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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L4271990-09-0707 September 1990 Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications ML20059G0821990-09-0404 September 1990 Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8 ML20059F7551990-08-29029 August 1990 Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining ML20059F1501990-08-29029 August 1990 Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829 ML20028G8731990-08-29029 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71 ML20059D3761990-08-24024 August 1990 Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant ML20028G8881990-08-24024 August 1990 Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned 05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990 Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued ML20058P7651990-08-14014 August 1990 Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc ML20059E0571990-08-10010 August 1990 Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4)) ML20059E7631990-08-0101 August 1990 Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory ML20059B8141990-08-0101 August 1990 Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations ML20056A3471990-07-31031 July 1990 Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed ML20056A1841990-07-27027 July 1990 Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon ML20055H2581990-07-25025 July 1990 Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b) ML20055F7061990-07-0909 July 1990 Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage ML20055D3871990-07-0202 July 1990 Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results ML20058K5031990-06-29029 June 1990 Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria ML20044A3661990-06-21021 June 1990 Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue ML20043G6811990-06-14014 June 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown ML20043H9341990-06-14014 June 1990 Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04 ML20043G5981990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1 ML20043G6851990-06-12012 June 1990 Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp ML20043G7941990-06-12012 June 1990 Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl ML20043G8001990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d ML20043H0291990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program ML20043F5251990-06-0707 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl ML20043F1361990-06-0404 June 1990 Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002 ML20043B5971990-05-18018 May 1990 Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531 ML20043B0511990-05-15015 May 1990 Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario ML20043B1921990-05-11011 May 1990 Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14 ML20042G9761990-05-0808 May 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601 ML20042G8541990-05-0303 May 1990 Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests ML20042G9071990-05-0101 May 1990 Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b) ML20042F1381990-04-30030 April 1990 Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990 ML20042F0991990-04-20020 April 1990 Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program ML20012F5951990-04-10010 April 1990 Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990 ML20042E1471990-04-0404 April 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization ML20012F6021990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed ML20012E3091990-03-23023 March 1990 Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation ML20012E3451990-03-23023 March 1990 Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl ML20012D6491990-03-19019 March 1990 Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus ML20012E4091990-03-16016 March 1990 Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI ML20012D6181990-03-15015 March 1990 Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled ML20042D7401990-03-14014 March 1990 Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89. ML20012D5801990-03-13013 March 1990 Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index ML20012D6221990-03-13013 March 1990 Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events ML20012C1791990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled ML20012E0911990-03-0505 March 1990 Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2) ML20012B7051990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G 1990-09-07
[Table view] |
Text
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'Af M Teieanon. s t2) 4564o00 Nuclear Division August 10, 1982 P.O. Box 4 Snippingport, PA 150774004 United States Nuclear Regulatory Commission '
Office of Inspection and Enforcement Attn: Mr. R. C. Haynes, Regional Administrator Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NRC Inspection 81-16 -
Additional Information Gentlemen:
This letter documents telephone conversations between Mr. T. T. Martin of your office and Mr. J. D. Sieber of my office clarifying the Company's response to Violation B of NRC Inspection 81-16 as set forth in our January 12, 1982 letter. Additional information was requested regarding the manner in which the on-the-job training program modifications identified in the " action to prevent recurrence" satisfies the requirements of ANSI N18.1-1971.
By internal letter dated August 24, 1981 (Attachment A),
an " Employee Qualification Statement", along with instructions for its use, was prepared. This " Employee Qualification Statement" was designed to satisfy Section 5.6 of ANSI N18.1-1971 which requires that " records of the qualifications, experiences, training and retraining of each member of the plant organization should be maintained".
