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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld ML20195G4591999-06-10010 June 1999 Forwards MORs for May 1999 & Revised Repts for Apr 1999 for LGS Units 1 & 2 ML20195H0531999-06-0909 June 1999 Forwards Revised Bases Pages B3/4 10-2 & B3/4 2-4 for LGS Units 1 & 2,in Order to Clarify That Requirements for Reactor Enclosure Secondary Containment Apply to Extended Area Encompassing Both Reactor Enclosure & Refueling Area ML20195E7701999-06-0707 June 1999 Provides Notification of Change to NPDES Permit PA0052221, for Bradshaw Reservoir Facility Which Supports Operation of Lgs,Units 1 & 2,per EPP Section 3.2 ML20195C7631999-06-0101 June 1999 Notifies NRC That PECO Energy Has Completed Installation of New Large Capacity,Passive Strainers on RHR & Core Spray Sys Pump Suction Lines at Lgs,Unit 2,in Response to Ieb 96-003 ML20195D5381999-05-26026 May 1999 Forwards 1998 Occupational Exposure Tabulation Rept for LGS Units 1 & 2. Encl Is Diskette & Instructions.Rept Is Being re-submitted to Reset 12 Month Time Period.Without Disk ML20195B2821999-05-24024 May 1999 Requests That NRC Distribution Lists for LGS Be Updated. Marked-up Distribution List Showing Changes Is Attached ML20196L2891999-05-20020 May 1999 Provides Status Update of Thermo-Lag 330-1 Fire Barrier Corrective Actions,Iaw Commitments Made in ML20195B2951999-05-20020 May 1999 Forwards Rev 0 to LGS Unit 2 Reload 5,Cycle 6 COLR, IAW TS Section 6.9.1.12.Values Listed Have Been Determined Using NRC-approved Methodology & Are Established Such That All Applicable Limits of Plants Safety Analysis Are Met 05000352/LER-1999-003, Forwards LER 99-003-00,re Rps,Pcrvics Actuations.Ler Contains Special Rept Info for HPCI & Reactor Core Isolation Cooling Sys Injections Into Rv1999-05-19019 May 1999 Forwards LER 99-003-00,re Rps,Pcrvics Actuations.Ler Contains Special Rept Info for HPCI & Reactor Core Isolation Cooling Sys Injections Into Rv 05000353/LER-1999-002, Forwards LER 99-002-00,automatic Actuations of Primary Containment & Reactor Vessel Isolation Control Sys & Other Common Plant ESF Due to Loss of Power to a Rps/Ups Power Distribution Panel on 9904191999-05-18018 May 1999 Forwards LER 99-002-00,automatic Actuations of Primary Containment & Reactor Vessel Isolation Control Sys & Other Common Plant ESF Due to Loss of Power to a Rps/Ups Power Distribution Panel on 990419 ML20206E2001999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept (Non- Radiological) for Limerick Generating Station,Units 1 & 2. Rept Submitted IAW Section 5.4.1 of App B of Fols,Epp (Non- Radiological) & Describes Implementation of EPP for 1998 ML20206D8801999-04-27027 April 1999 Forwards Rev 2 to LGS Unit 1 Reload 7,Cycle 8 COLR, IAW TS Section 6.9.1.12.COLR Provides cycle-specific Parameter Limits for Noted Info ML20206A5461999-04-21021 April 1999 Responds to Conference Call Between Util & NRC on 990420,re TS Change Request 98-07-2,revising TS Section 2.0 to Incorporate Revised MCPR Safety Limits.Attached Ltr Contains Info Requested ML20205T0441999-04-17017 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept 15, IAW TS Section 6.9.1.7.REMP for 1998,confirmed That LGS Environ Effects from Radioactive Release Were Well Below LGS TSs & Other Applicable Regulatory Limits ML20205Q7581999-04-15015 April 1999 Forwards Response to RAI Re ISI Program First & Second 10-Yr Interval Relief Requests.Revs to Identified by Vertical Bar in Right Margin 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K3671990-09-14014 September 1990 Informs