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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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912H5s6000 435 Smth Avenue My'S">* September 22, 1981 Director of Nuclear Regulatory Regulation United States Nuclear Regulatory Commission
' C#) ,x Attn: Mr. Steven A. Varga, Chief
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Operating Reactors Branch No. 1 p ,
Division of Licensing h A
Washington, DC 20555 _
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Reference:
Beaver Valley Power Station, Unit No. 1 [ kJ Docket No. 50-334 %'- %
Control of Heavy Loads - NUREG-0612 Y % <
D / Tyt (O Gentlemen:
Attached for your review are the itemized responses as requested by your letter dated December 22, 1980. The three Sections submitted are:
2.2 Specific Requirements for Overhead Handling Systems Operating in the Vicinity of Fuel Storage Pools.
2.3 Specific Requirements of Overhead Handling Systems Operating in the Containment.
2.4 Specific Requirements for Overhead Handling Systems Operating in Plant Areas Containing Equiprent Required for Reactor Shutdown, Core Decay Heat Removal, or Spent Fuel Pool Cooling.
Very truly yours, 2
. J. Carey Vice President, Nuclear cc: Mr. D. A. Beckman, Resident Inspector U. S. Nuclesr Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission b
c/o Document Management Branch j Washington, DC 20555 ll 8109290723 810922 PDR ADOCK 05000334 PDR.
p
DUQUESNE LIGHT COMPANY Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Control of Heavy Loads - NUREG-0612 Attachment A 2.2 Requirements. for Overhead Haddling Systems in the Vicinity of Fuel Storage Pools 2.2.1 Identify by name,. type, capacity, and equipment designator, any cranes physically capable (i.e. , ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying loads which could, if dropped, land or fall.into the spent fuel pool.
RESPONSE Name: Moveable Platform Crane Type: Electric Overhead Traveling Capacity: 2-10 Tons (each)
Equip. Designation: CR-27 Note: Incorrectly listed as 5 tons each in Table 1 of June 23, 1981 submittal 2.2.2 Justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads or are permanently prevented from movement of the hook centerline closer .than 15 feet to the pool boundary, or by providing a suitable analysis demonstrating that fm. any failure mode, no heavy load can fall into the fuel-storage pool.
RESPONSE Fuel Cask Grane is shown on Figure 3A of the June 23, 1981 submitta' a- ehis subject. This crane travels the length of the Decontamination- Building and into the northwest section of the Fuel Building. The Bel Building -is oriented such that the fuel cask crane travel does not pass over the spent fuel pool. The sIent fuel cask laydown r area is separated by a concrete wall (2 feet thick) from 4
the spent fuel pool. The only penetration is a 24 in. slot to allow for passage of spent fuel elements into the laydown area. This slot is entirely above the storage
- 'icvel of the spent fuel elements in the pool, thereby
- providing assurance that the loss of- water via the . slot could not uncover the fuel. The movement of the fuel cask l within the fuel cask laydown area is handled in a two-?if t t operation with both levels of cask placement resulting in the cask remaining below the top of the 2 foot thick' concrete wall. The only time that the cask is lifted above i the level of the wall is to clear the platform hoist rail at the side of the fuel building. The time over this point is minimal and the distance 'to the fuel pool is the maximum possible. Thus, the - physical arrangement o f '. the Fuel Building is such that a cask drop accident would not cause damage to the stored spent fuel assemblies.
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. l Beaver Valley Power Station, Unit No. 1 l
. Control of Heavy Loads, NUREG-0612 ]
Attachment A Page 2 l 2.2.3 Identify any cranes listed in 2. 2-1, above, which you have evaluated as having sufficient design features to make the likelihood cf a load drop extremely small for all loads to be carried and the basis for this evaulation (i.e., complete compliance with NUREG 0612, Section 5.1.6 or partial compliance supplemented by suitable alternative or additional design j featu res ) . For each crane so evaluated, provide the load- )
handling-system (i.e., c rane-load-combination) information I specified in Attachment 1.
RESPONSE None ~
I 2.2.4 For cranes identified in 2.2-1, above, not categorized accord- I ing to 2.2-3, demonstrate that the c rite ria of NUREG 0612, Section 5.1, are satisfied. Compliance with Criterion IV will be demonstrated in response 20 Section 2.4 of this request.