On May 5, 1982, a new procedure (Attachment B) was made effective in the Station Administrative Procedures (SAP-15) which requires a special written evaluation of an employee following an incident which is considered to demonstrate either outstanding or unsatisfactory performance. All members of the station staff are evaluated on an annual basis. This comprehensive evaluation of job performance was designed to reveal not only defects in the training program but also many other factors considered by us to be valuable in managing the work force. SAP-15 requires the Director of Nuclear Division Training to modify the training programs to correct group deficiencies or trends identified to him 8209240346 820916 PDR ADOCK 05000334 a PDR
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NRC Inspection 81-16 -
Additional Information Page 2 by the various group supervisors. This evaluation procedure was implemented in addition to other Corporate rating and deficiency 4
documentation systems which have been in use for a number of years -
and which yield similar information. We believe that the use of SAP-15 satisfies the requirements of ANSI N18.1-1971, Section 5.5 which requires that a "means should be provided in the training programs for appropriate evaluation of its effectiveness".
In reviewing the records related to this action to prevent recurrence, we concluded that additional improvements could be made to the on-the-job training program to more closely meet the requirements of ANSI N18.1-1971. A Standing Operating Order containing the text provided as Attachment C to this letter has been issued. This Standing Operating order will be incorporated into the Operating Manual, Chapter 48, Section 4, " Qualification Of Operating Personnel", by September 1, 1982. This order provides the following additional assurances of compliance:
i
- 1) Makes mandatory the use of qualified personnel
- 2) Sets controls on and documents the content of the training
- 3) Provides a qualitative assessment of the effectiveness of the training before the trainee is allowed to perform the task without direct supervision
- 4) Requires a review by the Nuclear Training Section which will permit the evaluation of the adequacy of training being conducted by this method.
We have also noted that editorial changes to Paragraph V -
Section I of SAP-15 are needed to clarify the intent of that section.
l It is not our intent to utilize on-the-job training as the major basis for overall qualification of operating personnel. This program is intended to be used to train operations personnel to perform relatively simple tasks under situations where formally i
trained personnel are not available. We believe that these methods meet the requirements of ANSI N18.1-1971 and will provide a satisfactory amount of training so that the related tasks can be accomplished in a safe manner.
l
4 .
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NRC Inspection 81-16 -
Additional Information Page 3 Should you have any further questions, do not hesitate to contact me.
Very trul yours, J. . arey Vice President - Nuclear Attachments i
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, D. C. 20555 b
,1 t
,, , - - _ , _ .-, _ - -- - --.,. -,-, . - _ - - - ~ , - - - , , - - , , , - - - - - - . m .- - w - ,--p m - , -- n-
4 4
DUQUESNE LIGHT COMPANY ATIACHMC E "A" Nuclear Support Services Department Page 1 of 2 August 24, 1981
! MNS:024 Training on Shift Mr. T. D. Jones:
Trainees assigned to plant operations for on-the-job j
training in preparation for licensing or qualification as 4 " Auxiliary" ators duringOperators, should normally not be used as oper-the training period. In the event that they are required to perform certain functions, the trainee may be instructed on-shift, provided the training received is documented, utilizing the Employee Qualification Statement, Figure 0.2.
The sheet shall identify the portion of or component 3
in the system in which training was provided, the student's
! name, received. the date, and a brief description of the training A licensed operator / supervisor's signature is required, noting the trainee is qualified to perform the task. A Training Sheet and also sign the form.
Instructor will review the Checkoff in ourI discussion believe the on above August addresses
- 18. areas of concern noted
/ .
F MY/
J. Bissert Attachmen t cc: J. V. Vassello I
---,,~ _ . _ . . _ _ ._.~._, - - _ . - - . - . , _ _ - - -_ . . . _ _ _ . . _ , _ . . _ . , ,
l' .- .
DUQUES::E LIGHT COMPANY Fig. 0.2 Beaver Valley Poacr Station Training Manual ATDCHME:7I "A"
- 98 Of
- EMPLOYEE QUALIFICATI_ON ST ATEM ENT Employee Name/ Number Course Title (1) Completion Date Employee Job Title Ralph Code Description of Instruction
- (1) 1 I
t i
Description of Tasks: (1): -
t i
Reason / Requirement for Instruction:
i This qualification is conditional and limited by the following waivers or physical limitations. (If no restrictions, state "None ")
i e
Employee qualified to perform spacific tasks noted above. Supportive documentation attached.
cc: Manager Nuclear Operators Manager Nuclear Support Services Signature of NSS, NSOF, or i Individual Sta f f Supervisor Person Responsible for Trng.
