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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] |
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2NRC-4-078
= (412)787 - 5141 (412) 923 -1960 Telecopy (412) 787-2629 Nuclear Construction Division June 13, 1984 Robinson Plaza, Building 2. Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. George W. Knighton, Chie f Licensing Branch 3 Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Outstanding / Confirmatory Issue Response Gentlemen:
This le t ter fo rward s res pons es to the issues listed below, diich were discussed at a meeting with the Radio logice' As ses sme nt Branch .
Duquesne Light Company plans to incorporate the res po ns es as indic a ted in each attachment into FSAR Amendment 8. The following items are attached:
Attachment 1: Response to Confirmatory Issue 12 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report At tachment 2: Response to Confirmatory Issue 13 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report At t achment 3: Response ta Confirmatory Issue 14 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Attachment 4: Response to Confirmatory Issue 15 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report At tachment 5: Response to Confirmatory Issue 16 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Attachment 6: Res ponse to Out standing Issue 95 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Att achment 7: Res pons e to Outstanding Issue 96 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report
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8406190191 840613 PDR ADOCK 05000412 g t
E pop lI
. United Stctes Nuclear R:gulatory Commission Mr. Georga W. Knighton, Chief Page 2 At tachment 8: Res pons e to Out standing Issue 97 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Attachment 9: Technical Specifications DUQUESNE LIGHT COMPANY By . . [
E. J M Wo'olever Vice President GLB/wjs At tachment cc: Mr. H. R. Denton, Director NRR (w/a)
Mr. D. - Eisenhut , Director Division of Licensig (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
Mr. M. Licitra, Project Manager (w/a)
Ms. M. Ley, Project Manager (w/a)
COMMONWEALTH OF. PENNSYLVANIA )
) SS:
COUNTY OF ALLEGHENY )'
On this /8 k day of y, _, /f/ , be fo r e me ,
a Notary Public in and fo r said Commonwe alt h and County, pe rsonal ly appeared E. J. Woolever, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execut e and file the foregoing Submit t al on behalf of said Company, and (3) the s t ateme nt s set fo rt h in the Submittal are true and correct to the best of his knowledge, f Nu ) 1 Not ary Pub lic ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPlRES OCTOBER 20,1986
j' '
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ATTACHMENT 1 Response to Confirmatory Issue 12 of the j Beaver Valley Power Station Unit No. 2 !
Draf t Safety Evaluation Report i
Draft SER Section 12.2.1: By-product, Source, and Special Nuclear Material Description (Excerpt)
A description of by product, source and special nuclear material of cons ideration in plant shielding design will be provided seven to nine months before fuel loading (Q471.14).
Response
l r
I r l The need for procurement of sources beyond those now in use at BVPS-1 has not been fully determined. Seven to nine months prior to fuel load- ,
ing, a description of by product , source , and special nuclear material !
that requires shielding design considerations will be provided. A list- !
ing of isotope, quantity, form, and use of all special nuclear material exceeding 100 millicuries and requiring shielding design considerations l will also be provided. This information will be included in the FSAR in !
accordance with Regulatory Guide 1.70, Revision 2..
l
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- - _ . - - _ . __ - _ _ __..____ _ ____ _ __ ___.-_-,_ _ _______._ _ _ _ ,._ . _ _ _ _ _ _ . _ _ . _ - ~ _ . _ . . _ - _ _ J
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- i ATTACHMENT 2 Response to Confirmatory Issue 13 of the Beaver Valley Power Station Unit No. 2 ;
Draft Safety Evaluation Report j Draf t SER Section 12.3.1: Verification that Cobalt use in Primary System has f been Minimized (Excerpt) l t
i The ap plic ant 's corrosion product control fe atur es are cons istent with i the guidance of Regulatory Guide 8.8 and are ac cept able , although con-firmation that the basic plant design reflects an ef fort to minimize the ,
cobalt content of materials used in primary systems is needed (Q471.10).
Response
l FSAR Section 12.3 and the response to Question 471.10 will be revised as !
shown on the attached pages. ;
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- - -...--.,-,,-,_.,-w.,,- - , - - , , .- - - -en-- _ . ,, , . , - - - , , , . . - . - . .-- . , - - - , - - - - - , , - - - - - - ,
. s BVPS-2 FSAR ,
Remote handling equipment.is provided for removing filters ,
from the filter vessels and for placing them into shipping (,!j containers. Contact operations in high dose rate areas are ,
minimized. !