of Revised Commitments Re Crud Induced Localized Corrosion Related to Fuel Cladding Failures.Deep Bed Demineralizers Installation Activities Will Be Performed in Unit 1 Subsequent to Third Refueling Outage ML20065D4421990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Proposed Schedules for Operator Licensing Exams, Requalification Exams & Generic Fundamental Exams Encl ML20064A5831990-09-0707 September 1990 Responds to Violations Noted in Insp Repts 50-352/90-17 & 50-353/90-16 Re Differential Pressure for Pumps.Corrective Actions:Licensee Will No Longer Use Expanded Ranges as Acceptance Criteria for Inservice Testing Program Tests ML20064A4821990-08-31031 August 1990 Forwards Rev 20 to Emergency Plan.Changes Necessitated by Annual Emergency Plan Update & Administrative in Nature ML20059E6071990-08-29029 August 1990 Forwards Semiannual Effluent Release Rept,Jan-June 1990 & Rev 8 to Odcm ML20059B0751990-08-24024 August 1990 Forwards Rev 0 to Updated FSAR for Limerick Generating Station,Units 1 & 2,Vols 1-19.W/one Oversize Encl. Proprietary Vol 7A (App 3B) Withheld (Ref 10CFR2.790) ML20064A6471990-08-24024 August 1990 Forwards Public Version of Revised Epips,Consisting of Rev 10 to EP-101,Rev 2 to EP-112,Rev 13 to EP-208,Rev 11 to EP-230 & Rev 22 to EP-291 ML20059E9861990-08-24024 August 1990 Provides Justification for Applicability of Reload Methodology Topical Repts to Facility & Requests NRC Approval for Application of Reload Analysis Methodologies ML20058N9591990-08-13013 August 1990 Forwards Revised Response to Violations Noted in Insp Repts 50-352/90-13 & 50-353/90-13.Corrective Actions:Ltr Issued to All Plant Personnel Providing Instructions on Proper Use & Handling of Controlled Documents in Controlled Locations ML20058N1771990-08-10010 August 1990 Responds to NRC Re Unresolved Items Noted in Insp Repts 50-352/90-80 & 50-353/90-80.Plant-specific Technical Guideline Has Been Revised to Ref Contingency Numbers Rather than Transient Response Implementation Plan Procedures ML20063P9461990-08-10010 August 1990 Provides Plans for Ultimate Disposition of Recirculation Inlet Nozzle to Safe End Weld Indication.Alternative Corrective Actions to Disposition Nozzle to Safe End Weld Indication Include Repair by Weld Overlay W/O Monitoring ML20058N1281990-08-0909 August 1990 Forwards Correction to Rev 10 to EPIP EP-234, Obtaining Containment Gas Samples from Containment Leak Detector During Emergencies ML20058N1991990-08-0909 August 1990 Advises of Change of Address for Correspondence Re Util Operations.All Incoming Correspondence Must Be Directed to One of Listed Addresses ML20058P1261990-08-0909 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Limerick Units 1 & 2 & Rev 1 to June 1990 Rept ML20058M9951990-08-0808 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-352/90-15 & 50-353/90-14.Corrective Actions:Personnel Counseled on Importance of Procedure Compliance & Operations Manual Revised ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML20055J0241990-07-26026 July 1990 Forwards Response to NRC Regulatory Effectiveness Review Rept for Plant.Response Withheld Per 10CFR73.21 ML20056A9731990-07-25025 July 1990 Forwards Facility Written Exam Comments for NRC Insp Repts 50-352/90-10 & 50-353/90-11.Written Exam for Reactor Operator & Senior Reactor Operator Considered Comprehensive & Thorough ML20055H8511990-07-24024 July 1990 Responds to NRC 900720 Request for Addl Info Re Util 900516 Request for Exemption from Full Participation During 1990 Onsite/Offsite Emergency Exercise.Nrc Region I & FEMA Support