Reviewed:
Supervisor of Training (1) If course or training is not described in TM-1, a description of instruction completed must be provided under " Description"
OCQUI5:i! I. 0C COMPANT 3eaver Valley Power 5:szien - Uni: 1 ATIAOCCTr "B" APPROVAL SEZIT - ADM*'T*SUAT M Page 1 of 14 STATICN ADMI!TISTRAT!"E PROCEDURIS Chapter 15 , ri:la Evaluation of Job Performance OSC Rev. Reviev OA Review Acereval Effective No. Pages Issued Da:e Ini:ialsi Date i Sienature i Da a i Date 0 1 -11 4/
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3esvar Valley Power 5:2:1on - Uni: 1 ATUONE27T "B" Sta:1on Ad-*-ds::a:1ve ?:ocedures Page 2 of 14 i
1 LIST OF :.:: C"'T ?ACIS Chap::: is Ti:le Evaluation of Job Perfor ance Page No. Rev. No. Effee:1ve Date Psee No. Rev. No. Effee:1ve Date 1 1 5/21/82 2 1 5/21/82 3 1 5/21/82 4 1 5/21/82 5 1 5/21/82 6 1 5/21/82 7 1 5/21/82 8 1 5/21/82
- 9 1 5/21/82 10 1 5/ 21 /82 11 1 5/21/82 I
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ATIACEMNT "B" Page 3 of 14 Beaver Valley Power Station Station Administrative Procedures Chapter 15 EVALUATION OF JOB PERFOPS.ANCE Chepter Index Page I. PURPOSE 1
II. APPLICABILITY 1
III. FREOUENCY l
IV. DEFINITIONS 1
A. Evaluation of Job Performance 1 B. Quality of Work 1
C. Quantity of Work 2 D. Job Knowledge 2 E. Critical Incident 2 7 RESPONSIBILITIES 2 A. Operations Supervisor 2 B. Operations Support Coordinator 2 C. Maintenance Supervisor
- 3 D. Maintenance Support Coordinator 3 E. Supervisor I:.strumentation and Controls 3 F. Instrumentation and Controls Sup> ort Coordinator 4 G. Supervisor of Testing and Plant Performance 4 H. Coordinator of Station Study Projects 4 I. Director of Nuclear Division Training 4 J. Evaluator 5
.. REFERENCES 5
VII. INSTRUCTIONS 5
A. General 5 B. Mechanics of Preparing Work Incident Sur: nary (Form A) 5 C. MechJ.nics of Preparing the Perfo::ance Review i
L (Form B) 5 D. Evaluation Review and Processing 6 E. Guidelines for Evaluation of E=p syee 6 F. Guidelines for Review of Evaluation with j Employee 7 Section A Work Incident Su ary .
8 Section 3 Perfor=ance Review 9 Page 111 of 1. ' Revision 1
BVPS - AP Chapter 15 ATrICDETE "B" EVALUATION OF JOB PERFORMANCE Page 4 of 14 I. PURPOSE The purpose of the Evaluation of Job Perfor=ance is to:
- 1. Provide for periodic evaluation of station Testing and Plant Pe rfo rmance, Maintenance, Instrue.entation and Control, and Operations job personnels performance in relationship to specific related standards.
2.
Provide a means for objective feecback on job performance to management.
3.
Provide for accumulation of data for use in determining individual and group deficiencies, strong points and knowledge and attitude trends. This data will be incorporated into training, and/or in an immediate on shift correction of an identified deficiency.
4 II APPLICABILITY This evaluation is to be used by the Testing and Plant Performance Supervisor, the Operations Supervisor, the Instrument and Control Supervisor, Maintenance Supervisor, and all designated subordinates in performing evaluations of all person:e1 under their responsibility.
III. _FREOUENCY i
The Evaluation of Job Performance is to be performed for each applicable employee at a minimum annually, and should be performed l in the event defined of an individuals in Section involvement in a Critical Incident as IV of this chapter.
