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MONTHYEARML20080G8541983-09-14014 September 1983 Advises That Actions Required by 830708 Generic Ltr 83-28, Items 2.2.2,4.2.3,4.2.4 & 4.3 Re Reactor Trip Breakers Currently Being Reviewed.Response Will Be Provided Upon Completion Project stage: Other ML20086A8401983-11-0404 November 1983 Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events.' Proprietary List Rules Will Be Forwarded Separately Project stage: Other ML20094A3731984-10-30030 October 1984 Responds to 840913 Request for Addl Info Re Generic Ltr 83-28,Items 4.2.1 & 4.2.2.Westinghouse Owners Group Maint Program Reviewed & Pertinent Insps Incorporated Into plant-specific Preventive Maint Program Project stage: Request ML20127K6121985-06-17017 June 1985 Forwards Tables & Figures Summarizing History of Reactor Trip Breakers in Response to Requirement for Addl Justification Contained in 850424 Preliminary Safety Evaluation Per Generic Ltr 83-28,Item 4.2.1 Project stage: Other ML20127G8141985-06-17017 June 1985 Forwards Application for Amend to License DPR-66,removing Iodine Sampler Cartridges from Radioactive Gaseous Effluent Monitoring Instrumentation Project stage: Request ML20138K9301985-10-0808 October 1985 Forwards Safety Evaluation Accepting 850617 Response to Salem ATWS Items 4.2.1 & 4.2.2 Re 18-month Surveillance Frequency for Reactor Trip Breakers Project stage: Approval ML20211Q1081986-12-10010 December 1986 Informs That Contact Pressure Will Be Removed from Reactor Trip Breaker Trending Program.Westinghouse Indicated That Test for Contact Pressure Should Be Go no-go Test Instead of Obtaining Actual Reading.List of Trended Parameters Encl Project stage: Other 1984-10-30
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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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Telephone (412) 393-6000 Nuclear Division sNp' pig" port. PA
- 15077-0004 Division of Licensing U.S. Nuclear Regulatory Commission Attn: 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 83-28, Items 4.2.1 and 4.2.2 Gentlemen:
Attached is the Beaver Valley Unit I response to your letter of September 13, 1984 requesting additional infonnation on Generic Letter 83-28 Items 4.2.1 and 4.2.2 If you have any questions regarding this infonnation, please contact my office.
Very trul yours, J. J. Carey Vice President Nuclear Group 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 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 [
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Attachment Page 1 Response to Request for Additional Information Regarding Salem ATWS Event Items 4.2.1 and 4.2.2 1.1 Information Request for Item 4.2.1 Included with the submittal is a copy of the Beaver Valley 1 Preventa-tive Maintenance Procedure for the Reactor Trip Switchgear effective March 9,1983, which is in substantial conformity with the Westing-house recommendations. However, the submittal states that "when the WOG program is finalized, we will review the program and adopt the preventative maintenance reconmendations determined necessary to maintain the reactor trip breakers." Do you intend to adopt the Owners Group program in total? If not, identify any exceptions that may be taken with respect to the Westinghouse recommendations for the maintenance of the breakers and provide appropriate justification.
Response
The Westinghouse Owners Group Maintenance Program has been reviewed, and the pertinent inspections have been incorporated into the plant-specific preventive maintenance program. The following are the major exceptions:
A. The frequency of the preventive maintenance has remained at 18 months (refueling) instead of the semi-annual and refueling intervals recommended in the WOG program. This is based on acceptable performance and results from prior preventive mainte-nance, surveillance testing, and reactor trips.
B. Presently, no counters are installed on the breakers, as such, the PM program does not call out replacement of the UVTA at 1250 cycles. However, a design change has been initiated to investigate the possibility of adding counters.
Attached for your information is a copy of the preventive maintenance program for the 'A' reactor trip breaker, revised to incorporate the pertinent inspections of the WOG Maintenance Program.
In addition, a corrective maintenance procedure was developed for rcplacement of the UVTA based on the WOG maintenance program.
. __ ___ _ _ ~ , . - - ~ ~ _ . _ - . _ - . _ - - _ _ - . _ _ _ . - - - . _ - _ - _-.
. Attachment Page 2 1.2 Criteria for Evaluating Compliance With Item 4.2.1 The Beaver Valley 1 Reactor Trip System utilizes Westinghouse DB-50 circuit breakers. The primary criteria identified for an acceptable maintenance program for this breaker is contained in the Westinghouse Maintenance Program for DB-50 Trip Switchgear. Specifically, the criteria used to evaluate compliance should include those items in the Westinghouse program that relate to the safety function of the breaker supplemented by these measures that must be taken to accumu-late data for trending.
Response
The pertinent items in the WOG program related to safety, specifically undervoltage trip attachment, shunt trip attachment, and lubrication, have been incorporated into the plant-specific program (Steps II.C,
.D, .M, .Q, .T, and .U).
Data Sheets 1 and 2 are used to record parameters taken during the test and compare the values with their required values.
2.1 Infonnation Request for Item 4.2.2
- a. The submittal states that the breaker time response data along with other pertinent infonnation will be used to forecast any possible degradation in the breaker operability. You should identify what other parameters such as trip force, dropout voltage and breaker insulation resistance will be used for this forecast.* You should also provide verification that the selec-tion of parameters is sufficient to track all of the relevant factors that give indication of degradation of the breaker safety related function and that the breaker time response measurement includes the operating time of the under-voltage trip attachment.