With respect to Criteria I through III, provide a discussion of your evaluation of crane operation in the spent fuel area and your determination of conpliance. This response should include the following information for each crane: l
- a. Which niternatives (e.g. , 2, 3, or 4) from those identi-fied in NUREG 0612, Section 5.1.2, have been selected.
RESPONSE Alternative 2 i
- b. If Alternative 2 or 3 is selected, discuss the c rane motion limitation imposed by electrical interlocks or mechanical stops and indicate the circumstances, if any, under which these protective devices may be bypassed or removed. Discuss any administrative procedures invoked to ensure proper authorization of bypass or removal, and i provide any related or proposed technical specification (operational and surveillance) p rovided to ensure the operability of such electrical interlocks or mechanical stops.
RESPONSE The moveable platform crane spans the spent fuel pool and' carries two electric hoists (one spent fuel and one new l fuel). Fuel assemblies are moved within the spent fuel l pool by means 'of a long-handled tool suspended from the l hoist. 1 l
The hoist travel, tool, and sling length are designed to l limit the maximum lift of a fuel assembly to a safe j shielding depth. The motor-driven platform is also used l to upend the new fuel assembly shipping container (its 1
-heaviest load). The upending operation consists of a hoisting motion concurrent with a traversing motion of the platform.
1 i
l
Beaver Valley Power Station, Unit No. 1 ,
Conttol of Heavy Loads', NUREG-0612 Attachment A Page 3 Although this is the heaviest load lif ted by the crane, it' is not truly a lif ted load because the shipping contair.er is never entirely lifted, only up-ended. Additionaly, this is not lifted near the spent fuel.
Further, the moveable plat form load limit switch is set for 50 lb. over the weight of the fuel assembly and its handling tool. The c rane design safety factor of 5 coupled with the load limiter results in a factor of safety of approximately 25.
In addition, loads in excess of l.5 tons are prohibited from travel over the . fuel assemblies in the Spent . Fuel->
Storage Pool Building by Technical Specification 3.9.7.
This restriction on movement of loads over fuel assemblies in the storage pool ensures that no more than the contents of one fuel assembly will be damaged in the event of a fuel handling accident. Thus , a fuel handling accident ~
does not result in potential offsite~ exposures in excess .
of those listed in ICCFR100.
- c. Where reliance is placed on crane operational limitations with respect to the time of the storage of certain quantities of spent fuel at specific post-irradiation decay times , provide present and/or proposed technical specifications and discuss administrative or physical controls provided to ensure that these assumptions remain valid.
RESPONSE Reliance is not placed on the time of storage of spent fuel.
- d. Where reliance is placed on the physical location of specific fuel modules at certain post-irradiation decay times, provide present and/or. proposed technical speci-fications and discuss administrative or physical controls provided to ensure that these assumptions remain valid.
RESPONSE Reliance is not placed on ~ the physical location of specific fuel elements.
- e. Analyses performed to demonstrate compliance - with . Cri-teria I through III should conform to the guidelines of ~
NUREG 0612, Appendix A. Justify any exception taken-to these guidelines, and ' provide the specific information requested in Attachment 2, 3, ' or 4, as appropriate, for each analysis performed.
RESPONSE Load drop analysis is . not required in this case.
_ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ __ ____________.__ ____u
r -
Beaver Valley Power Station, Unit 3b. 1 Control of Heavy Leads, NUREG-0612 Attachment A Page 4 2.3 Requirement for Overhead Handling System in Containment 2.3.1 Identify by nau, type, capacity, and equipment designator, any cranes physically capable (i.e., taking no c redit for any interlocks or operating procedures) of carrying heavy loads over the reactor vessel.
RESPONSE Name: Containment Polar Crane Type: Electric Overhead Circular Traveling Capacity: Trolley No. 1 main hook 130 tons aux. hook 15 tons Trolley No. 2 main hook 130 tons Equip. Designator: CR-1 2.3.2 Justify the exclusior. sf any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads, or are pe: unently prevented from the movement of any load either directly over the reactor vessel or to such a location where in the event of any load-handling-system fail-ure, the load may land in or on the reactor essel.
RESPONSE (a) The Refueling Manipulator Crane (CR-5) lifts a maxinum load of one fuel element and handling tool. By definition (NUREG-0612), this is not a heavy load. The results of a drop from this crane have been previously addressed in a detailed study entitled " Fuel Handling Accident Evalu-ation" dated October 31, 1977. In addition, the crane is scheduled to be modified tc provide a dual cable heist and various safety feature improvements.