IV. DEFINITIONS A. Evaluation of Job Performance A standard process used to analyze a series of documented subjective evaluations and to arrite at an objective indicator of an employees performance level.
B. Cuality of Work The nature or character of an indisiduals performance.
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BVPS - AP Chapter 13 ATTACHE 2,7 "B" E7ALUATION OF JOB PERFORMANCE (Continued) Page 5 of 14 C. Quantity of Work The amount or number of projects, operations or evolutions an individual may be involved with.
D. Job Knowledge The familiarity, awareness, or understanding of job related projects, operations or evolutions, possessed by an individual, gained through experience or study.
E. Critical Incident An action, either taken, or not taken by an individual which illustrates either outstanding or unsatisfactory job performance.
V. RESPONSIBILITIES A.
Operations Supervisor (Supervisor Nuclear Station Ooerations)
The Operations Supervisor is responsible to the Station Super-intendent for ensuring that annual Evaluations of Job Performance are conducted for each person assigned to the Plant 03erations Croup. He personally conducts evaluations of thoes individuals assigned as Shift Supervisors (Nuclear),
Radioactive Wer*.e Disposal Coordinator, Operations Support Coordinator, and in turn assigns appropriate subordinates for the performance of evaluations for the remainder of the Operations Group. He will review the results of all evaluations performed.
The Operations Supervisor additionally is responsible to ensure any group deficiencies or trends are identified to the Director of Nuclear Training Division for specific upgrading program incorporation into the requalification program.
B. Operations Supeort Coordinator The Operations fupport Coordinator is responsible to the l
Operations Supervisor for the collection of completed Evaluations of Job Performance, and appropriate distribution and filing of the evaluations in accordance with prevailing company policy. He will maintain a supply of Evaluation of Job Performance forms for issue to applicable persons upon request.
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3VPS - AP Chapter 13 C. Maintennnee Suoervisor 1s is responsible to the Station Superintendent for ensuring that annual Evaluations of Job Performance are conducted for each person assigned to the Instrument and Controls Group. He personally conducts evaluations n! those individuals assigned as Senior Instrument and Controls sintenance Engineer, Senior Instrument and Controls Calibration Fagineer, Lastrument and Control Coordinator, and in turn assigns
- ppropriate subordinates for the performance of evaluations for n.he remainder of the Instrument and Controls Group. He will review l ihe results of all evaluations performed.
1 .
' The Supervisor of Instrumentation and Cont ols additionally is tesponsible to ensure any group deficiencias or trends are identified
' to the Director of Nuclear Training Division for specific upgrading program incorporation into the periodic training program.
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SVPS - AP Chapter 15 E'.'ALUATION OF JOB PERFORMANCE (Continued)
Page 7 of 14 F.
Instrumentation and Controls Suenort Coordinato r The Instrumentation and Controls Suppor: Coordinator is re-sponsible to the Instrumentation and Controls Supervisor for -
the collection of completed Evaluations of Job Performance and appropriate company distribution and filing in accordance with prevailing policy.
He will maintain a supply of Evaluation of Job Performance forms for issue to applicable persons upon request.
G. Suoervisor of Testing and Plant Performance
)
The Supervisor of Testing and Plant Performance is responsible l'
to the Station Superintendent for ensuring that annual Evaluations j of Job Performance are conducted for each person assigned to the Testing and Plant Performance Group. He personally conducts evalua-tions of those individuals assigned as Senior Testing Coordinators, Csordinator of Station Study Projects, and in turn, assigns appropriate
.csordinates for the performance of evaluations for the remainder of the Testing and Plant Performance Group. He will review the results of all evaluations performed.
The Supervisor of Testing and Plant Perforrance additionally is responsible to ensure any group deficiencir.; or trends are
' identified to the Director of Nuclear Tr.uning Division for j
specific program. upgrading program incorporation into the periodic training H. Coordinator of Station Study Projects i
Ine Coordinator of Station Study Projects is responsible to the
'upervisor of Testing and Plant Performance for the collection of completed Evaluations of Job Performacce and appropriate distribution and filing in accordance with prevailing company policy.