*Four parameters have been identified as trendable and are included in the criteria for evaluation. These are (1) Under-voltage trip attachment dropout voltage, (2) trip force, (3) breaker response time for under-voltage trip, and (4) breaker insulation resistance.
Response
The parameters trended for the reactor trip breakers at Beaver Valley 1 are:
Response time for reactor trips from plant computer Response time for undervoltage trip attachment from breaker time response test Response time for shunt trip attachment from breaker time response test Undervoltage trip attachment dropout voltage from preventive maintenance
Attachment Page 3
- Trip force from preventive maintenance Insulation resistance from preventive maintenance Contact pressure from preventive maintenance Contact resistance from preventive maintenance This set of parameters is based on our reviews of vendor information along with operating experience.
In addition, data obtained from maintenance activities (i.e., parts replaced) is maintained for future reference.
The operating time of the undervoltage trip attachment (UVTA) and the shunt trip attachment (STA) for the reactor trip breakers is measured during the Technical Specification required time response testing (MSP 1.14). This test includes the time response for the UVTA alone, STA alone, and UVTA-STA together.
2.1 Information Request for Item 4.2.2
- b. The submittal states that trend report results of the reactor trip breakers will be issued periodically to the plant's upper 4
management staff and significant degradation found during breaker trending will be immediately identified for corrective action.
Please provide a discussion of the technical criteria to be used for evaluating trend data. It should include a description of the use of acceptance limits, establishment of baseline values or other basis for identifying significant degradation of the breaker. It should also indicate the schedule or guideline for scheduling evaluation of the trend data.
Response
The technical criteria used to evaluate trend data are:
Parameter Criteria Time Response 50.167 seconds UVTA Dropout Voltage 14.4 to 28.8 Volts Trip Force 530 ounces Insulation Resistance a2.0 megohms Contact Pressure 0.050 to 0.093 inches Contact Resistance 550 micro-ohms These criteria are based on the WOG Maintenance Program, reviews of vendor information, and operating experience.
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. Attachment <
Page 4 The data obtained from the various sources is compared to the acceptance criteria and-plotted. If an unacceptable or questionable condition is identified, supervision is notified for a determination of appropriate corrective action. The parameters, except reactor trip times, have a tentative review schedule of 18 months, which is consistent with the frequency of the procedures which obtain the data. In addition to the trending review, all the procedure results are reviewed by a maintenance engineer upon conpletion.
The response time for reactor trips is reviewed on a monthly basis and reported to supervision in a monthly trend report. Attached is an example plot of trip breaker response time.
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, DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit No. 1 PREVENTIVE MAINTENANCE PROCEDURE TITLE: RTA REACTOR TRIP SWITCHGEAR INSPECTION PMP NO. 1-1RP-BK-RTA-1E System Chapter No: System Chapter
Description:
Frequency:
1 Reactor Control and Protection Sys. 18 Months Equipment No: Equipment
Description:
RTA Reactor Trip Breaker Task
Description:
The Reactor Trip Switchgear will be inspected, tested and lubricated.
Outage or Operating Limits:
The Reactor Trip Breaker will be inspected when the reactor is shutdown'and the rod drive motor generator breakers open. This procedure is to be performed in conjunction with PMP's 1-1RP-BK-l RTB-1E, 1-1RP-BK-BYA-1E, 1-1RP-BK-BYB-1E, and MSP 1.14.
Special Material, Tools or Equipment Required:
, i Handtools, fine file, breaker closing handle, feeler gauges, vacuum cleaner, brush, Lubricant (2)S3701GW, Safety Solvent stocked by DLC, 1000 V Megger, Ductor Test Set, Biddle Lubri-Tact Rheostat Catalog No. 411K50CS or variable 125 VDC power supply, 0-100 VDC Test l . Voltmeter, Closing Sequence Tester, 48 VDC power source with a l' capacity of at least 0.25 amperes, Spring-force scale or force j gauge, 20 oz. weight +0 oz., - 4 oz.
Equipment Location Elevation (Ft.): 715 Housekeeping Zone: IV Building: Service Building Cleanliness Class: D Area: Switchgear Room Category: I l-l PAGE 1 0F 31 REVISION 6
r .
DUQUESNS LIGliT COMPANY Beaver Valley Power Station APPROVAL SH$ET - NONADMINISTRATIVE PREVENTIVE MAINTENANCE PROCEDURE l-lRP-BK-RTA-lE RTA REACTOR TRIP SWITCHGEAR INSPECTION
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BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCMGEAR INSPECTION (continued)
I. PURPOSE The purpose of this procedure is to inspect, lubricate and test the Reactor Trip Switchgear.
II. INSTRUCTIONS NOTE: THE SECOND SIGN-OFF ON STEPS INVOLVING RETURNING VALVES, SWITCHES, WIRING AND/OR COMPONENTS TO THE NORMAL OPERATING CONDITION MUST BE SIGNED AND VERIFIED BY A KNOWLEDGEABLE PERSON OTHER THAN THE PERSON PERFORMING THE PROCEDURE STEP.
NOTE: THIS PROCEDURE INVOLVES THE USE OF SOLVENTS. REFER TO THE BVPS MAINTENANCE MANUAL, GENERAL WORK PRACTICES FOR FIRE PREVENTION TO OBTAIN A BREAKDOWN OF FLAMMABLE /NON-FLAMMABLE SOLVENTS AND CONTROLS REQUIRED FOR THE USE OF FLAMMABLE SOLVENTS.