(b) The Neutron Detector Carriage (CR-16) does not lift any heavy loads.
2.3.3 Identify any cranes listed in 2.3-1, above, which you have evaluated as having su f ficient design features to make the likelihood of a load drop er.tremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1_.6, or partial conr-pliance supplemented by suitable alternetive or additional design featu res ) . For each crar.e so evaluated, provide the load-handling-system (i.e., crane-load-combination) informa-s tion specified in Attachment 1.
RESPONSE The Beaver Valley Unit 1 polar crane was designed with a minimum safety factor of 5 in accordance with EOCI Specification 61 and meets the later requirement of CMAA
- 70. The crane bridge was designed for 200 tons, with an occasional overload of 25 pe rcent ; and was ' capable of withstanding the one-time ' overload lif t of 375' tons for the reactor vessel and a 345 ton lif t with bridge rotation
Beaver Valley Power Station, Unit No. 1 Control of Heavy Loads, NUREG-0612 Attechment A Page 5 for each steam generator. The centerline of the 375 ton load was located between the centerline of bridge and a point 37 f t, f rom centerline of bridge toward the extended girder end.
See Enclosure 1 for the 13ad-handling-system information specified in Attachment 1.
2.3.4 For cranes identified in 2.3-1, above, not categorized accord-ing to 2.3-3, demon strate that the evaluation criteria of NUREG 0612, Section 5.1, are satisfied. Compliance with Criterion IV will be demonstrated in your response to Section 2.4 of this request. With respect to Criteria I through III, provide a discussion of your evaulation of c rane ope ra tion in the containment and your d^ termination of compliance.
RESPONSE There are no cranes in this category 2.4 Requirements for Overload Handling Systems in Proximity to Safs Shutdown Equipment 2.4.1 Identify any c ranes listed in 2.1-1, above, which you have evaluated as having sufficient design featu re s to make the likelihood of a load drop extremely small for all loads to be ca rried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial com-pliance supplemented by suitable alterna*ive or additional design featu re s ) . For each crane so evaluated, p rovide the load-handling-system (i.e. , crane-load-combination) informa-tion specified in Attachment 1.
RESPONSE As discussed in Section 2.1.3f and Section 2.33, the polar c rane (CR-1) was conservatively designed such that the possibility of a load drop is small. In addition to the design fea tu re s , the rigorous administration controls imposed by refueling procedures and comprehensive opera-tor training provide an in depth defense against load d rop. Fu rt he r, the inclusion of NUREG 0612 requirements in maintenance procedures and of ANSI B30.2 requirements for inspection, testing, and maintenance will increase the margin of safety.
The load-handling-system information is provided in En-closure 1 2.4.2 For any cranes identified in 2.1-1 not designated as single-tailure proof in 2.4-1, a comprehensive haza rd evaluation should be provided which includes the following information:
. Beever Valley Power Station, Unit No. 1 Control of licavy Loads , NUREC-0612 Attachment A Page 6
- a. The presentation in a matrix format of all heavy loads and potential impact areas where damage might occur to safety-related equipment. Heavy loads iduntification should include designation and weight or c ros s-re fe rence to information provided in 2.1-3-c. Impact areas should be identified by construction zones and elevations or by some other mcthod such that the impact area :an be located on the plant general arrangement drawings. Figure 1 provides a typical matrix.
RESPONSE Table 1 shows the matrix of heavy loads and potential impact areas.
- b. For each interaction identified, indicate which of the load and impact a rea combinations can be eliminated because of separation and redundancy of safety-related equipment, mechanical stops and/or electrical interlocks, or other site -specif * : consideratic as.
RESPONSE Table 1 provides this information.
- c. For interactions not eliminated by the analysis of 2.4 b, above, identify any handling systems for specific loads which you have evalisated as having sufficient design features to make the liked' hood of a load drop extremely small and the basis for chis evaluation (i.e.,-complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitabic alternative or addi-tional design features). For each crane so evaluated, provide the load-handling-system (i.e., c rane-load-combination) information specified in Attachment 1.
RESPONSU Thir information is included in the response to 2.4.1
- d. For intt ractions not climinated in 2.4-2-b o r 2,4-2-c ,
above, Jemonstrate using appropriate analysi , that damage would not preclude operation of suf ficient equipinent to allow the system to perform its safety function following a load drop (NUREG 0612, Section 5.1, Criterion IV).
