ML20207F996
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Letter Sequence Other | |
|---|---|
TAC:63996, (Approved, Closed) | |
Initiation
Administration Questions
Results Other: ML20196A234, ML20207F996, ML20207R184, ML20212B113, ML20214E245, ML20235U287, ML20235W720 | |
MONTHYEARML20207F9961986-12-31031 December 1986
[Table View]Discusses Requirements of Radiological Control Program,Per App I of 10CFR50.Relaxation from Requirement to Impose RM-50-2 Radiological Criteria Requested.Response Requested within 30 Days Project stage: Other ML20212B1131987-02-24024 February 1987 Advises That 861231 Request for Change from Requirements of RM-50-2,specified in Annex to App I of 10CFR50,does Not Comply W/Requirements of App I.Staff Position Re Util Request to Control Activity Releases & Recommendations Encl Project stage: Other ML20207R1841987-03-0505 March 1987 Requests Schedular Exemption from Requirements of RM 50-2, Per NRC 870224 Position Concerning 10CFR50,App I.Requests That Exemption Remain in Effect Until 6 Months After Issuance of Full Power License for Unit 2 Project stage: Other ML20214E2451987-05-11011 May 1987 Forwards Rev 0 to Calculation Package ERS-ATL-87-026, Beaver Valley Power Station Units 1 & 2 Offsite Dose Calculation T..., Per R Fell 870402 Question & Requests Approval to Depart from NRC Interpretation of Instantaneous Project stage: Other ML20235P4191987-07-14014 July 1987 Notifies That Review of Offsite Dose Calculation Manual Complete & Acceptable Except for Two Concerns Re Noble Gas Nuclides & short-term X/Q Values Needing Resolution.Response Requested within 90 Days of Ltr Receipt Project stage: Approval ML20235W7201987-10-0606 October 1987 Responds to Two Concerns Delineated in Re Offsite Dose Calculation Manual.Util Always Performs Priority LLD Calculation & Compares Results to Tech Spec Table 4.11-2 Requirements to Ensure Compliance Project stage: Other ML20196A2341988-06-20020 June 1988 Concludes That Based on Licensee Annual Rept of Facility, Changes,Tests & Experiments & 880608 Site Visit, Changes,Tests & Experiments Meet Criteria in 10CFR50.59. Lists Improvements Recommended to Licensee During Visit Project stage: Other ML20235U2871989-03-0202 March 1989 Advises That 880225 Issue 2,Rev 0 & Issue 1,Rev 1 to Offsite Dose Calculation Manuals Acceptable Project stage: Other 1987-03-05 |
| ML20207F996 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton, Tam P Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-6-132, TAC-63996, NUDOCS 8701060276 | |
| Download: ML20207F996 (2) | |
Similar Documents at Beaver Valley | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999
[Table view]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 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
[Table view]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 Category:UTILITY TO NRC MONTHYEARML20059L4271990-09-0707 September 1990
[Table view]Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications ML20059G0821990-09-0404 September 1990 Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8 ML20059F7551990-08-29029 August 1990 Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining ML20059F1501990-08-29029 August 1990 Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829 ML20028G8731990-08-29029 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71 ML20059D3761990-08-24024 August 1990 Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant ML20028G8881990-08-24024 August 1990 Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned 05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990 Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued ML20058P7651990-08-14014 August 1990 Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc ML20059E0571990-08-10010 August 1990 Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4)) ML20059E7631990-08-0101 August 1990 Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory ML20059B8141990-08-0101 August 1990 Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations ML20056A3471990-07-31031 July 1990 Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed ML20056A1841990-07-27027 July 1990 Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon ML20055H2581990-07-25025 July 1990 Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b) ML20055F7061990-07-0909 July 1990 Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage ML20055D3871990-07-0202 July 1990 Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results ML20058K5031990-06-29029 June 1990 Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria ML20044A3661990-06-21021 June 1990 Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue ML20043G6811990-06-14014 June 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown ML20043H9341990-06-14014 June 1990 Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04 ML20043G5981990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1 ML20043G6851990-06-12012 June 1990 Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp ML20043G7941990-06-12012 June 1990 Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl ML20043G8001990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d ML20043H0291990-06-11011 June 1990 Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program ML20043F5251990-06-0707 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl ML20043F1361990-06-0404 June 1990 Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002 ML20043B5971990-05-18018 May 1990 Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531 ML20043B0511990-05-15015 May 1990 Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario ML20043B1921990-05-11011 May 1990 Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14 ML20042G9761990-05-0808 May 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601 ML20042G8541990-05-0303 May 1990 Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests ML20042G9071990-05-0101 May 1990 Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b) ML20042F1381990-04-30030 