Feb 1991 Exercise,Per 900718 Telcon ML20055H8331990-07-20020 July 1990 Submits Change of Addresses for Correspondence Re Util Nuclear Operations ML20055H0231990-07-12012 July 1990 Forwards Public Version of Revised Epips,Including Rev 10 to EP-210,Rev 19 to EP-231 & Rev 13 to EP-237 ML20044A1041990-06-22022 June 1990 Forwards Application for Amends to Licenses NPF-39 & NPF-85, Consisting of Tech Spec Change Requests 90-03-0 & 90-04-0, Revising Surveillance Requirement 4.9.6.1 for Section 3.9.6 Refueling Platform Re Main Hoists/Auxiliary Hoists ML20043J0371990-06-20020 June 1990 Forwards Description,Scope,Objectives for Plant 1990 Annual Emergency Exercise Scheduled for 900920,per 890809 Ltr.Util Will Submit Revised Objectives for Exercise to Reflect Limited Participation,If Exemption Request Approved ML20043H6081990-06-19019 June 1990 Corrects 900427 Response to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing - 10CFR55 & Conforming Amends. ML20055C7621990-06-18018 June 1990 Informs NRC of Plans Re Licensing of Senior Reactor Operators (Sros) Limited to Fuel Handling at Plants.Util in Process of Implementing New Program for Establishment & Maint of Licensed SROs Limited to Fuel Handling at Plants ML20055C7471990-06-15015 June 1990 Requests That Listed Operator Licenses Be Discontinued ML20043G1331990-06-14014 June 1990 Responds to NRC 900614 Ltr Re Violations Noted in Insp Repts 50-352/90-13 & 50-353/90-12.Corrective Actions:Boxes of Completed Procedures Improperly Stored Shipped to Util Storage Vault by 900406 ML20043G9981990-06-12012 June 1990 Forwards, Core Operating Limits Rept for Unit 1 Reload 2, Cycle 3 & Core Operating Limits Rept for Unit 2,Cycle 1. Repts Submitted in Support of Tech Spec Change Request 89-13 Re Parameter Limits,Per Generic Ltr 88-16 ML20043G7311990-06-0808 June 1990 Provides Addl Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Welds Examined During Last Refueling Outage Addressed ML20043G7501990-06-0808 June 1990 Requests Withdrawal of 900516 Tech Spec Change Request 90-11-1 Re Extension of Snubber Visual Insp Period.Change No Longer Needed Since Unit Shutdown on 900605 & Visual Insp of Three Affected Snubbers Performed on 900607 ML20043F8021990-06-0808 June 1990 Forwards Monthly Operating Repts for May 1990 for Limerick Units 1 & 2 & Revised Pages to Mar 1990 Rept for Unit 2 & Apr 1990 Rept for Units 1 & 2 ML20043D8101990-05-29029 May 1990 Forwards Application for Amends to Licenses NPF-39 & NPF-85, Consisting of Tech Specs Change Request 89-07 to Relocate Radiological Effluent Tech Specs to ODCM or Process Control Program,Per Generic Ltr 89-01 ML20043E6571990-05-25025 May 1990 Forwards Public Version of Rev 135 to Epips,Including Rev 11 to EP-202,Rev 14 to EP-282,Rev 12 to EP-284,Rev 8 to EP-312 & Rev 9 to EP-410.W/DH Grimsley 900607 Release Memo ML20055C5121990-05-18018 May 1990 Provides Info Inadvertently Omitted in Re Property Insurance Coverage for Plants.Limerick Generating Station Unit 2 Should Have Been Ref as Being Included Under Insurance Coverage ML20043A7881990-05-16016 May 1990 Requests Exemption from Requirement to Perform Biennial full-participation Onsite/Offsite Emergency Exercise for Plant During 1990 ML20055C4851990-05-15015 May 1990 Forwards Annual Financial Repts for 1989 for Philadelphia Electric Co,Pse&G,Atlantic Energy,Inc & Delmarva Power & Light Co ML20043B1501990-05-14014 May 1990 Forwards Public Version of Rev 134 to Epips,Consisting of Rev 10 to EP-230,Rev 4 to EP-255,Rev 1 to EP-302,Rev 7 to EP-304 & Rev 3 to EP-314.Release Memo Encl