RESPON_SE All interactions were eliminated.
Encircure I to Attcchment A Load - Handling - System Data Nace: Polar Crane (CR-1)
Cranc Mf r: P6H (a product of Harnischfeger)
Design Rated Load: 375 Tons (main trolleys) 15 Tons (aux. hoist)
Max. Critical Load: 130 Tons (main trolleys)
The Beaver Valley Power Station - Unit No. 1 containment polar crane (CR-
- 1) was purchased in 1969 prior to the publishing of NUREG-0554 (1979). The design was compared to the NUREG, and the results are outlined below.
SPECIFICATION AND DESIGN CRITERIA This crane was designed and fabricated to comply with the requirements of EOCI Specification No. 61, however, it does meet the later requirements of CMAA 70. The design rated load exceeds the maximum critical load by almost a factor of 3. Its design took into account the containment environnent to which it would be subjected.
A coldproof test as recommended as an alternative for operating plants (NUREG-0554) using a singic dummy load equal to 1.25 times the MCL is not considered necessary for this polar crane, All construction loads were far in exceas of this load and were pet formed over a period during which the containmen. was not closed and during the months of June thru December. A nondestructive examination of all critical areas was conducted after each const ruction lif t.
The crane structure is fairly ficxible and a review of crane drawings has not revealed any welds which would be susceptible to lamellar tearing. Most welds are small fillet welds. In most cases, welded parts on this crane are made of carbon steel. These steels have good weld ability. This crane was a shop fabricated structure and all welding was perforned to manufacturers standard procedures.
The crane will perform only a limited number of lif ts (several hundred) throughout the life of the plant. Of these lif ts, the heaviest expected load is that of the reactor vessel head each refueling. Because the number of cycles is small and the maximum stresses are well below yield stress, fatigue failure is highly unlikely.
SEISMIC ANALYSIS The method of analysis employed by the crane manufacturer (Harnischfeger Corp.) was computational in natu re and was based upon the matrix d isplacement method (d irec t stif fness method). The first step in this method was to approximate the actual configu ration as a st ruc tu ral framework which was defined as a stable system of uniform (constant cross section), weightless beam segments, and joints at which loads are applied and weights are lumped. This model information along with the structural
.. Beaver Valley Power Station, Unit No. 1
' Control of Heavy Lords - NUREG-0612
. Enclosure 1 to Attachuent A Page 2 loading (static loads and dynamic loading in the form of a shock spectra input) is used by the computer to perform the computations to provide the following information:
, 1. Displacements , = Nen t and axial fo rces , and moments of members for static loadings.
- 2. Reactions and equilibrium checks at each joint for static loadings.
! 3 .' Frequencies and' node shapes.
i
- 4. Displacements , shear and axial' fo rc e s , and moments of members for each of first six forced nodes of vibration.
The polar crane meets the requirementt of Regulatory Guide 1.29, " Seismic
, Design Classification" and is designed for all normal operating loads l acting simultaneously with both horizontal and vertical seismic loading.
The horizontal and vertical operating basie seismic loading is combined i directly considering a single horizontal direction earthquake. The stress level due to these combined loading condition does not exceed 90 percent of
- the minimum yield strength. The following design cases were analyzed
Case I In this case the crane analysis considered the sum of the following:
l Dead Load: This is the weight of all effective
- parts of the bridge s t ruc tu re , ma-l' chinery parts,' and the fixed equipnent supported by the structure.
]i Live Load: This is wieght of the trolleys and the lifted load (rated capacity - 200 tons).
- Impact Allowance
- This is an additional load equal l to 15 percent of the rated capa-
- city.
Case II In this case an analysis was performed considering all dead loads and a 380 ton construction live load.
l Case III In this case an analysis was performed considering all dead loads and a 418 ton test load.
Case IV i
a This analysis was for the operating base earthquake (OBE) considering the sum of all dead loads and live loads (no lifted load).
i t
i l
._- .,. _ _ -. _ . _ = _ _ ._-_ _ _ . _ . _ __ _
. Betver Velley Power Station, Unit No. 1 Control of lietvy Lords - NUREG-0612
, Enclo:ure 1 to Attachment A Page 3
- b. This analysis was for the design base carthquake (DBE) considering the sum of all dead loads and live loads (no lifted load).