The solid waste system is essentially a remotely operated ;
system. Operations are conducted remotely or manually after '
the waste source has been shielded. ;
stations for potentially radioactive valves are, in general, l arranged either in shielded cubicles away from the equipment i 1
served and/or are provided with reach rods. The ;
demineralizer and filter valves are in cubicles below and adjacent to the vessels and are also provided with reach j rods. !
i
- 17. All features for radiation control are designed to !
accommodate maximum expected failures such as fuel element i cladding failures and steam generator tube leaks. l l
Design features such as shielding- and radiation zones i accommodate clad defects for 1 percent failed fuel and primary to secondary steam generator tube leaks of 144 gal / day. ,
- 18. Sampling. sites are located. so exposures will be ALARA during such routine operations, as sampling off-gas, primary ,".. '
coolant, and liquid waste. ' '
I A sampling room is provided for the remote taking of routine [
-samples from points in the ' reactor and auxiliary systems with the- exception of the samples from the evaporators. '
Sample points for the evaporators are provided with a sample sink and ventilation hood, splash screen, and valves located
' outside the splash screen. The samples are provided with a :
recirculation path behind the shield wall at the sample sink with reach rods for the operator. A shielded sample station is also provided. for solid waste streams (for example,
, i l
evaporator bottoms, resins and sludges). ;
- 19. Redundancy of equipment is utilized in the plant design to - ,
facilitate ALARA by allowing longer holdup time .between .
f I
scheduled fluid processing r.ad by reducing the urgency for accelerated equipment repair. Redundant radwaste ,
solidification drum inspection / labeling stations permit i processing more drums in shorter periods of time to reduce ,
individual exposure to radioactive sources.
/ I
,- I o S eWLT .L } .,
12.3-8 May 1983 Amendment i t:
BUPS-2 FSAR Two safeguards recombiner area monitors are provided outside the cubicles in which the post-DBA hydrogen recombiners are located. ,
a A list of area radiation monitors and their locations, sensitivities, and ranges is presented in Table 12.3-10. The sensitivity of each L
monitor is the lower value of the monitored range.
12.3.5 References for Section 12.3 Stone & Webster Engineering Corporation (SWEC) 1975. Radiation Shielding Design and Analysis Approach for Light Water Reactor Plants. Topical Report RP-8A, Boston Mass.
SWEC 1981a. QADMOD - Point Kernel Gamma Transport. NU-137.
SWEC 1981b. ANISND - A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering. NU-146. T SWEC 1981s.. COHORT 2 - Monte Carlo Radiation Environment Aitalysis.
NU-157.
SWEC 1982. GAMTRAN1 - Gamma Transport by Point Kernr1 Technique.
NU-003.
U.S. Nuclear Regulatory Commission 1980. Clarification of TMI Action
, Plan Requirements. NUREG-0737. ,
p4 O
TnsEAT '2 -
i
\
- aa> .
i Amendment 3 12.3-32 October 1983
c _.- --
4 l
INSERT 1
- 20. Materials
'- Equipment specifications for component s in the nuc le ar steam supply
-system contain specific limitations on the cobalt impurity content of the base metal as given in Table 12.3-11 thereby controlling the poten-tial -for production of radioactive cobalt-60 from the base metal impur-ity cobalt-59. The estimated surf ace area of material in contact with i the reactor coolant is given in Tsbie 12.3-11. The use of hard facing material with cobalt content such as stellite is limited to applications where its use is necessary for reliability considerations. Table 12.3-13 shows the es timated tot al surface area of stellite in the nucle ar stema supply sys tem. Nickel based alloys in the nuclear steam supply l
system (cobalt-58 is produced fra activation of the base metal nickel-
- 58) are similarly used only when component reliability may be compro-mised by the use of other materials. The major use of nickel based alloys in the nuclear steam supply system is the inconel stema generator tubes. The surface area in contact with the reactor coolant sys tem is given in Table 12.3-12. Fram Tables 12.3-12 and 12.3-13, it can be seen that. the inconel surface is the predominate area in contact with the reactor . coolant systen and. that the stellite area is minimal. A further discussion of material considerations is given in Westinghouse (1977).