ML20043A2361990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-352/90-07 & 50-353/90-06.Corrective Actions:Sampling Review of Plant Baseline Data Will Be Performed to Ensure Product Code Number Correctness for Components ML20042F4481990-05-0101 May 1990 Advises That Plant Transient Response Implementing Plan Procedures & Related Ref Matls Provided to Dj Florek,Nrc Region I,On 900430.Documents Provided in Response to NRC 900327 Ltr Re Preparation for Planned NRC Insp of Procedure ML20042E8741990-04-27027 April 1990 Responds to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing. Certifies That Limerick Operator Requalification Training Program Renewed on 900125 & Peach Bottom Subj Program Renewed on 890622 ML20042E0881990-04-0909 April 1990 Forwards Addl Info Re 891011 Tech Spec Change Request 89-09 to Reduce Number of Suppression chamber-to-drywell Vacuum Breakers Required to Be Operable ML20042E0201990-04-0606 April 1990 Forwards Vols 1-3 to Preservice Insp Summary Rept, & Books 1-3 to Form NIS-2 for Preservice Insp Interval 1985-1990, Per 10CFR50.55a(g) & ASME Code Section Xi,Paragraph IWA-6230 ML20012E2151990-03-20020 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' for Peach Bottom.Response for Limerick Generating Station Will Be Provided by 900504 ML20012C2931990-03-12012 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey, Per 900118 Request ML20012D9511990-03-0909 March 1990 Forwards Public Version of Revised Epips,Including Rev 10 to EP-203,Rev 12 to EP-317 & Rev 18 to EP-292.W/DH Grimsley 900322 Release Memo ML20012A3631990-03-0101 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-353/89-32 on 891211-15.Corrective Action:Util Will Document Both Receipt & Shipment of Fuel Loading Chambers on Next Semiannual Doe/Nrc Form 742 ML20012A1151990-02-28028 February 1990 Forwards Semiannual Effluent Release Rept 11,Jul Through Dec 1989 & Annual Tower 1 Joint Frequency Distributions of Wind Direction & Speed by Atmosphere Stability,Rept 5 for 1989. W/O Annual Tower 1 Rept ML20012A2621990-02-16016 February 1990 Forwards Public Version of Revs 124 & 125 to Epips, Consisting of Rev 9 to EP-201,Rev 20 to EP-291 & Rev 21 to EP-291 ML20006E7731990-02-16016 February 1990 Requests Discontinuation of Listed Operator Licenses ML20006E6511990-02-15015 February 1990 Discusses & Forwards Results of Field Verification Testing of Unit Spds,Per Licensee Commitment to Submit Rept within 30 Days After Unit SPDS Declared Operational.No Significant Problems Encountered W/Spds During Power Ascension Testing 1990-09-07
[Table view] |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX SP 39 PHILADELPHIA PA.19101 1215) e 41 4 s00 November 17, 1987
- ,s[o c',sh$, ;
Docket No. 50-352 Mr. William T. Russell, Administrator U.S. Nuclear Regulatory Comnission Region 1 631 Park Ave.
King of Prussia, PA 19406
Subject:
Limerick Generating Station Unit 1
!.E. Bulletin 85-03, "Motor-Operated Valve Comron .
Mode Failures During Plant Transients Due to Inproper Switch Settings" J. S. Kerrper (PECo) letter to T.' E. Murley ORC),
Reference:
dated October 2, 1986 File: GOVT 1-1 (Bulletins)
Dear Mr. Russell:
This submittr,1 provides Philadelphia Electric Cenpany's (PECo) The final d
response to I.E. Bulletin 85-03 for Limerick iGeneratin contains the required design basis differential pressure information and sco of testing.
The report enclosed herein completes the bulletin's reporting reautrements with regard to Limerick Unit 1.
Should you have any questions regarding the information contained in this submittal, please contact us.