SAFETY FEATURES Crane motor controls are of the " dead man" type wica spring return to "0FF" position. The bridge movenent is controlled by four (4) self adjunting, hyd raulically ope ra ted , brakes which a re mounted on the bridge motor extension shaf t and actuated by a foot Icver located in the cab. Each main hoist and auxiliary hoist has three brakes, an eddy current load brake and two s p ring-se t , electrically released, double shoe type load holding brakes. All are rated at 150 percent of motor full load torque. The holding brakes are automatically applied to the motor shaf t when the motor is deenergized. The trolley traverse motor has a helf-torque brake which is automatically applied to the motor shaf t when the motor is deenergized.
Limit switches have been provided to limit travel of the hoists in both the upward and downward directions.
IIDISTING MACllINERY The basic hoisting system used on the polar crane hoists consiste of a hoist drum driven by an electric motor through a gearcase. The hoist drum is used to takeup and payout the wire rope used to raise and lower the load.
A nagne to rque load brake rated for 150 percent of full motor torque is located between the motor and gearcase. The magnetorque is an electro-magnet exerting torque on the motor to preload the motor and to provide the speed control of a normally loaded motor without the use of a mechanical load brake. Magnetorque control provides superior speed regulation over any other AC crane control and actually exceedr the control available with DC dynamic lowering control. An additional feature of Magnetorque control is ths- it is impossible for the load to lower with the controller on any hoist position. OFF position braking is a safety feature with Magnetorque
< >n t ro l . With the controller in the OFF position, the Magnetorque unit is excited at a reduced voltage. In the case of an electric motor brake f a ilu re , the load will overhaul the hoisting unit, but the Magnetorque brake will exert a braking torque to slowly lower the overhauling load to the floor, thus preventing a f ree falling load.
In addition to the above braking system, each hoist is equipped with two (2) shoe-type electric brakes. These brakes are spring-set and electri-cally released.
The hoisting ropes used on the main hoists are 12 part, 1-1/8 inch, 6 x 37, ext ra-high-s t rengt h ropes with independent wire rope centers. The hoisting rope used on the auxiliary hoist is 4 part, 5/8 inch, 6 x 37 improved steel plow cable. The attachment of the cabic ends to the the
Besver Velley Power Station, Unit No. 1 Control of Heavy Loads - NUREG-0612 Enclosure 1 to Attachment A Page 4 d rums is such that if all but two wraps of the rope were unwound, the attachment would be strong enough to carry the load with a factor of safety of at least five.
Drums, sheaves, bottom blocks, and hoisting ropes were designed such that when raising or lowering, no twisting of the cables occurs. Bottom sheave blocks are of the enclosed type with guards to prevent cables from leaving the sheaves. Limit switches have been provided which limit the travel of hoists in the upward direction, thereby preventing two-blocking.
Maximum hoisting speed for the critical load for the polar crane is in compliance with the requirements of CMAA Specification #70.
A static load test was performed on each hook in addition to the 418-ton load test described under " Testing and Preventive Maintenance". Physical measurements of the hooks were taken prior to and af ter the load test and again af ter each special construction lif t and were acceptable. Hooks were magnetic particle tested for cracks and flaws before and after the load test, and af ter each special construction lif t. The hook bottom blocks and main pinion shaft fillets (on the drum side of each shaf t) were ultra-sonically tested for cracks and flaws at the same time.
BRIDGE AND TROLLEY Bridge structure braking is accomplished by four type DH brake assemblies.
All are shoe-type hydraulic applied and spring-released brakes. The DH type brake is self-adjusting and does not require any adjustments during normal operation. Depressing the pedal on the master cylinder, pumps hydraulic fluid to the wheel cylinder on the brake.
Trolley movement is controlled by a disc-type electric b rake which is spring-set and magnetically released. Operating the motion control device associated with a crane motion closes the circuit which applies power to both the motor and b rake coil. Energizing the b rake coil pulls the armature which compresses the spring and release t he b rake . Returning the motion control device to the OFF position, opens the circuit to both the motor and brake coil, and the spring sets the brake.
The c rane speed limits a re in compliance with those specified in Specification CMAA #70.
