- the RCS pressure and temperature indication and determining degrees subcooled. Curves of pressure vs. temperature have been prepared and inserted in our procedures which identify 50' subcooled, 20' subcooled and saturated conditions. Pressure is obtained from the RCS wide range pressure transmitters and temperature is obtained f rom the wide range RTD hot leg temperature or the core exit thermocouple indication.
- 4. Describe the use of the primary and backup displays. What training will the operators have in using the core exit thermocouple instru-l mentation? How will the operator know when to use the core exit thermocouples and when not to use them? Reference appropriate emergency operating guidelines where applicable.
Response
The core exit thermocouple primary and secondary displays are used daily by the operators. The most frequent use is when a core map is being run and a core exit temperature printout similar to Figure 1 is requested.
Attachment Generic Letter 82-28 Supplemental Response
? age 7 All operators have been trained not to rely on any one indicator when evaluating plant parameters. A precaution statement has been added to our procedures advising the operators to monitor redundant or related channels to check for consistency while performing pro-cedure steps. Our E0Ps direct the operator to determine degrees subcooling by monitoring the CETCs or the wide range RTDs.
Additional training to the operators will be based on the new E0Ps which are currently under development. These are symptom based procedures which will follow the Westinghouse Emergency Response Guidelines (ERGS).
- 5. Confina completion of control room design task analysis applicable to ICC instrumentation. Confirm that the core exit thermocouples meet the criteria of NUREG-0737, Attachment 1 and Appendix B, or identify and justify deviations.
Response
The Westinghouse ERGS were developed to provide instructions for the operators to follow under emergency conditions. These guide-lines have as their basis the transie.nt and accident analysis for which the plant was designed and the steps necessary to mitigate these accident conditions. The new E0Ps will be validated as to their effectiveness in accordance with our response to Generic Letter 82-33 where a schedule has been presented for the completion of symptom based EOPs and a control room design review. An evalua-tion of the CETCs is included in the TABLES attached to this sub-mittal.
- 6. Describe what parts of the systems are powered from the lE power sources used, and how isolation from non-lE equipment is provided.
Describe the power supply for the primary display. Clearly delineate in two categories which hardware is included up to the isola tion device and which is not.
Response
The CETC and primary display system is powered from the emergency bus with diesel back-up provided. Included with this submittal is drawing number 8700-RE-lZ which is a one line diagram identifying the power supply to the computer.
- 7. Confirm the environmental qualification of the core exit thermocouple instrumentation up to the isolation device.
Response
The core exit thermocouple instrumentation is not environmentally qualified. Refer to the TABLES included with this submittal which provide the evaluation of conformance of the CETCs to NUREG-0737, Attachment 1 and Appendix B.
.. Attachment Generic Letter 82-28 Supplemental Response Page 8 Appendix B (of NUREG-0737, II.F.2)
Confirm explicitly the conformance to the Appendix B items listed below for the ICC instrumentation, i.e., the SMM, the reactor coolant inventory tracking system, the core exit thermocouples and the display systems.
Response
Subcooling Margin Monitor: This instrument was installed following NRC guidance provided in NUREG-0578 and as such its design did not include a reference to Appendix B of NUREG-0737. We will be review-ing this instrument as part of our review of Regulatory Guide 1.97, Rev. 2 to be done in accordance with our schedule submitted in response to Generic Letter 82-33, dated April 15, 1983.
Core Exit Thermocouples: Refer to TABLE 2 for the evaluation of the CETC to Appendix B.
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TABLE 1 i
NUREG 0737 Item II.F.2 Attachment 1 Design and Qualification Criteria For PWR Incore Thermocouples item Criteria Confo rmance No.
1 Sufficient number of thermocouples for Yes. See Figure 1 each core quadrant 2a A spatially oriented core map available Yes. See Figure 1 and Note 1 on demand 2b Selective reading of core exit Yes. See Note 2 temperature, continuous on demand 2c Direct readout and hardcopy capability Yes. See Note 2 and response to Item 2b in the attached response to this Generic Letter for readout ranges.