NOTE: ADHERE TO THE REQUIREMENTS OF STATION ADMINISTRATIVE PROCEDURE, CHAPTER 18, WHEN USING CONSUMBABLE MATERIALS (E.G., LUBRICANTS, SOLVENTS, TAPES, ETC.) ON CATEGORY I EQUIPMENT.
NOTE: RECORD REPAIRED OR REPLACED PARTS INFORMATION ON DATA SREET 2. 0QC REQUIRED VERIFICATION OF REPAIRED OR REPLACED PARTS WILL BE DOCUMENTED ON DATA SHEET 2.
A. Sign on Equipment Clearance.
CAUTION: ENSURE THAT THE RCD CONTROL MOTOR GENERATORS ARE DEENERGIZED SUCH THAT NO POWER IS SUPPLIED TO THE ROD CONTROL SYSTEM.
B. Switchgear Enclosure Inspection. *
- 1. Remove the breaker from the cubicle and place it in a suitable work location.
- 2. Inspect both the stationary and moveable portions of the main, as well as, secondary disconnecting devices for abnormal wear and overheating. Discoloraticn of the surface is not harmful unless corresion due to atmcspheric conditions is sufficiently severe as to leave deposits on the contact surfaces. Any deposits must be removed by rubbing with a clean cloth moistened with Stoddards Solvent, otherwise maintenance supervision must be notified that installation of new contacts is required.
PAGE 2 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
- 3. If required, remove excessive dust from buses, connections, supports and enclosure surfaces by wiping and vacuuming or blowing with electric blower.
- 4. Check buses, primary connections and supports for tightness of bolts.
- 5. Check tightness of all secondary wiring connections at the terminal blocks.
- 6. Inspect the positioning stop bracket and support rails for signs of mechanical damage and corrosion.
- 7. Check breaker support wheels for free movement.
- 8. Inspect cell interlock switches for distortion and free movement.
- 9. Record inspection results on Data Sheet 1.
C. Trip Force Check and Functional Test of Undervoltage Trip Device.
CAUTION: DO NOT PUT ANY MORE THAN 48 VDC ON THE TRIP DEVICE COIL AT ANY TIME DURING THIS PROCEDURE.
- 1. Connect a Biddle Lubri-Tact Rheostat, to a 125 VDC test source as shown in Figure 3, or connect a variable 125 VDC power supply (if available).
- 2. . With the undervoltage device disconnected, adjust the variable resistor or variable power supply to obtain 48
_ VDC on the output.
- 3. Disconnect the 125 VDC test source if the Lubri-Tact Rheostat is being used.
4 Connect the test circuit to the breaker secendary contacts 11 & 12 (See Figure 3).
- 5. Reconnect the 125 VDC test source if the Lubri-Tact Rheostat is being used.
- 6. Readjust the variabic resistor or power supply control slowly, if necessary, to obtain 48 VDC on the undervoltage coil.
- 7. Close the breaker manually.
- 8. Using a spring-force scale or a force gauge, pull or push up vertically on the trip bar (See Figure 5).
PAGE 3 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
Record the force at the instant of breaker trip on Data Sheet 1.
- 9. Drop Out Voltage Test l a. Close the breaker manually.
l
- b. Reduce the D.C. voltage slowly with the variable rheostat or power supply control until the breaker trips. Record the voltage at the time of breaker trip on Data Sheet 1.
- c. Reenergize the UV coil with 48 VDC and repeat steps II.C.9.a and b two times, recording dropout voltages on Data Sheet 1.
- d. Average the three dropout voltages and record the averaga on Data Sheet 1.
l 10. Load the .tt'p bar (See Figure 5) with a weight of 20 oz., +0 oz., - 4 oz.
l
- 11. Apply 48 VDC to the undervolta3, coil and manually close the breaker.
l 12. Deenergize the undervoltage coil and observe and recota on Data Sheet 1 that the breaker trips.
l 13. Remove the weight and the test apparatus.
Weight and Test Apparatus REMOVED INITIAL VERIFIED D. Trip Bar Inspection Raise and lower the trip bar by hand to assure tnat it does not bind (i.e., it should feel like a free weight). Record results on Data Sheet 1.
E. Arc Chutes.
- 1. Remove the three arc chutes (See Figure 1).
- 2. Examine the condition of the arc chutes. While a somewhat pitted, mottled and so'oty appearance is normal, be alert for heavy erosion or broken plates.
Damaged chutes should be replaced in the return to service section of this procedure. Record the condition of the arc chutes on Data Sheet 1.
PAGE 4 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
F. Retaining Ring Inspection.
Check that all retaining rings are securely in place on all visible shafts and pins as follows:
- 1. Moving Contact Hinge Pins (6, 2 per pole).
- 2. Stationary Arcing Contact Hinge Pins (6, 2 per pole).
- 3. Crossbar (2, one on each side).
- 4. Operating Mechanism (8, 5 left side).
- 5. Auxiliary Switch Linkage (3, 3 right side).
- 6. Pantograph (6, 3 top and 3 bottom).
- 7. Positioning and Interlock Lever (2).
All Retaining Rings Secure. INITIAL G. Bolts.
Check all visible bolts and nuts for tightness.
H. Cleanliness.
If required, remove dust from the breaker parts with a vacuum cleaner and brush. Clean caked dirt from the breaker pins and slides with Safety Solvent.
< I. Positioning Lever.
Check the spring loaded lever on the left side of the breaker for the following:
- 1. Lever is undistorted and moves freely.
- 2. Stop pin is und!storted.
- 3. Trip arm is undistorted.
Record inspection results or Data Sheet 1. .