April 1990 Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990 ML20042F0991990-04-20020 April 1990 Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program ML20012F5951990-04-10010 April 1990 Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990 ML20042E1471990-04-0404 April 1990 Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization ML20012F6021990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed ML20012E3091990-03-23023 March 1990 Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation ML20012E3451990-03-23023 March 1990 Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl ML20012D6491990-03-19019 March 1990 Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus ML20012E4091990-03-16016 March 1990 Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI ML20012D6181990-03-15015 March 1990 Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled ML20042D7401990-03-14014 March 1990 Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89. ML20012D5801990-03-13013 March 1990 Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index ML20012D6221990-03-13013 March 1990 Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events ML20012C1791990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled ML20012E0911990-03-0505 March 1990 Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2) ML20012B7051990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G 1990-09-07 |
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2NRC-6-132 Beaver Valley No. L Unit Project Organization S.E.G. Building Te6ecopy 2)64 5 Ext.160 P.o. Box 328 Dec. 31, 1986 Shippingport, P A 15077 Mr. Harold R. Denton, Director Office Of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation
Subject:
Beaver Valley Unit No. 2 Docket No. 50-412 Appendix I Operating Program
References:
A) 2NRC-4-144, dated September 14, 1984 B) NRC letter dated November 6, 1986 from Mr. L. Rubenstein C) 40 Federal Register 40816, published September 4, 1975 D) 2NRC-5-034, dated March 1, 1985 Gentlemen:
Duquesne Light Company (DLC) has committed to develop the Technical Specifications for Beaver Valley Power Station Unit No. 2 (BVPS-2) to be as much like the RVPS-1 Technical Specifications as possible (per Reference A) and agreed to by the Nuclear Regulatory Commission in Reference B. In addition, DLC has developed plant procedures and structured numerous programs for both plants to be executed as similarly as possible to promote effective human factors considerations for maximum safe operation for both plants.
Since the Technical Specifications for BVPS-2 were modeled to be as much like the BVPS-1 Technical Specifications as possible, the BVPS-2 offsite dose calculation manual (00CM) was written to comply with the BVPS-2 Technical Specifications and to be similar to the BVPS-1 ODCM. DLC also believes that the BVPS-2 ODCM meets Appendix I because the plant was designed to meet the more restrictive criteria of RM-50-2. This criteria was imposed for construc-tion permit holders which filed after January 2, 1971 as per Section V of 10CFR50, Appendix I. BVPS-2 construction perinit application was docketed in October, 1972. Also per Reference C, cost-benefit analyses were not required of applicants in accordance with II.D of Appendix I, if the radioactive waste systems and equipment described in the Final Safety Analysis Report satisfied the Guides on Design Objectives proposed in RM-50-2. DLC believes that the design for BVPS-2 is acceptable per Appendix I requirements because it was shown in the Final Safety Analysis Report and Environmental Report that BVPS-2 was designed to be able to meet the more restrictive pre-Appendix I criteria of RM-50-2.
BO Y 8701060276 861231 (' s PDR A
ADOCK 05000412 PDR ,
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- United States Nuclear Regulatory Canmission Mr. Harold R. Denton Appendix I Operating Program Page 2 l
Plant design evaluation findings in the SER and FES written by the NRC reference the pre-Appendix I criteria of RM-50-2. However, DLC is in the pro-cess of conpleting the full implementation of an Appendix I-designed radiolog-ical controls progran for BVPS-2. DLC had notified the NRC of its intentions to operate in accordance with Appendix I through conments on the BVPS-2 Draft Environnental Statenent (Reference D) and through its Technical Specifications and ODCM submittals provided over a year ago without any NRC notification of non acceptance. At DLC's request, a conference call was conducted on October 28, 1986 during which DLC was notified that developing a radiological controls progran to meet the requirenents of 10CFR50 Appendix I at BVPS-2 was not accep-table to the NRC. In contrast to DLC's belief that 10CFR50 Appendix I itself shows that Appendix I criteria should be applied to BVPS-2, Mr. Robert Fell of the Nuclear Regulatory Conmission stated that his interpretation of Appendix I requires him to apply RM-50-2 criteria for BVPS-2.
DLC hereby requests relaxation fran Mr. Fell's perceived requirenent to impose RM-50-2 radiological criteria on BVPS-2. DLC will conmit to operate BVPS-2 in accordance with Appendix I radiological criteria which has been the design for the BVPS-1 radiological progran and is also the sane standard that other recently licensed nuclear power plants are using at multi-unit sites, such as Millstone Unit No. 3 and the River Bend Units.
Because fuel loading for BVPS-2 is scheduled in less than six months, DLC requests notification of acceptance of this proposed use of Appendix I for BVPS-2 within 30 days of this transnittal.
If you have any questions regarding this subject, please contact Mr. K.
D. Grada at (412) 393-5211 as soon as possible.
DUQUESNE LIGHT COMPANY l
By J.J.Wa(eJ (/ '
Sr. Vice President RWF/ijr NR/0PER/PROGRM AR/NAR cc: Mr. Peter Tam, Project Manager Mr. W. Troskoski, Sr. Resident Inspector Mr. J. Beall, Sr. Resident Inspector
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