, - Sincerely, VWh
/
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TSN/pdO9288701 '
Enclosure L f
Copy to: E. M. Kelly, LGS Resident Site Inspector fl USNRC, Docurent Control Desk Washington, DC 20555 ' l i
8803290126 871117 i PDR ADOCK 05000352 O DCD l
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LIMERICK GENERATING STATION UNIT 1 RESPONSE TO I.E. BULLETIN 85-03 y i
l REVISION 0 NOVEMBER 16, 1987 l
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REPORT FOR LIPERICK GENERATING STATION UNIT 1 IN RESPONSE TO I.E. BULLETIN 85-03 PURPOSE _
This report responds to I.E. Bulletin 85-03 which required licensees to develop and irrelement a program to assure that motor-operated valve (MOV) switch settings In certain safety systems are selected, set and maintained correctly such that the MOVs will function during This both report normal and abnormal events within the plant design basis.is in 1.E. Bulletin 85-03 action item (f) for Limerick Unit 1.
RESPONSE TO BULLETIN REOUTREMENTS The following discussion provides PECo's respenses to items (a) through (f) of I.E. Bulletin 85-03 The recuirements of the Bulletin are restated belcw along with PEco's response.
y Item (a)
"Review and doctrnent the design basis for the operatico of each valve. This doctanentation should include the maximtsn differential pressure expected during both opening an these valve operations and events are included in the existing, approved design basts, (i.e., the design basis docunented in When pertinent IIcensee submittals such as FSAR analyses a determining the maxirn.rn differential pressure, those single equipment failures and inadvertent eculgrnent operations (such as inadvertent valves closures or openings) that are within the plant design basis shN1d be asstrned."
PECo Resoonse Reference (3) provided PECo's preliminary I.E.The Bulletin 85-03 Information l
submittal which addressed bulletin action item a). ik supplied b with this action item and describes hcw it relates to the overall L progran.
PECo was a participating merrber of the BWROG ccmnittee which established the scope of systems and valves subject to the I.E. Bulletin This ccmnittee also developed and recemnended the 85-03 recuirements.
' rrethodology by which the MOV design basis operational differentialRef pressures were to be calculated. report whichPECo describes has adoptedthese results a regarding I.E. Bulletin 85-03 program Irnolementation. ld the BWROG Ccmnittee's reccmnended program end has expanded it to inc u e other Motor Operated Valves.
3_
For Limerick Units 1 and 2, the systems identified by the BWROG as being subject to I.E. Bulletin 85-03 are the High Pressure Coolant injection CHPCI) and Reactor Core isolation Cooling (RCIC) Systems.
The BWROG report further defined the Bulletin scope by stating that*
only those HPCI/RCIC MOVs designated as having an active safety function need ccumiy. For the other safety-related MOVs which the BWROG classifled as having no active safety ftnction, slmllarly developed methodologies were used to calculate their maxinun operational differential pressures. These calculations are considered conservative, since they include a conservatively nodeled hydrodynamic pressure ccrrponent.
The NRC in Reference (4) took exception with the BWROG position on I.E. Bulletin 85-03 The central issue concerned the exclusion of certain MOVs frcm the scope of the Bulletin on the basis that they would not be inadvertently out of pos! tion when called upon to operate.
Inadvertent M3V operation according to the BWROG ls beyond design basis and failures resulting frcm it are considered within system single failure criteria. Since PECo's !.E. Bulletin 85-03 program scope includes all HPCI and RCIC safety-related MOVs, the NRC's major objection '
with the BWROG is not applicable to Limerick.
The attached Tables 1 and 2 present a stirmary of information, Including differential pressure recuirements, appilcable to the valves /
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' operators in the HPCI/RCIC systems. These tables have been formulated to provide sufficient technical data to permit identification of rrotor-operated valve assentiles for which similarity (type) testing can be applied. In these tables please note the changes In the The differential pressure values previously reported in Reference 3).
changes resulted from subsequent evaluation and refining of theAll changes had supporting calculations during the checking process.
a negligible effect on MOV operating requirements as will be dertonstrated in later discussions.
Item (b)
"Using the results from item (a) above, establish the correct switch settings. This shall include a program to review and revise, as necessary, the methods for selecting and setting all switches, (i.e., torque, torque bypass, position !!mit, overload) for each valve operatton (opening and closing).