He will maintain a supply of Evaluation of Job Performance i
forms for issue to applicable persons up)n request.
l I.
Director of Nuclear Division Training The Director of Nuclear Divisien Trainin:; is responsible for ensuring group deficiencies or trends id.istified to him by the various Group Supervisors are incorporacol into applicable training programs, or in the case of Operations Group, Operator Requalification Training, as specific upgrading progra=s.
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BVPS - AP Chapter 15 ATTTGETI "B" EVALUATION OF JOB PERFORMANCE (Continued) Page 8 of 14 t
J. Evaluator The individual assigned by an applicable Group Supervisor is responsible to conduct an Evaluation of Job Performance for the person he has been assigned.
He will conduct the evaluation in accordance with this procedure, prepare and process performance ratings sheets (form A and B attached), and will conduct a post evaluation interview with the individual.
1 i VI. REFERENCES
71!. INSTRUCTIONS A. General 4
- 1. Form A (Attached) is used to record pertinent administrative data, the reason for the evaluation and any comments or recommendations reached as a result of the evaluation.
2.
! Form B (Attached) provides criteria for evaluation of job performance and specific areas to which these criterion will be applied.
B.
Mechanics of Preoaring Work Incidett Summarv (Form A)
- 1. Fill in the heading of the foLa as follows:
- a. Record Employee's Name, Job Ittle, and Number.
I
- b. Record date of work incident. (If evaluation is being 1
performed as a periodic requirement, record N/A).
c.
- Record date of initial evaluation and date the form is prepared.
- d. Record a brief description of the incident, or reason for this evaluation. (If this evaluation is being performed as a periodi: requirement, record " Periodic Review") .
t
! C.
Mechanics of Preoarine ,1,ha Performance Review (Section 3) .
i
- l. Fill in the heading of the form as follows:
- a. Record e=ployee 's name and nunber.
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- b. Record employee 's job title, date evaluation is performed.
I and the na=e of the individual performing the evaluatien.
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. l EVPS - AP Chapter 13 ATIX2 BENT "B" EVALUATION OF JOB PERFORMANCE (Continued) Page 9 of 14
- 2. Fill in the Evaluation Rating as follows:
j j a. Determine the description of behavior most applicable to the area of review in question per the Performance '
Rating Guide.
- b. Record this number in the space provided.
- c. If an explanation of the description selected is
(
necessary, mark the appropriate column and record the comment in Secticn A beneath the heading " Comments".
' of Review", merk the appropriate column and record explanation in Section A under the heading
" Comments." -
D. Evaluation Review and Processing i
1.
Review the comments and overall evaluation with the j individual in accordance with Section VII.F of this
' procedure. This review will include any immediate
- corrections of identified dificiencies.
- 2. Sign the Evaluation of Job istformance.
3.
Submit the final Evaluation of Job Performance to the applicable Group Support Coordinator.
i '
! E. Guidelines for Evaluation of Emplovee i
t
- 1. The evaluation should be limited to the time period or incident covered by the rating. It is not good practice to review old evaluation sheets until the current evaluation is complete. The rating sh
- 21d reflect the employees performance for the current seriod and the evaluators review l
could be biased by reviewini data from outside the period.
[ 2.
' The evaluator must employ diseplined thinking so as to rate the employee on each " Area for Review" separately, and not allow his decision on one area sway his decision on others.
- 3.
- The evaluator should determine his personal prejudices towards the employee and exercise caution that these prejudices good or bad do not interfere with an objective i
evaluation of e=ployee.
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BVPS - AP Chapter 15 ATU O M2.T "B" EVALL'ATION OF J03 PERFORMANCE (Continued) 4 When deter =1ning the description of behavior most applicable the evaluator must bear in mind the e=ployees Quality of Work, Quantity of Work, and Job Knowledge. .
F. Guidelines for Review of Evaluation with Emoloyee
- 1. The review should be conducted in private.
- 2. The review should be conducted as soon as possible after 4
the evaluation is performed.
- 3. The evaluator should point out strong points as well as weak areas, and should offer recommendations for improve-munts in areas identified as needing improvement. He will institute immediate on shift corrective action of any identified deficiency.