I INSERT 2 i
Westinghouse 1977. " Design, inspection, operation, and maintenance as pect s of the Westinghouse NSSS to maintain occupational radiation exposures as low as reasonably achievable," WCAP 8872, April 1977.
t f
f, a
. T ABLE 12.3-il EGU!PMENT SPECIFICATION LIMITS FOR COSALT iMPUHf1Y LEVELS Maximum ,
Camponent Materlot" Weloht Purcant Cobol,t, Reactor interneels (nnnactive region) 55' U.20 Reactor internals (w:tiva region) 55 0.12 -
Reector vessel clad SS 0.20 -
Reactor cuolent piping 55 -
0.70 Reector internal botting (natcrial SS , 0.25 Remetnr enoient pumpe SS 0.20 55 0.20 Pressurizer Auxillery host exchanger surfnewe vaposed to reactor coolant SS . 0.20 Stasm generatore Incunal 0.10 - ,
Fuel (mmactive region) 55 0.12 Fust(active ruginn) SS 0.08 Fuel Inconel 0.13 Zircoloy 0.007 Fuel
'55. Staininas steel 5
9 e
e m.ei %
W - 9s--=
+--,w,aw
~
J. -
4 o
TAOLE22.h IJ. .
APPROXIMATL MLACiOR COOL ANT SYSTFM WFTTfD StJRFACf' AREAS .
Surfnen Arna Component gterlot (ft2)
Rwwetne intornote ,
55* 4276 Remstor vagoni elarf SS 2190 Remeter coolant plpirwJ 55 775G ,
Rosetor internal 14ultitwJ material .55 Negligihte
Negligtble Aumillary twmL cachassler surfaces facef,t, l: Negllgibin Stoom generotore ,
inconel 1.90 x 105 fuel (pannetive region) $$ 2000
+ Fuel (active region) $$ 3600 Fuel Inconel 7.A0 r 10)
Fuel Ilrentny 7.76 a 104 1
e i
i 4
855 - Slainlane steal I
d 0
- - w - d T
e TAult.173= l1
, APPROX!M.A.lt - . RF ACTOR COOL ANT. . SYSTEM.- ..W. F.TTrn 91 sRf ACC AftCA OF STELLtTE I
Surface Areo (ft2)
(otnoonent Reactnr Internett J.2 Reacter vuelant pump juvenals 17.2 .
Content rud delve mechantmma 10.0
Meactne coolent nyetem vulvue 2.4 4
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t BUPS-2 FSAR NRC I.etter: August 31, 1983 i
I Question 471.10 Discuss how material selection and water chemistry control will be !
utilized at BVPS-2 to reduce the production, distribution, and i retention of activation products.
i Responses Material, selection for components in the reactor coolant system is l discussed in Sections 4.5, 5.2.3.1, 5.3.1, 5.4.2.1, and 5.4.3. Water chemistry control and reactor coolant purification are discussed in i Sections 5.2.3.2.1 and 9.3.4.
F Use of corrosion-resistant materials, implementation of water i chemistry monitoring procedures to control the oxygen content and ,
impurities in the reactor coolant system, and continuous purification !
of the reactor coolant letdown through cleanup systems reduces the production and retention of activated solid corrosion products. The ;
chemical and volume control system is designed to provide an effective means for removing these corrosion products from the ,
i primary coolant, as discussed in Section 9.3.4. i REFE4% AEVt6ffD sac.wed 2.. & , i, t. F6 A 41:se.ussied bv c.o&4t.T cont w r na _.
pro msk' .s ysrtni i
M4764.lALS.