"If the I tcensee determines that a valve is inoperable, the IIcensee shall also make an appropriate justification for continued operation in accordance with the applicable technical specification."
._ ~ ~ - -__ _
PECo Response Reference (3) provided a brief swmary of the Limerick program The elements that support ccrno11ance with this action item.
Information supplied below provides the specific details which denenstrate cmpliance.
The Limerick program was essentla11y in place prior to issuance of This program provided for torque switch
!.E. Bulletin 85-03.
setpoint testing based on the original These specified differentialdifferential pressure pressure for each valve tested.
values remained as the bases for setting the torque switches on those valves where the values exceeded the newly calculated design basis differential pressures. Therefore, this Limerick program feature provides additional conservatism with respect to valve capablitty to fmetion under higher than the design basis differential pressure cond!tIons.
- With other valves for which the original specified differential pressures were less than the newly calculated values , the as-left settings were confirmed to be adecuate to assure MOV closure To ensure against the higher design basis differential pressures.
l - that replacement valves are capable of operating against the l
I higher design basis differential pressures, the appilcable Limerick valve specifications are being revised to reflect the more stringent design requirements.
The necessary specification revisions are scheduled to be completea by the end of 1987.
Toroue Switches f
I At Limerick Generating Station, notor-operator torque switches settings are based on the following criteria:
l 1)
The mininun acceptable setting shall be such that the developed stem thrust, asessured using the Motor Operated Valve Analysis and Test System (MOVATS), is sufficient to fully close the valve against the as-specified differential pressure.
2)
The maxinun acceptable setting Is constrained by the twer of ths fo11 ming four limits:
a)
The valve maxinun a11mable thrust as specified by the l
' valve manufacturer.
I b) The maxinun allowable thrust for the specific noter operator type.
1
' c) The maximun torcue capab!11ty of the rrotor @ degraded voltage, d) Spring pack specific maxinun a11mable settings.
1 1
4 9
The valve stem thrust reout rements are as specified on Valve Motor Operator Concatibility Forms (WCCF) which were supp1 t ed by For those valves with the the valve manufacturer for each MOV.
newly calculated differential pressure (per colmris 3 and 4 of Tables 1 and 2) having a value less than the valve design differentla) pressure, a revised stem thrust value is not necessary and has not been provided. Valves having a newly calculated differential pressure higher than the valve design differential pressure have been !!sted in Table 3 with the higher reQulred stem thrustThese revised stem corresponding to that pressure.
were derived from standard procedures provided by the operator manufacturer and were confinred to be acceptable by the valv w pplier.MOVATS data for all valves within the scope of this v2ove.
program is included in Tables 3 and 4 which denonstrate that the erveloped closing thrusts at torove switch trip (for the established toraue switch settings) exceed the recuired mlnirrun in all cases.
A review of the actual thrust requirements for the valves Indicates This that to valve assently is loaded beyond its allowable maxirrtm.
evaluation was made by comparing the actual measured closing thrusts agaltst valve / operator maxtrrun capabilities specified on the VMOCFs.
Another positive feature of the Limerick program Therefore, is that the open an and close toroue switch settings are Identical.
operator output force at least ecual to that recuired to fu This program conservatism to fully open the valve when actuated.
further assures recovery from Inadvertent valve operation.
The toroue switch setting adjustment and/or verification recuirements discussed above have been implemented on allThese Limerick safety-related include K)Vs having SMB-000 through SMS-4 type operators.
all valves within the scope of !.E. Bulletin 85-03 with the exception of HV-55-1F041 which is a limit-seated butterfly valve operating mder relatively low differential pressure conditions.
Over four hundred (400) MOVs at Limerick Unit I have had theirThis sam torcue switches set in this rnanner.The toroue switch setting and stem ld progress at Limerick Unit 2. thrust testing utilizing MOVATS are Irr Engineering Procedures FE-14 or FE-16.an acceptable torque s for verification of as-found conditions.
Limit Swltches The setting of MOV limit switches is procedurally controlled and docurented at Littnrick via Maintenance Procedure PMQ-500-087.