DRIVERS AND CONTROLS The polar crane main hoists are driven by 50 HP wound rotor motors, while the auxiliary hoist is driven by a 15 HP motor. Each of the motors are protected by thermal overload relays and speed controlled by PVA timed Magne torques . Hoisting movement is limited in the up direction by P6H type HB weight operated limit switches and in the down direction by geared type limit switches. All control c ircuits , hoisting, b raking, and holding
l ~, Beaver Valley Power Station, Unit No. 1 Control of Heavy Lords - NUREG-0612
, Enclosure 1 to Attachment A Page 5 systems hava been satisfactorily tested and are further described in other sections of this response. The complete operating control system and provi* ions for eme rgency controls for this crane are located in the operators cab on the bridge.
OPERATING MANUAL AND INSTALLATION INSTRUCTIONS The requirements of NUREG-0554 concerning the manufacture's issuing of a manual of information and procedures for use in construction, checkout, testing, control and operation of the polar c rane have been fully satisfied.
TESTING AND PREVENTIVE MAINTENANCE Af ter erection of the polar crane and prior to acceptance, the c rane undement a complete testing program and a e 18-ton load tests This load test was 321% of the maxinum critical load to ba lif ted by the crane. The test consisted of raising the 418-ton load 0.5 inches and stopping it to check the holding of the hoist brakes (duration of hold was one hour).
After successful completion of this test, the load was raised at the lowest speed position possible (#3); and as the load came approximately one inch off the floor, the main power was shut off in the operator's cab. The brakes held satisfactorily under this loss of power. The load was then raised using the 3rd, 4th, and 5th speeds to a suitable height (about 15 feet). The load was then lowered through all five speeds, and when within one foot of the floor, the power was again shut off in the cab, and the brakes again held satisfactorily. The load was then raised to a height of 5 feet and the bridge and tr Lley t ravel we re tested with the load traversing to the mid-span of the bridge.
At the completion of the above test, an NDT and a visual inspection was performed on the hooks and on the critical points.
A thorough visual examination of the entire c rane was performed for evidance of permanent deflection or wear resulting from the load test. The crane was then used for the successful installation of the reactor vessel, pressurizer vessel, and three steam generators.
J
TABLE 1 ,
IDAD/ IMPACT AREA MATRIX .
\
!!AZARD
. 2.1.3.a S.**ETY RELATED y ELIMINATION LOAD WEIGIIT(TONS) pi c, , EQuli> MENT COORDINATES ELEVATION CATEGORY
-CRANE NONE 7.5 5C RIVER WATER K, 11 1/2 713 a2,b l CR-9
' ( 76 6 '-7")
- CR-15 3
( 79 8 '-4")
- S<E'tT FUEL 21.5 3A FUEL POOL P-R, 8 1/2 766 a ,b,d SIIP G. C AL'K COOLING PIPING
- CR-17 RIVER WATER 4 RIVER WATER C-D, 2-6 705 a 5 ,b
( 74 5 ' -0")
RAW WATER 4 RIVSR WATER 'C-D, 2-3 & 705 a,b PUMP 9.3 PUMP & PIPING 5-6 MOTOR -
3.8 SERVICE WATER PUMPS & PIPING ELECTRIC FIRE 4 R1'IER WATER D-E, 2-3 666 a,b PUMP 3.0 PIPING MOTOR 2.0 DIESEL FIRE 4 RIVER & D-E, 2-6 666 a,b PUMP 3.0 SERVICE WATER ENGINE 1.9 PIPING IlYDRO- 1.2 4 RIVER WA'?ER D-3, 2-3 666 a,b PNEUMATIC PIPING TANK REMOVABLE 4.3 4B RIVER & SERVICE C-E, 2-6 705 a,b COVERS (largest) WATER PUlIPS &
PIPING SERVICE WATER 13.8 4 RIVER & SERVICE C-E, 3-6 705 a,b PUMP & MOTOR WATER PUMPS &
PIPING ,
TABLE 1
- LOAD / IMPACT AREA MATRIX ,
IIAZARD 2.1.3.a SAFETY RELATED ELIMINATION CRANE- LOAD WEIGIIT (TONS) Fia. EQUIPMENT COORDINATES 1 ELEVATION CATEGORY CR-17 TRAVELING 6 ,
( 74 5 '-0 ")
- SCREENS 10.4' 4A cont. (heaviest)
STOP LOGS 6 10 4A CR-19 4 NONE 13.9 NONE CABLES ON TIIE
( 751'-6")
- SPECIFIED (MAX) LEVEL BELOW F-II , 5-9 725 b CR-20
( 742 '-0")
- CIIARGING 5C REMAINING G 's/8-J, 722 b7 PUMP 3. 8 CIIARGING PUMPS 8 /8-10 1/ 4 MOTOR 2.0 . & PIPING ItEMOVABLE 5.0 SC REMAINING . G 7/8-J, 722 b7 COVE RS (MAX)
CIIARGING PUMPS 87/8-101/4
& PIPING ,
CR-21
( 746 '-0") *
- COMPONENT SC AUX. BUILDING K-L,9 3/8-11 732 b,c COOLING WATER VENT.EXII AUST PUMP 1.5 (CliARGINO PUMP M(7FOR 1.7 ZXIIAUSTS INTO THIS DUCT)
CR-23 SEAL WATER 1.1 5C' RIVER WATER J-K,11 1/2-13 730 d
( 76 0 ' -0 ") *
- IIE AT PIPING EXCIIANGER NON 4.3 5B " " "
d REGENERATIVE IIEAT EXCIIANGER DEBORATING 1.0 SB d
DEMINERALIZER CESIUM REMOVAL 1.0 5B " " " " d.