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BVPS AP Chapter 15 A MAEtTr "B" EVALUATION OF JOB PERFORMANCE Page 11 of 14 SECTION A - UORK INC!nENT SLW.ARY NOTE:
Significant work incidents of employees - both satisfactory and unsatisfactory should be recorded as follows:
Employee's Name Job Title Employee No.
Date of Work Incident Date of Talk with Employee Date of this Report Description of this significant work incident or review:
Comments (Data from talk with employee and special recommendations)
NOTE:
Record data of this significant work incident on " Performance Review" report opposite specific job characteristics which'are specifically related to this work incident.
Signature of Evaluator Page S of L; Revision 1
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BVPS AP Chaptar 15 ATIX2MT7I' "B" EVALUATION OF JOB PERFOPS.ANCE Page 12 of 14 SECTION B - PERFOP3ANCE REVIE*4 PEPJORMANCE RATING GUIDE
- 1. Poor judgment, needs constant supervision Employee 's Name/Numoer 2. Must be checked closely, difficulty in application ~
- 3. Avoids responsibilities, cooperation fair 4 Adequate, understands p.:11cies Job Title 5. Satisfactory, needs occasional supervision
- 6. Usually accurate and dependable, constructive Evaluation Date 7. Good judgment, good leader, thinks independently 8.
Well informed, consistent, keen and original, plans well
- 9. Willing to be held accountable, maintains consistent Evaluator controls
- 10. Self starter, recogniaed authority, excellent, dynamic, outstanding (vo M l Evalu '
i s ation g u u *]
AREA 0F REVIEW o a- yu Rating 2y i3 l
A. PROCEDURE COMPLIANCE ' (1-10) o .9 " l
- x. Adherence to . . . . . . .. . . . . . . . . . x
- y. Attitude toward . . . . . . . . . . . . . . y B. SAFETY
- x. Ut111aation of . . . . . . . . . . . . . . . x Attitude toward l y. .
. . . . .. . . . . . . . . y l
C. SECURITY 1
}
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- x. Compliance with
.. . . . . . . . . . . . . . X e
, y. Attitude toward ... . . . . . . . . . . . . 'y 1 i
! D. RADIOLOGICAL CONTROLS ,l ,i i , t 1
1 -
- x. Application of . '
. . . . .. . . . . . . . . . . x ,I -
1 l
- y. Attitude toward i l
. . . . . . . . . . . . . . . y ;
E. TRAINING
- x. Co= prehension of .
. . . .. . . . . . . . . . x i
- y. Attitude toward . . . . . . . . . .. . . .
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BVPS - AP Chapter'13 EVALUATION OF JOB PERF0PMANCE SECTION 3 - PERFORMANCE REVIEi4 NENT "B" Page 13 of 14 PERFC2&ViCE laTING GUIDE
- 1. Poor judg=ent, needs constant supervision Employee 's Name/ Number 2. Must be checked closely, difficulty in application 3.
Avoids responsibilities, cocpe' ration fair 4 ?>.dequate, understands :mst policies Job Title 5. Satisfactory, needs occasional supervision '
- 6. Usually accurate and dependable, construc':ive
- 7. Good judgment, good leader, thinks Evaluation Date independently '
- 8. Well informed, consistent, keen and origitral, plans well
- 9. Willing to be held accountable, maintains Evaluator consistent controls
- 10. Self starter, recognized authority, excellent, dynamic, outstanding W V) iEvalu-
'a tio n Jw 'ys j AREA 0F REVIE'4 m .; , - .v. - . _
Rating -c a EO (1210) ' * $ l. S " . _
F. HOUSECLEANING
- x. Exercise of . . . . . . . . . . . . . . .. . . x
- y. Attitude toward . . . . . . . . . . . . . . . . y G. WATCH STANDING -
l
- x. Alertness . . . . . . . . . . . . . . . . . . x i i
- y. Attitude toward . . . . . . . . . . . . . . . .
I
- y E. LOG TAKING !