N l
i Q471.10-1 October 1983 Amendment 3
_. .a___._...__ . _ . _
ATTACHMENT 3 Response to Confirmatory Issue 14 of the Beaver Valley Power Station Unit No. 2
Draf t Safety Evaluation Report T
Draft SER Section 12.3.4.1: Cont ainment High-Range Radiation Monito rs (Excerpt) l i
Additional information regarding cont airunent high-range-radiat ion monitors (NUREG-0737, Item II.F 1(3]) needed to complete the review will ;
be provided by the applicant (Q471.14). j k
4
Response
FS AR Table 12.3-10 has been revised to provide the missing information >
related to cont ainment high-range radiation monitors as shown on the ,
attached page. the res ponse to ques tion 471.14 will be revised accordingly.
t I
t l
I i
. - . - . - . - . , , . - _ . - , - _ ,.- .,,-_--,v___,..,.- _ _ , , ,. _. _ . . . , , , _ , . _ . _ - . , _ - - . . _ _ - . , , , , , _ , _ _ . - . . ._,..n-. , ---,_-_
., .. , , , .- e v BVPS-2 FS.'
,g TABLE 12.3-10 AREA RADIATION MONITOR LOCATIONS AND RANGES Sensitivity and Detector Location Range * (mrem /hr)
Reactor containment area, low range 1-105 Outside personnel hatch area 1-107
) Reactor in-containment area, high range 103-1018 Manipulator crane 1-105 In-core instrumentation area 1-105 Decontamination area -
0.1-104 .
New' fuel storage area 0.1-104 Fuel pit bridge 0.1-104 Auxiliary building 0.1-10+
,6, Sample room 0.1-10+-
Waste handling area s 0.1-104 Condensate polishing area 0.1-104 Control room 10-2 103 l Safeguards recombiner area 1-105 NOTE: ,
- Sensitivity is equal to the lower value of th range.
Amendment 3 1 of 1 October 1983 w
[
ATTACHMENT 4 \
r Response to Confirmatory Issue 15 of the Beaver Valley Power Station Unit No. 2 i Draft Safety Evaluation Report i
i i
Draft SER Section 12.3.4.2: Airborne Radioactivity Monitors (Excerpt) [t I
The applicant will ins tall airborne radioactivity monitoring sys tass !*
(RMS) in work areas dere there is a potential for airborne radioactiv-icy. Visual and audible alarms are provided in the main control roam for these monito rs . The licensee should verify that the RMS airborne monito rs have the capability to de tect 10 mye hours of part iculate and iodine radioactivity in any compartment that has a possibility of con- -
taining airborne radioactivity and that may be occupied by personnel. l The applicant will provide portable continuous air sanitors den needed !
to monitor air in areas not provided with fixed airborne radioactivity monito rs . Airborne Radioactivity monitors will be calibrated at regular time intervals as required in Technical Specifications. j i
Response: ,
j -
i FSAR 12.3.4.1 provides the requested information. A calculation has been performed to confirm the capability to detect 10 spc hours. ;
I L
4 i
f t
t r
t h
4 e
-- -. ~
ATTACHMENT 5 Response to Confirmatory Issue 16 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Draft SER Section 12.5.3: Quality Assurance Program Requirements (Excerpt)
Verification that quality as surance requirement s related to radiation protection have been implemented at Beaver Valley 2 in accordance with Regulatory Guide 1.33, " Quality Assurance Program Requirements," should be provided.
Response
FSAR 12.5.3 will be revised as shown on the attached page.
l I
i
. - - - . . - . - . . - . . . - _ . - - - - - . - . , . .._,._- - .- . , . _ , , - . _ - , . - - - - - , - . - , . - . . . . , . - ~ - - , - . -
BVPS-2 FSAR The. radiological limits, controls, and policies as described in the l Id Radeon Manual will be consistent and in compliance with the N/
/3 recommendations and requirements of applicable federal and state l
.) regulatory agencies. In accordance with both company and station 0 and o administrative policies, compliance with the controls. limits, E k requirements of the Radeon Manual will be mandatory.
o,e g 3 The Radeon Manual will be supplemented by other work procedures to g 4 => assure that abnormal or unique work practices and/or operations are y $ conducted in accordance with the Radeon Program. This will ensure ,
oc N standards and limits specified therein ~
are carefully and conservatively followed so that radiation exposures, contamination -
g7 y (surface or airborne) levels, and radioactive waste volumes are ht yE maintained as low .as reasonably achievable and consistent with established requirements.
W' <!.
YgQ The Radeon Manual and other work procedures will contain information on external radiation protection, respiratory protection,, protective y g. O y y clothing, etc; including detailed specifications, qualifications, ,
4 '.1 a precautions, performance limits, and/or controls and any other l 9y 4 information, personnel exposure.
instructions, or guidelines required to minimize !
uo%
2g The Radcon Program, as presented in the Radeon Manual, will be !