J. Pole Bases.
Inspect the physical condition of the pole bases checking for dirt or cracks. Clean as necessary. (The pole bases are the molded bases at the rear of the pole through which the breaker studs pass.) Record inspection on Data Sheet 1.
PAGE 5 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
K. Insulating Link (Refer to Figure 1).
Check-the insulating link for cleanliness, chips, cracks and '
tightness of locknut. Clean as necessary. Record inspection results on Data Sheet- 1.
L. Wiring.
Check the condition of insulation and terminations. Record inspection results on Data Sheet 1.
NOTE: REFER TO ATTACHMENT 1 FOR LUBRICATION PRECAUTIONS AND TECHNIQUES.
M. Lubrication. '
- 1. Dispense drops of lubricant (Westinghouse Spec.
33701GW) liberally by placing the tip of the dispensing tube at the appropriate location and gently squeezing the container- for the following points in the
} Undervoltage Trip Attachment (See Figure 6).
4 a. Latch to latch spring.
- b. Latch loop to latch guide-pin.
- c. Latch to latch pin.
- d. Latch pivot.
. e. Latch. pivot pin bearings.
- f. Pin running through the trip spring.
Record lubrication on Data Sheet 1.
', 2. Exercise the mechanism during and fol!cwing lubricant application by blocking the breaker partially. towards the. closed position so that the UTVA reset lever is released. Exercise the device by manipulating the reset lever.
- l. 3. Breaker Mechanism Lubrication.
NOTE: IF A SOLVENT HAS NOT BEEN USED ON THE BREAKER AND THE BREAKER DOES NOT SHOW SIGNS OF SLUGGISHNESS OR FRICTION, STEP II.M.3 MAY BE OMI'ITED. INDICATE ON DATA i
SHEET 1. WHETHER LUBRICATION WAS APPLIED OR NOT.
CAUTION: NEVER USE LUBRICANT ON CURRENT CARRYING PARTS.
l PAGE 6 0F 31 REVISION 6
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BVPS - PMP 1-IRP-BK-RTA-1E RTA REACTOR TRIP-SWITCHGEAR INSPECTION (continued)
- a. Apply lubricant sparingly to all mechanism pins, bearing points and latch surfaces.
- b. Tie back the adjustable reset lever on the undervoltage trip device.
- c. Manually close and trip the breaker several times.
N. Operating Machanism Test.
- 1. Tie back or check tied back the adjustable reset lever on the undervoltage trip device (Refer to Figure 2).
This will allow the breaker to be closed without being automatically tripped by the undervoltage device.
CAUTION: KEEP HANDS AND TOOLS WELL AWAY FROM MOVING PARTS OF THE BREAKER TO AVOID PERSONAL INJURY OR EQUIPMENT *)A'9GE.
- 2. Attach a Closing Sequence Tester or equivalent to each phase of the Circuit Breaker. The Tester will monitor the arcing contacts of the breaker. When the Tester lights are lit, the breaker arcing contacts are made.
- 3. Slowly close the breaker by exerting a slight closing pressure on the closing handle (See Figure 1) and simultaneously pushing forward on the breaker cross bar to start the breaker closing. Continue to slowly twist the breaker closing handle until one of the Tester lights are lit.
- 4. Continue to close the breaker and check visually to ensure that the arcing contact touches before the main contact in the same phase for each phase. Record this action on Data Sheet 1.
- 5. Push the push-to-trip button and ensure that the following occurs. Record on Data Sheet 1.
- a. The toggle linkage should collapse and the mcving contact assemblj move freely to the full open position. This should be followed by complete resetting of the links in the toggle mechanism.
- b. The links are free to move without friction or binding.
O. Arcing and Main Contacts.
- 1. Examine the condition of the arcing and main contacts check for roughness, spawling, galling or distortion.
Some tarnishing is normal due to silver oxides and sulfides. Remove rough or high spots on the contacts PAGE 7 0F 31 REVISION 6
i BVPS - PMP 1-1RP-BK-RTA-1E l RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued) with a fine file or replace the contact if necessary.
Record inspection results on Data Sheet 1.
1 NOTE: IN THE FOLLOWING STEP DO NOT OVERADJUST AS THIS WILL i
CAUSE THE CONTACT SPRINGS TO COMPRESS TO THE SOLID POSITION AND THUS INCREASE THE CLOSING EFFORT. CHECK FOR OVER ADJUSTMENT BY PRYING THE STATIONARY ARC TIPS OPEN TO AT LEAST 1/16 INCH GAP.
i
- 2. Close the breaker and check the contact pressure by
) measuring dimension "G" with feeler gages (Refer to Figure 1). The gap should be between 0.050 and 0.093 inches. Record the As Found gap on Data Sheet 1. If the gap is out of tolerance, adjust the gap by removing the crossbar and screwing the insulating link in or out on the stud. Tighten the lock nuts after each adjustment.
h
- 3. With the breaker closed measure the main contact s resistance of each phase with a Ductor Test Set. .
Resistance should not exceed 50 micro-ohms. Record
P. Control Relay.
!- 1. Examine the contacts for wear and pitting. Replace the t- contacts if necessary (Refer ~to Figure 7).
- 2. Disconnect the closing coil leads from the control i
circuit wiring. ;
- 3. Energize the relay operating coil and slowly close the breaker manually. The relay release arm should operate '
the relay trip assembly and the relay trip assembly should open the relay contacts just before the breaker
~
latches. This position can best be determined by
, ' watching the pawl in the breaker operating mechanism, which should snap in' place just after the relay contacts open. Record results on Data Sheet 1. If
- this operation is not correct proceed as follows
- a. Bend the relay release arm in the corrective '
direction.