ION EXCIIANGER
TABLE 1 .
LOAD / IMPACT AREA MATRIX
- IIAZARD 2.1,.3.a SAIT;TY RELATED ELIMINATION CRANE LOAD WEIGHT (T'ONS) Fig. EQUIPMENT COORDINATES 1 ELEVATION CATEGORY
( con t. ) FUEL POOL 1.0 SB RIVER WATER J-K, 11 1/2-13 730 d ION EXCIIANGER PIPING REMOVAB LE 8.5 "iB d COVERS (largest)
SEAL FILTER 7.5 REMOV71 SIIIELD SB d CR-24 ** REMOVABLE 6.0 SA CIIARGIMG AND -J-L, 8 7/8- 753 a8 A&B COVE RS VOLUME CONTROL 9 3/8
( 78 2 '-0") PIPING CR-27 ** NEW FUEL 2.5 3B FUEL POOL IIEAT' P-R, 10 3/4- 741 a,b,d 9 (788'-6") S!!IPPING (fully EXCIIANGERS 11 3/4 NTAINER '.oaded)
FAILED FUEL 1.5 3A FUEL POOL M-R, 8 1/8- 741 a
?
ASSY. STORAGE ( full) COOLING 10 3/4 CAN PIPING NOTES:
- 1. Coordinates are column designations from plant equipment location.
- 2. Redundant line: 2 4 " - WR 151 - 03,
- 3. Redundant line: 6" - FC 152 - Q3.
- 4. CR - 19 13.9 ton load limit discussed in 2.1.3.f remains ir effect.
- 5. The entirely separate auxiliary intake structure provides redn.J3ancy as well as the redundant river water pumps and piping.
- 6. These loads, listed in response to 2.1.3c, are physically prevented (because of their size) from being lifted over any safety related .
equipment.
- 7. These lifts will be controlled to maintain the minimum lift height possible (generally less than 6") and to insure that the load passes over no floor opening other than that required to gain access to the i af fected equipment.
4
NOTES: cont. '! .
- 8. In the unlikely case that a floor plug would be dropped in such a manner that it passed through the smaller sized floor opening and then damaged either boric acide, transfer pump suction pipe (2"-Cll-41-15 3WQ3 or 2 "-
CII-42 -15 3W-03) , the other transfer pump would remain unaffected and would continue to perform its intended function. Also emergency boration means exist by lining up cperating charging pump with the borated re fueling water supply tank.
- 9. This load is never fully lifted, only upended. In addition the lift is restricted by the crane safe load path. Finally, the fuel pool cooling system contains 100 pc1 cent redundant pumps and heat exchangers which would continue to perform their intended function in the event of a load drop sufficient to cause damagc to either of the "a"or "b" train equipment.
The river water system is also provided as an emergency means of cooling the spent fuel pool, if required.
- Elevation of the top of the crane rail.
- Elevation of the hook at maximum height.
. HAZARD ELIMINATION CATEGORIES :
- a. System redundancy and separation preculudes loss of capability of system to perform its safety-related function following this load drop.
- b. Sufficient administrative controls exist to prevent lifting this load to a height sufficient to penetrate the concrete floor separating the lif ting device and load from the safety related equipment.
- c. Sufficient time exists to allow repair of any damage caused by this drop before loss of capability of this system to perform its safety-related function would occur.
- d. Administrative controls exist to maintain the load within the bounds of the safe load path and to prevent the movement of the load over the safety related equipment.
s