$44 e developed in accordance with 10 CFR 20 and other applicable federal 33 g,, & _and state regulations.smRevisions in applicable regulations that are T 3 f F adopted and published in the Federal Register, or are issued in the NRC Regulatory Guides will be evaluated by the Nuclear Division g*p
- Staff, as well as the station staff. If warranted, the Radeon Manual-sl! 4 be revised to be consistent. with the revised rules and d $ .$ will
.t practices.
The Radeon Program and its implementation will be audited periodically by qualified person (s), who are not assigned to the station, to ensure the program is in compliance with existing requirements. Audit findings.will be reported to mangement for their
-information and 'ppropriate action.
12.5.3.1 ALARA Physical and administrative controls will be instituted to assure DLC's philosophy of maintaining personnel exposures as low as reasonably achievable (ALARA) is implemented.
12.5.3.1.1 Physical and Administrative Controls Operation of the plant, as well as certain maintenance and repair tasks, may require access to and work in all areas of the plant. ,
This includes areas defined by 10 CFR 20, as radiation areas and high Amendment i 12.5-10 May 1983 1
i
, -. . . - . - _ _ - - - _ . _ _ . - ~ _ , . _ , -- , - _ . _ , , , . - , . , , , , _ , , , , - _ _ , , . . _ _ . - - . _ . _ _ . . _.-m _ . , . . .
ATTACHMENT 6 Response to Outstanding Issue 95 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Draft SER Section 12.3.4.1: Exemption to 10CFR70. 24(a) and Description of Alternative to Required Criticality Monitors (Excerpt)
The applicant has provided area radiation monitors around the fuel stor-age areas . These do not meet the particular requirements of 10CPR70.24 and the related guidance of Regulatory Guide 8.12 " Criticality Accident Al re Systems:" however, the ap plicant will file for an exemption frcut 10CFR70.24(b) by September 1984 The ap plicant must still provide a discussion of the proposed alternative monitoring methods as reques ted by the staf f (Q471.3).
Response
The response to Question 471.3 will be revised as shown on the attached page.
f BVPS-2 FSAR NRC Letter: August 31, 1983 Question 471.3 DLC has indicated in Table 1.9-2 that'an application for an exemption in from the installation of the criticality monitor required accordance with 10 CFR Part 70.24(b) and Regulatory Guide 8.12 will be filed with the NRC. Provide a commitment date for this action and describe the specific alternative methods to be used in lieu of the required monitors.
Responset The application for exemption will be formally filed as part of the application for a special nuclear materials license which is to be submitted in September 1984. Alternative methods which preclude the need for a criticality monitor include administrative controls for the movement offuelDppropriatedesignoffuelstoragefacilities.,
(to prevane critica nty. and plant security controlsf TH ESC 39tTEAurTIMS
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I ATTACIDENT 7 Response to Outstanding Issue 96 of the Beaver Valley Power Station Unit No. 2 j Draf t Safety Evaluat on Report !
l Draft SER Section 12.5.2: Types, Nude rs , and Specifications fo r Port able {
and Laboratory HP Instruments (Excerpt) i The number and type s of survey equipment , the sensitivity and range , and i details of calibration are needed to complete the staf f's review in this !
area, and the applicant has cosusitted to provide the information. [
f I
Response: ,
Figure 1 (attached) provides an example of the general type and approxi- l mate quantity of tortable and laboratory health physics equipment avail-able at BVPS-1 as of April 19 , 19 84. This table demons trates that i Duquesne Light Company is fully cognisant of the types and nudes of !
equipment required to conduct an ef fective health physics program.