- b. Make rure that the relay release arm does not rub '
on' either side of the relay trip assembly lever aperture.
- c. When the breaker is latched, deenergizing and then.
energizing the relay operating -coil should not cause the relay contacts to move toward the closed position.
i-PAGE 8 0F 31 REVISION 6 i
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BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
- 4. Deenergize the relay operating coil and remove the test apparatus.
- 5. Reconnect the closing coil leads to the control circuit wiring.
Closing Coil Leads RECONNECTED. INITIAL VERIFIED Q. Shunt Trip Attachment (See Figure 4).
- 1. With the breaker in the open position, manually push the moving core against the stationary core (Verify movement is free and nonbinding.) and rotate the breaker handle to the closed position. Verify on Data Sheet 1 that the breaker is trip free, i.e., the trip lever will raise the trip bar which prevents closing of the breaker.
NOTE: TRIP LEVER TO TRIP BAR CLEARANCE IS NONADJUSTABLE. IF THE VALUE MEASURED IS OUT OF TOLERANCE, VENDOR SERVICE IS REQUIRED.
- 2. Measure and record on Data Sheet 1 the cicarance of the shunt trip lever to the trip bar.
- 3. Check tightness of shunt trip attachment mounting bolts.
- 4. Close the breaker manually.
- 5. Using the 125 VDC variable power supply apply 70 VDC to the shunt coil via the secoadsry contact terminals, (See Figure 9) and observe and reccrd on Data Sheet 1 that the breaker trips.
- 6. Recave the test apparatus.
Test Apparatus REMOVED. INITIAL VERIFIED R. Auxiliary Switches.
- 1. Manually operate the breaker and check that contacts
- are touching well before the end of travel (See Figure 8). Record results on Data Sheet 1.
- 2. Inspect contacts for burning and pitting. Replace the contacts if necessary. Record inspection results on Data Sheet 1.
PAGE 9 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E-RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
S. Insulation Check.
- 1. With the breaker closed, megger from the primary disconnect on each phase to ground with a 1000 V Megger. Record results on Data Sheet 1.
- 2. With the breaker open, megger from the primary disconnect on each phase to ground with a 1000 V Megger. Record results on Data Sheet 1.
T. Under-Voltage Trip Attachment.
- 1. Manually close the breaker and check that trip lever to trip bar clearance is approximately 1/16 in with the breaker halfway closed.
CAUTION: BE SURE *O HOLD THE VERY END OF THE RESTRAINING LINE AND KEEP BOTH HANDS, AS WELL AS EQUIPMENT, AVAY FROM THE CROSSBAR WHICH WILL SNAP BACK AS THE BREAKER TRIPS.
- 2. Slowly release the temporary restraint allowing the UV attachment to perform the breaker trip function before the reset lever comes to rest. Visually monitor for smooth, unhesitant, positive, snap-action of the UV attachment and breaker trip.
Temporary Restraint REMOVED. INITIAL VERIFIED
- 3. - Post Lubrication Drop Out Voltage Test CAUTION: DO NOT PUT AST MORE THAN 48.VDC ON THE TRIP DEVICE COIL AT ANY TIME DURING THIS PROCEDURE.
- a. Connect a Biddle Lubri-Tact Rheostat, to a 125 VDC test source as shown in Figure 3, or connect a variable 125 VDC power supply (if available),
- b. With the undervoltage device disconnected, adjust the variable resistor or variable power supply _ to obtain 48 VEC on the output.
- c. Disconnect the 125 VDC test source if the Lubri-r Tact Rheostat is being used.
~ d. Connect the test circuit to the breaker secondary
- contacts 11 & 12 (See Figure 3).
- e. Reconnect the 125 VDC test source if the Lubri-
{ Tact Rho.ostat is being used.
I PAGE 10 0F 31 REVISION 6 4
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BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
- f. Readjust the variable resistor or power supply control slowly, if necessary, to obtain 48 VDC on l the undervoltage coil. t I
- g. Close the breaker manually.
- h. Reduce the DC voltage slowly with the variable rheostat or power supply control until the breaker trips. Record the voltage at the time of breaker trip on Data Sheet 1.
- i. Reenergize the UV coil with 48 VDC and repeat Steps II.T.3.g and h two times recording dropout voltages on Data Sheet 1.
- j. Average the three dropout voltages and record the average on Data Sheet 1. i
- 4. Remove the test apparatus. j Test Apparatus REMOVED. INITIAL VERIFIED U. Cell Interlocks Test and Return to Service
- 1. Reinstall the three are chutes and covers.
- 2. Return the breaker to the cubicle.
- 3. Sign off Equiement Clearance on Log Only.
- 4. Have Operations rack.the breaker into the TEST position and close it.
- 5. Release the position lever. The breaker will trip.
Record trip on Data Sheet 1.
- 6. Have Operations rack the breaker partially toward the CONNECTED position.
- 7. Try closing the breaker between the TEST and CONNECTED positions; it should not close. Record results on Data Sheet 1.
- 8. Have Operations rack the breaker to the CONNECTED position.
- 9. Check the positioning lever stop pin for positive engagement with the third (rear most) slot of the positioning stop bracket. Also check for a visible PAGE 11 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP Sh'ITCHGEAR INSPECTION (continued) clearance (1/16" minimum) between the positioning icver trip arm and the breaker trip bar.
- 10. Have Operations close the breaker.
- 11. Depress the positioning interlock lever on the left side of the breaker. The closed breaker will trip.