2d Trend capability, temperature time Yes. From the unit on-line computer history available on demand See Note 2 2e Appropriate alarm capalility Yes. Alarms at 700*F 2f Operator - display device interface Yes. See Note 3 3 Backup displays Yes. See Note 4 4a Human factors analysis on use of To be done as part of the Detailed information during normal and Control Room Design Review for ab-abnormal plant conditions normal operations 4b Integration into E0P's Yes. Utilizing Westinghouse Owner's Group ERGS 4c Integration into operator training Completed under ICC Training 4d Other alarms and need for prioritization The WOG ERGS address the priorities for maintaining all critical safety functions 5 Conformance to Appendix B No. See Table 2 6 Display channels should be electrically No. See Note 5 independent , Class lE power, and physically separated
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TABLE 1 Item Criteria Conformance 7 The instrumentation should be No. See Note 5 environmentally qualified 8 99% availability No. See Note 6 9 QA No. See Table 2 NOTES:
Note 1: In addition to the core map in Figure 1, upon completion of the SPDS, a copy of the CRT display of a spatially oriented core map will be available on demand.
No te 2 : The primary display can provide a continuous indication of a CETC on demand. The core subcooling monitor can also provide a digital indica-tion of a CETC at the microprocessor located in the control room. (see Figure 4). Upon completion of the plant variable. computer system and the SPDS, the operator will have two additional display capabilities available to him to continuously monitor CETC. This is a direct readout of core exit temperature and a hardcopy of the display is available.
Additionally, the plant variable computer can feed chart recorders to trend selected parameterc, which include CETCs.
Note 3: Rapid access to temperature displays is possible at the plant computer console. (See Figure 2). This will also be a feature of the two additional computer systems being installed in the control room.
Note 4: The back-up display for the primary CETC display is the Honeywell Pre-cision Temperature Indicator which is capable of monitoring all CETCs.
The subcooling margin monitor microprocessor display is capable of displaying any one of eight specific CETCs up to 1650*F. Additional monitoring capability will exist upon completion of the two computer systems being installed as discussed above.
Note 5: In order for our CETC system to satisfy these criteria, this system l
would have to be upgraded. It is our position that the benefit for upgrading cannot be justified as previously stated.
Note 6: This was not a design requirement when the plant computer was designed and installed. Additional display information, through the use of the two ncw computer systems, will provide additional display capabilities which have been designed to provide a high degree of availability.
TABLE 2 EVALUATION CHECKLIST NUREG-0737 Item II.F.2 Appendix B Criteria Core Exit Thermocouples Item Criteria Conformance No.
1 Instrument Environmentally qualified in No. The CETC's are part of the accordance with RG 1.89 (NUREG 0588) Incore Instrumentation and are instrument grade. It is our posi-tion that upgrading the CETCs cannot be justified.
2 No single failure should result in loss No, however, a diverse channel is of indication provided by the coolant loop wide range RTD's.
3 Class lE power The main computer is the readout device and is powered from an in-verter with a battery backup.
4 Instrument channel available prior to Yes.
an accident 5 QA requirements No. The CETCs were installed as instrument grade and as such, the QA provisions of Appendix B did not apply.
6 Continuous indication On demand only. Use of the unit-on-line computer is the normal means for recording incore thermo-couple readings. A Honeywell Pre-cesion Temperature Indicator provides backup readout capability. The two additional systems currently being installed will provide additional capability.
7 Recording of instrument readout Yes. The ins trument readout is recorded in the on-line computer and thermocouple histories can be made. Additional capabilities are currently being installed as previously discussed.
8 Instruments specifically identified No. The core exit thermocouples for use under accident conditions are part of the incore instrumenta-tion and are also used during normal operation.
TABLE 2 Item Criteria Conformance No.
9 Isolation devices No. There are no isolation devices.
10 Means should be provided for checking Yes. These instruments are used operational availability periodically during normal operation 11- Servicing, testing and calibrating Yes. Westinghouse provided technical programs to maintain instruments manual and calibration procedure.
12 Means for removal from service in Yes. Administrative controls exist the design should facilitate admin- for removing equipment from service.
instrative control of access to the means for removal from service 13 Design should facilitate administrative Yes. Access to this en,uipment is control of access to set points and restricted, adjustments 14 Monitoring instrument design should Yes. By design, this system is very minimize conditions giving confusing simple and is not susceptable to indications conditions resulting in anomalous indications.
15 Design should facilitate recognition, No. The reference Junction Boxes are location, repair replacement, or ad- inside containment and may not be justment of malfunctioning components accessible.
16 Instrumentation inputs should be from Yes. The CETC's directly measure sensors measuring the variable core exit temperature 17 Instruments should be used for both Yes. The CETC may be used by the normal and accident monitoring operators, in conjunction with other instruments, at all times.
18 Periodic testing per R.G.1.118 No. This criteria was not an original design requirement for our CETC system.
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