Figure 2 ( attached) provides - tabulation of the general types of po rt able and laboratory equipment dich are expected to be employed for ,
radiological monitoring at BVPS-2. l l
The standard review plan provides no quantitative accept ance criteria ;
for determining the necessary types and quantities of ins trument ation required to support a successful health physics program. With continual ;
improvement s in technology, industry practices , and regulatory require- j me nt s , it is not possible to provide specific acceptance criteria, nor :
is it appropriate to provide a listing of the types and quantities in the FSAR.
i Duquesne Light Company will maintain health physica equipment required :
l to perform radiation and contamination surveys, airborne radioactivity
- monitoring and sampling, area radiation monitoring, and personnel moni- l l
toring during normal operation, anticipated operational occurrences, and l accident conditiona at BVPS-2: The types and quantities of equipment to i i
l be employed at BVPS-2 will be continually changing based upon experience
! In order to improve the efficiency and ef fset iveness of the he alth physics program. l I
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PORTADLE SURVET INSTRtMENTS TYPE METER RANCE M i SEN5tpylTfjgFLClJ(lCT c,,.-ce 0-50.000 CrH Sr-90 Y-90(Eg3g.54-2.ZMev) 451 G-M PANCAKE (FRISKER) 0-60.000 CPM Tc-99(EnAx.29MeV) 30%
C-14 (Eggg.15Mev)10%
Co-60 5000 CPM /mR/hr Cs-137 3500 CPM /mR/hr 0-200 mR/hr WITil!N +20% 40 KcV-1.25 MeV G-M LOW RANGE Cs-131 1200 CPM /mR/hr 0-20 R/hr Co-6019 CPM /mR/hr G-M HIGH RANGE Cs-13712 CPM /mR/hr PROSE: 0-200 mR/hr Cs-137 1200 CPM /mR/hr G-M CUM 8tMAfl0N INTERNAL: 0-2 R/hr Cs-131 100 CPM /mR/hr 0-1000 R/hr 80' kev-200 kev t15%
G-M EXTEN01BLE 0.2 MeV-2 MeV t101 LOW RANGE 0 200 mR/hr 1200 CPM /mR/hr G-M PORTADLE
. M10 RANGE 0-200 R/hr 1200 CPM /mR/hr HIGH RANGE O-10000 R/hr 60 kev-l .3 MeV .
0-5 R/he 7:15% 12 kev-1.3MeV IGN CHAM 8ERS Sr-90. T-90 75% AT 40 cm WINDOW OPEN 8% e.T 40 cm SLIDE CLOSED 0-50 R/hr y tl5% 12Kef-1.3MeV ION CHN1SER$ Sr-90. Y 90 75% AT 40 cm SL10E OprH 8T AT 40 cm SLIOC CLOSED 10N CHAM 8ER 0-1.999 R/he
- 0-199.9 R/hr 60 kev-1.3 MeV t201 -
CITEN0!BLE 0-19.990 R/hr i
0 1
O' 10.000 R/hr
ION CHAM 8ER COUNT RATE MODE: Pu-239 9 CPM /DPM/cm a ALPHA SCINTILLATION ,
0-10.000 CIW SCALER MODE:
6 OtGIT 0-500.000 CPM 50% OF 2 o GEOMETRY FROM 50 cm ALPHA GAS FL0u
=
(Pu-239)
HEUTRON COUNTER 0.2-2G .fs/wr 109 CPM /aree/he .
.LA80RATORT INSTRtmENTS DETECit0N MINIMLM DETECTARLE 3 .
T7PE ACTlvITY (W, fMi .
SINGLE-CHANNEL 6 Dialf SCALER 6.7 a 10-t e vC1/cc (t-131)
ANALYZER , FOR 20 FTs SAMPLE MULit-CHANNEL 1.6 a 107 CPS I a 10*? uCl/cc (Co-60)
ANALYZER FOR 30 MIN. C00fif CAS FLOW PROP 0Rit0 MAL 6 O! GIT SCALER 1.5 DPM ($r-90. Y-90)
COUNTER 6 O! GIT SCALER 7.0 x 10*7 pCl/ml (Co-60)
N4t (T1)
GM 6 OtG1T SCALER A8 OPM (Tc-99)
ALPHA SCINTILLATION 6 O!Gli SCALER 1.35 OPM (Pu-239)
{ f/ &IXLL ~
PORTA 8LE CONTINUOUS AIR MONITOR 5 TYPE RANGE [ n ;} EFFICIENC1 M J G-M 0-50.000 CPM 155, 2 r Sr-90. Y-9C I G-M U-100.000 CPM 50%. Zu Sr-90. T-90 '
i PORTABLE AIR SAMPLERS
+
GRA8-SAMPLERS CONSTANT: 2 CFM VARIA8LE: 0-3 CFM l HIGM V0 LIME 20-30 CFM 8REATHIM ZOK lZ LPM ;
i RESPIRATORY PROTECTION EQUIPMENT !