Record trip on Data Sheet 1.
- 12. Have Operations close the breaker and then trip it froia the MCB switches for a total of 10 trips.
- 13. Sign off Equipment Clearance.
l
- 14. If PMPs 1-1RP-BK-RTB-1E, 1-1RP-BK-BYA-1E, and 1-1RP-BK-l BYB-1E have been performed, notify Maintenance Supervision to have the Instrumentation and Control Department perform MSP 1.14. If the PMP's have not been performed, perform them at this time and then have MSP 1.14 performed.
PAGE 12 0F 31 REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
REFERENCES:
A. Duquesne Light Company Accident Prevention Manual.
B. Beaver Valley Power Station Operating Manual, Chapter 48.
C. Beaver Valley Power Station, Unit No. 1, FSAR.
D. Westinghouse Instruction Manual for Type DB-50 Air Circuit Breaker, I.B. 33-850-3D, Index File No. 1.11-235A.
E. Westinghouse, Nuclear Service Division, NSD Letter Data Letter 74-2. WIN: 236-4744.
F. Duquesne Light Company Electrical Test Procedure No. 5-4, Issue 0.
G. Wm. S. Lacey letter NDISS1:0968 of Oct. 5, 1983.
H. Westinghouse Reactor Trip Switchgear Maintenance Program 1718D:4.
I. Westinghouse NSD Technical Bulletin 83-02, Rev. 1.
J. J.J. Carey to NRC, 11/4/83, response to Generic Letter 83-28 (NDISLC:0813) items 3.1, 4.1 and 4.2.
K. Stone & Webster Dwg. No. 08700-RE-5K.
c PAGE 13 0F 31 REVISION 6 1
, SVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (centinued)
PREVENTIVE MAINTENANCE PROCEDURE BRIEFING SHEET I have read, understand and will follow Preventive Maintenance Procedure No. 1-IRP-BK-RTA-1E Revision No. 6 Titled RTA Reactor Trip Switchgear Inspection SIGNATURE DATE l
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PAGE 14 0F 31 hEVISION 6 l
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BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
DATA SHEET 1 PROC.
'INIT./
STEP ACTION REQUIRED CHECK B. 10. Switchgear Enclosure Inspection Results Good C. 8. Force at Breaker Trip oz. 6 31 oz. j j 9b. Voltage at which UV device operates VDC 14.4-28.8 VDC i l
9c. Voltages at which UV device operates ; ,
VDC VDC 14.4-28.8 VDC l
9d. Average of th'.ee dropout voltages j VDC l14.4-28.8 VDC l
- 12. Trip Bar loaded and UV device j l
deenergized : Breaker Tripped
. l D. Trip Bar Non-Binding E.2 Arc Chute Inspection !Not Burned ior Cracked I. Positioning Lever Inspection Lever, Stop pin landtriparm
'undistorted and lever moves
. freely.
J. Pole Base Inspectica - Clean and Uncracked K. Insulating Link Inspection Clean, no cracks, no chips and locknut tight.
1 L. Wiring Inspection Insulation in good condition and terminal connections tight, PAGE 15 OF 31 REVISION 6 l
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
DATA SHEET 1 (continued)
PROC.
INIT./
STEP ACTION REQUIRED CHECK M. 1. UVTA Lubricated
- 3. Breaker Mechanism i Lubricated Not Lubricated N. 4. Arcing Contacts Touch before the Main Contacts Phase A Phase B 1 Phase C
- 5. a. Toggle Linkage lCollapsg Contact Assembly Full Open Position Toggle Mechansim Links Reset
- b. Toggle Mechanisrc Links Free to Move No Binding O. 1. Arcing Contacts Inspection No Roughness, Spawling, Galling or Distortion Main Contacts Inspection No Roughness, Spawling, Galling l; or Distortion
- 2. Contact Pressure (Dimension G)
Phase A in. 0.050 - 0.093 in Phase B in.
Phase C in.
- 3. Contact Resistance Phase A micro-ohms S 50 micro-ohms Phase B micro-ohms i Phase C micro-ohms P. Control Relay
- 3. Relay contacts open just before Open breaker latches
! PAGE 16 0F 31 REVISION 6
F BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
DATA SHEET 1 (continued)
PROC.
INIT./
STEP ACTION REQUIRED CHECK Q. Shunt Trip
- 1. Breaker is Trip Free Trip Free
- 2. Trip lever clearance to 1/32 to trip bar in. 1/8 inch ,
S. Breaker Trips with 70 VDC applied to ,
shunt Coil Breaker '
Tripped l R. 1. Auxiliary Switches Contacts '
touch before the end of travel Contact Made
- 2. Contact Inspection Not Burned Or Pitted S. Insulation Check
- 1. Breaker Closed:
Phase A'to Gnd Megohms 2 2 Megohms Phase B to Gnd Megohms Phase C to Gnd Megohms
- 2. Breaker Open:
Phase A to Gnd Megohms 2 2 Megohms Phase B to Gnd Megohms Phase C to Gnd Megohms T. 2. Trip Lever to Trip Bar Approximately Clearance with Breaker 1/16 in.
halfway closed in.