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- x. Adeptness I i
. . . . . . . . . . . . . . . . . . ,x {
- y. Attitude toward . . . . . . . . . . . . . . . .
i
'y I. ADAP~ABILI'"Y i t
- x. Accepts and promotes change . . . . . . . . . . 'x l
t i
- y. Attitude toward change . . . . . . . . . . . . ;y i s
3 J. LEADERSEIP
, x. Ability to lead .
J
. . . . . . . . . . . . . . . 'x
- y. Attitude toward . . . . . . . . . . . . . . . . y -
/
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BVPS-AP Chapter 15 Id"4OECT "B" !
EVALUATION OF JOB PERFOPyE'CE Page 14 of 14 SECTION B - PERFOUAiCE REVIra', I PERF0Py.ANCE RATING GUIDE E=ployee 's Name/Nu=oer 1. Poor judgment, needs constant supervision 2.
- 3. Must be checked closely, difficulty in applicatio Job Title 4.
Avoids responsibilities, cooperation fair Adequate, understands most policies 5.
6.
Satisfactory, needs occasional supervision Evaluation Date Usually accurate and dependable, constructive 7.
- 8. Good ,,udgment, good leader, thinks independently Well informed, consistent, keen and original, plans well
- 9. Willing to be held accountable, maintains Evaluator consistent controls 10.
Self starter, recognized authority, excellent dynamic, outstanding (d (4 Evalu- ,e ,
AREA 0F REVIEW ation v @
Rating w E "Ni (1-10) SE 53
$ EE K. Coch1 TION
- x. Job Knowledge .
. . . . . . . . . . . . . . . . . x
- y. Job Initiative . . . . . .. . . . . . . . . . y L. DECISION MAKING I
! x. Ju dgment.
. . . . . ... . . . . . . . . .. . . x l y.
Acceptance of Responsibility . . . . . . . . . . fy ,
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ATDGMENT "C" Page 1 of 2 1
Only qualified individuals shall be assigned to perform safety-related operations duties. Qualification to perform safety-related operations may be obtained and documented by successful completion of the appropriate training as set forth in the BVPS-TM -
or by on-the-job training documented on the attached Employee Qualification Statemen.t.
The content of "on-the-job" training for performance of an operations task involving safety-related equipment shall be determined by a qualified Operations Supervisor. A training plan will be prepared to provide guidance to the Trainer. The Trainer shall be a person qualified to perform the task and shall instruct the individual in the proper performance of the task. The Trainer shall complete the Employee Qualification Statement form and shall attach the Training Plan and other specific items not covered on the form. The Trainer shall determine through questioning and/or demonstration that the Trainee understands the training received and is qualified to perform the task for which instruction was j given. By his signature on the Employee Qualification Statement i
form, the Trainer certifies that the training has been given as described on the form and its attachments and that the Trainee
' has been examined and found to possess a satisfactory degree of knowledge to perform the task. The Employee Qualification Statement form and attachments shall be sent to the Director, Nuclear Training, for review and inclusion in the training records.
The Evaluation of Job Performance form, as described in SAP Chapter 15, shall be utilized to determine the long-term effectiveness of training.
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194 C4,CC1.002 , , l-DUQUESNE LIGHT COMPANY.' Figure 0.2 Beaver Valley Power Station Training Manual g g ,,C" EMPLOYEE QUALIFICATION STATEMENT a@ f2 Employee Name/ Number i Course Title (1) Completion Date
! Employee Job Title Ralph Code Dascription of Instruction:
Dascription of Tasks:
Re.ason/ Requirement for Instruction:
This qualification is conditional and limited by the following waivers or physical limitations. (.If no restrictions, state "None").
Employee qualified to perform specific tasks noted above. Supportive documentation atteched.
ces Manager Nuclear Operations Manager Nuclear Support Services Signature of NSS, NSOF, or Individual Staff Supervisor
. Employee's File Person Responsible for Trng.
Reviewed by:
Supervisor of Training (1)
If course or training is not described in TM-1, a description of instruction-completed and assigned task must be provided.
f 0.9 ISSUE 3
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