TYPE
AIR-PURIFYIM - FULL FACEPIECE (MP)
. FULL FACEPIECE (PP)
ATMOSPH( K SUPPLYINE SCBA 'OPEN CIRCUIT (PO)
SC84 CLOSED CIRCulf (RO) ;
L AIR-LIMIL FULL FACEPIECE IPO) ,
FULL FACEPIECE 1,CF)
I huus (GF) !
I NP - NEGATIVE PRESSURE: PP - POSITIVE PRESSURES PO - PRESSURE DEMANO l RO - NECIRCULATING DEMAND', CF - CONSTANT FLOW l
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r ATTACHMENT 8 Response to Outstanding Issue 97 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report t
I Draft SER Section 12.5.3: Training /Retraiing for Health Physics Profes-sionals and Verification that Contractor Training Meets 10CFR19.12 (Excerpt) l Additional infc rmation regarding training for health phys ics profes- i sionals and requalification and retraining programs has been requested I (Q471.5), but the applicant has not provided a satis factory res ponse.
Additionally, the applicant should verify that contractor training is in l compliance with 10CFR19.12 and not merely task oriented. [
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. l Response: ,
Although no regulatory requirements exist for specific training or I retraining of health physics professionals, Duquesne Light Company does ;
provide professional development trainirg for appropriate individuals to assure a proficient health physics staf f. This training is acccuplished thr ough participation in training progemas , seminars , or workshops .
I sponsored by various industry and profe'esional groups. Participation in l
these progress maintains the health physics staf f's level of knowledge !
current with changes in the industry resulting from technological inno- i vations and development s as well as chose res ulting from ch arging l
regulatory requiresent s. Appropriate information obt ained through participation in such training may thou be incorporated as improvement s i in the health physics program. ,
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With regard to 10CFR19.12, all individuals working in or frequenting any portion of a res tricted area receive the ins truction delineated in 10CFR19.12.
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ATTACHMENT 9 Technical Specifications The at t ached draft technical specifications are provided in suppo rt of the following ste.tements found in the Draf t SER.
- a. " Airborne radioact ive monitors will be calib rated at regular time intervals as required in technical specifications." (SER 12.3.4.2)
- b. "In the technical specifications , the ROC should be confirmed to be a member of the station's onsite safety committee." (SER 12.5.1)
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4 AININISTRATIVE CCNTROL9 i
6.3 FACILITY STPEF CUALIFICATICNS 6.3.1 Each marter of the facility and Radiation Protection staff l
shall meet or exceed the minimtm qualifications of ANSI N18.1-1971 for conparable positions, except for the Radiological Operations 03ordinator who shall meet or exceed the qualifications of Regulatory Guide 1.8, September t 1975, and the Shift '14chnical Advisor who shall have a bachelor's degree or l
equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retrainim and replacement training program for the facility l staff shall be maintained under the direction of the Director Nuclear Division Training and shall meet or exceed the requirements and l
rew.. ..dations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR l
i Part 55.
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, 6.4.2 A 'Itainim Program for the Emercency Squad shall be maintained under the direction of the Director Nuclear Division Trainity and shall meet ,
l r or exceed the reauirements of Section 27'of the NEPA 03de-1976.
l i j 6.5 REVIEN AND AUDIT 6.5.1 Onsite Safety Comunittee (OSC)
FUNCTICN:
h 6.5.1.1 1he OSC shall fi.:nction to advise the Station Superintendent on all matters related to nuclear safety.
COMPOSITICN:
1 6.5,1.2 'Ihe OSC shall be conposed of the:
Chairman: Oief Ehgineer i Manter: Senior Licensed Operator i l
Manber: Radiation control Ebreman l Member:
Maintenance Engineer Member: Senior Engineer - Station Engineering Monber:
Senior Testing or Study Projects Coordinator Member: Shift Technical Advisor Menber: Gemist rember: Quality (bntrol Engineer l l
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PFAVER VALIEY UNIT 2 i
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