3h. Voltage at which UV device operatas '
VDC 14.4-28.8 VDC
- 31. Voltages at which UV device operates VDC VDC 14.4-28.8 VDC 3j. Average of three dropout voltage VDC 14.4-28.8 VDC PAGE 17 0F 31 REVISION 6
p
, BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
DATA SHEET 1 (continued)
PROC. INIT./
STEP ACTION REQUIRED CHECK U. 5. Position Lever Released Breaker Tripped
- 7. Breaker between TEST & CONNECTED Breaker will not close
- 11. Positioning Interlock Lever Depressed Breaker Tripped
- 12. Breaker tripped a total of 10 times i from MCB swiches Breaker Tripped j 10 Times INSTRUMENTS USED CONTROL NO. HOLD DATE*
i PERFORMED BY DATE TIME Person In Charge of Work Party APPROVED BY DATE
, Senior Electrical Maintenance Engineer PAGE 18 0F 31 REVISION 6 ,,
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTICN (centinued)
DATA SHEET .!
PART NAME ITEM NO. IDENTIFYING INFORBIATION ACTION OQC FIGURE NO. (STOCK #, SIR #, ETC.) (REPLACED OR REPAIRED) s i
Y K
'k l
t I
l 4 E
!, Y PAGE 19 0F 31 REVISION 6
- -- L..-.- . . - . .- . . , .
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BVPS - PMP l-lRP-BK-RTA-lE RTA REACTOR TRIP SWITCHCEAR INSPECTION (continued) ;
\
l 77 EANEl. .
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Fig.1 Cccss-Sec:icnal Viw cf Type DB-50 Cire it 3r-ak-PAGE 20 op 31 REVISION 6
T
- I Duquesne Light Company ::o. 1-1RP-BK-RTA-1E %v 6
Beaver Valley Power Station RTA Reactor Trip Switchgear
~ Preventive Maintenance Procedure
Title:
Inspection DATE: . Pa ge- -21 or 31
, ~ ,
.- --_ .x. .m .
" 1 l l
~f l n h L.- _s H J - J'
; gqq .s
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m .z. mo r s ADJUSTA2LE RESET LEVER
/ CROSS BAR U
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13MA VGA
$Y'iT'
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- MOVING CORE i
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-(f i c4 i'I '
SELF LCCXtNG SCREW % b, /h// 9'D ~*f's"iTF'Nb 2N_' - aNQ(.Ji J 1v I / / /f
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- f}
COVER "
IL MMQATYd~
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a t !
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' : STATIONA4/ TRIP TRIP a CORE SPR;NG LEVER
- Undervoltage Trip Attachment - Construction Details FIGURE 2 J
\
9 k
s 4
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Duquesne Light Company No. 12:1RP-BX-RTA-lE pe . 6' Beaver Valley Power Station RTA Reactor Trip Switchgear Preventive Maintenance Procedure
Title:
Inspection DATE: Page 22 of 31
~
J
^
C
_, hII cr, c
C kg\L.~e (C\ % s- m uncan vnrkn b E'"" " VC!.TI a N D-vi c e o ft;n uIa m n1 ETERJ l25 Vc:.Ts 'u /
pC f4 0-100 6t.Ts v i 2.
tu l { c .
Q 81OVLE l.v8Ro-Tact
.. .C UiJorisVoL.TAGE TEST YvlfiiNCr I D[ A C-- R 4. ,
1 FIGURE 3 l *A variable 125 VDC power supply may be used in place
- of the Rheostat, if available.
T.
i
Duquesne Light Corapany No. 1-1RP-BK-RTA-lE' n e v , 6-Beaver Valley Power Station RTA Reactor Trip Switchgear Preventive Ifaintenance Procedure
Title:
Inspect, ion DATE: Page 23 of 31 oN 0 o lli g
gepwy
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s 4 o -iip e b>
i 8
0 f CORE 300 /R A M E l
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________ b_.7 LO C A TIO N TR,P LEVER DETAILS Shunt Trip Attachment - Location and Construction Details FIGURE 4 i
f'O/A/7' id$$,WA$ ECAC6 W
* /S s1]f,4.su/?GD 8 y'
/'OLLh4h up Base H
h 1 RIP BAK 4 N
g
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gy a, ~g u ,g, f as on essG VP c oJ y BA*' 'IR tP! a*IG fotLC S
~T R s t' Bak s 8
'l -- L ,oVcc m h 9a* AP'***
cv aoe eessa con ccear ec7 l-- . -f E.
So* nerea = -
.-{p l-} -9 I ~1ds.1 ,g2 H fl!*t'M D K.
SCAL [
L S rRr *>&
g SsDel VsE O ~ TRIP BAC Y M WI7)! at'ER C liR R E alt # tis b .l M m .'TKsP PADS { 3 PER B A'E) P' F1Ll."*Ill o V W i
g o
a FIGURE 5 Y cn 5
BVPS - PMP l-lRP-BK-RTA-lE
, RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
F/ELa Lus2KfTl04/ i OF UVTA
,\
TRIP 55'ACXE T d t Arc.y--- ,
QSPACER . Oy~ri-u
/ W I IN#IOE i
""'?(0?ALf 55)RFACi3
/ l c.
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;,l * !(! J i@-l UBRICATE SURFACES .
^/NDICA TED WITH l
~
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5370 l GW L.
N' -
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ds 555 ENLARGED 'C
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FIGURE 6 PAGE 25 op 31 REVISION 6
. BVPS - PMP l-lRP-BK-RTA-lE
, RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
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8 \ '
CLOSING 3CLENCID MOVING CORE QPERt. TING COlb 166 RELAY McLO STC7 SURFACE \ G 9 e.O a n: g: i o! %: .%Wnm. . .. g:3 ::st g$I;;5qj ;V!:3.a:.:?:W;g' J g 4:?j ;' :4.,;;f.g.E::; 90 , .x. ..,
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A OJtJs M 's- LIVER b= '
stowou? ::st 168 Aac exuT: rea :-c :str Ccat:ct Relay - Adjust.~nnt and Cons:..:c:ica Details FIGURE 7 PAGE 26 0F 31 REVISION 6
. BVPS - PMP l-lRP-BK-RTA-lE RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
EN eAcx covtam swar; a -
k[o susmNs . l l@ l I;. .lIrf8 '***" 8 g l ....
g y .:w.. aw
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=, W = Y cast- N i
e= = == = : . ,
', ., i I@ O
,,,,j' @ (,,j @ lIl @
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rnour coven l P, -
Auxiliary Switch - Consm:c:ica Detaila FIGURE 8 l
PAGE 27 0F 31 REVISION 6
BVPS - PMP l-lRP-BK-RTA-lE RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
NKh o -o y -o -
o -o --o -o o-. o- o i oq -
0 0 9 9 o Q o Q o o o 9 i ,
1 2 3 4 5 6 7 8 9 10 ll I2 1 13 14 15 16 17 18 19 20 21 22 23 24 2123 I f
, lh $ '
I -
- I 22 24 g T FIELD CHANGED 13.15 1,719 > TC UV i
MCONTACT TO "b"
[6 CONTACT 3 T7p T -
ll 12 141618 2 5 34 l
iih -iu"x M mT ' '
7i 2 6 10 8'l' A CC o
LX I-o 5
n
'5 hX 6- SB ii ;F-y_y_y __
DB-50 ACB CONN DI AG (FV)
FIGURE 9 PAGE 28 0F 3J REVISION 6
BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TR'P SWITCHGEAR INSPECTION (continued)
ATTACHMENT 1 i LUBRICATION PRECAUTIONS AND TECHNIQUES
, 1. The lubricant is to be dispensed with the chemists polyethylene " wash bottle" provided with the app 11cator kit. Lubricant handling and
+
application techniques are further described in the Instruction Sheet
- accompanying the Application Kit.
1 2. The lubrication may be performed without removing the UVTA from its L mounting. However, special care is required to reach all lubrication points by varying the direction'of the application bottle dispensing tube.
i
- 3. Place a' cloth beneath the UVTA while applying lubricant to collect over-shoot and run-off lubricant.
i
- 4. The -lubrication mixture must be kept thoroughly mixed prior to and
- throughout the procedure by vigorously shaking the container i occasionally.
1 7
- 5. The_only UVTA lubricant approved by Westinghouse is. a composition of a
- finely ground and purified natural ore of molybdenum disulfide and iso propyl alcohol. It is prepared by mixing 5 parts by weight of this lubricating grade molybdenum disulfide with 3 parts by weight of ;
commercial grade isopropyl alcohol. (Lubricant specified to Westinghouse Spec. 53701 GW.)
-6. Application i
i^ a. Thoroughly mix contents in glass container of lubricant by
, shaking vigorously for two minutes.
t
- b. Remove lubricant cap and attach the dispensing tube assembly.
Tighten the tube assembly on the container. Pull gently on tube
[ to make sure it is fully extended.
- c. Drops of lubricant are to be dispensed by placing the tip of the dispensing tube at the appropriate location and raising the
' lubricant container to the vertical position. It may be j desirable to try out the dispenser to get a feel for the position
, required to dispense one drop.
- d. While using the lubricant, shake the container about every minute to keep the lubricant from settling out. , , l
! e. _If the contents have been left standing for longer than 5 L minutes, it will require shaking for two minutes.
4.
3 PAGE 29 0F 31 REVISION 6
. BVPS - PMP 1-1RP-BK-RTA-1E RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
ATI'ACHMENT 1 (continued)
- 7. After using the dispenser for lubrication, if the lubricant is to be stored overnight or longer, the following storage steps should be taken:
- a. Remove dispensing tube assembly from lubricant container and seal lubricant with original cap.
- b. Wipe excess lubricant from outside surface of dispensing tube with a clean towel or cloth.
- c. Attach dispensing tube assembly to top of carrier container.
- d. Invert carrier container to wash lubricant from dispensing tube, 12 to 15 drops of carrier should clean the tube. The carrier is flammable and should be dispensed into a suitable container used for storage of flammable waste solvents. Remove dispensing tube assembly and store the clean dispensing tube assembly for future use.
- e. Seal the carrier container with original cap.
- 8. If the tip of the dispensing tube assembly becomes clogged it can usually be cleaned by inserting a common pin into the tip , opening to clear it. Repeat 7.c and d to wash clean.
PAGE 30 0F 31 REVISION 6
e
. BVPS - PMP 1-1RP-BK-RTA-1E ,
RTA REACTOR TRIP SWITCHGEAR INSPECTION (continued)
SURVEILLANCE CRITIQUE FREQUENCY 18 Months CRITIQUE PERFORMER OF TEST FOUND RESULTS SATISFACTORY WITH ENCEPTION OF THE FOLLOWING:
(a) PROBLEM FOUND (b) CORRECTIVE ACTION TAKEN OR INITIATED _
(c) MAINTENANCE WORK REQUEST NO._
WRITTEN AND FORWARDED TO:
INSTR MECH ELEC ENGR HP (d) ESTIMATED DATE OF COMPLETION Initiated by DATE TEST RESULTS FOUND: SATISFACTORY UNSATISFACTORY - RETEST SCHEDULED DATE OTHER ACTION - DESCRIBE _
RESPONSIBLE ENGINEER DATE PAGE 31 0F 31 REVISION 6}}