This procedure recuires that:
on the sa~e rotor as (1) the open torcue switch bypass switch (f .e.
the close limit) is to remain closed until pesttive ev torque switch operation and noting change in rrotor loading; and
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l (2) the open Ilmit switch is set such that the stem or disk does not coast into the backseat after terminating electrical operation. For SMB-000 operators, the valves are set to stop For all other 1/2 to I han& heel turn frcrn the backseat.
rising stem operators except SMB-000, the acceptance cril,erla is end of coasting between 1/4" to 1/2" of stem travel off the backseat.
1 In order to corrply with I.E. Bulletin 85-03, the wereapp 1' cable repeated limit during I
switch verification portions of PMQ-500-087 Limerick's first refuel outage (August 1987).
Thermal Overloads At Limerick Generating Station, safety-related trotor-operator thermal overload (TOL) protection has the following features:
(1) Motor-operator overload trips are annunciated in the Control rocyn.
(2) The motor-operator overload trip is bypassed during autcractuations which increases the probability that the valve will perform its safety function.
(3) Thermal overload protection can be bypassed In an emergency This is accortplished by holding by the control rocm operator.
the control switch In the o en or close positlon.
(4) The overload heaters are sized in accordance with the special service requiremr.nts of intermittent duty motors.
The sizing criteria is such that the trotor will rapidly trip off If a locked rotor condition exists; but provides sufficient margin over nortnal operational loadings.
The cuerload heaters on all I.E. Bulletin 85-03 MOVs were verlfled to be properly sized and oriented during Limerick's first refuel outage.
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Item (c_),,
"Ini:llvidual valve settings shall be changed, Whetherastheappropriate, valve settingto is those established in item b, above.
changed or not, the valve will be derronstrated to be operable by testing the valve at the rnaxirra.rn differential pressure determined in item (a) above with the exception that testing rrotor-coerated f valves under conditions simulating a break in the line containing l Otherwise, justification should be I the valve is not reculred.
I provided for any cases where testing withThis the maxtrrtin differential Justification pressure cannot practicably be performed.
should Include the alternative to maxirrtin differential pressure testing which will be used to verify the correct settings, i
PECo Response _
As described in our response to item b), the MOVS at Limerick Unit I were set and tested during the construction startup phase in accordance Using the with a program developed to assure their proper operation.
calculated valve actuator ferces recuired to overccrne the maxlrrun differential pressures, the valves were stroke tested using MOVATS to This verify the adecuacy of the existing torque Switch settings.
testing, which is an alternative to full differential pressure testing, is an Integral part of the program discussed in our response to Item b).
PECo has.ccrmleted a pre-operational and surveillance test review and performed supplementary MOV differential pressure testing in order to dermnstrate switches.
the adecuacy of using MOVATS for setting actuator tor system configurations required to achieve the maxinun differentist pressures, the supplementary testing was performed at the highestThe data co differential pressures practical.
effort confirms the adecuacy of the torque switch setting technloves and, to the extent practical, the vendor's methodologyThe to data predict was the necessary stem force for a given differential pressuge.
collected frcrn a large representative sarrole of Limitorque operator types, valve vendors and valve types subject to the I.E. Bulletin.
Tables 5 and 6 provide details of the specific supplementary tests performed.
In conclusion, PECo's Limerick I.E. Bulletin 85-03 program provides a very high confidence that the subject MOVs will perforTn their design basis safety fmet ton.
Item (d)
"Prepare or revise procedures to ensure that correct switch settings are determined and maintained throughout the life of the plant. Ensure that applicable Industry recernnendations are considered in the preparation of these procedures."
PECo Response Procedures E11.10, FE-1f+ and FE-16 iswere used used durin used as recuired. Limerick Maintenance Procedure PMQ-500-087 to ensure that the correct trotor-operator switch settings are maintained in addition to providing an electrical checkout follcwing maintenance.
This procedure is performed following safety-related MOV maintenance tb to provide a cerrolete functional checkout of the trotor-operator, revisions to the above procedures were determined to be necessary.
As part of the procedures review, PEco developed a specific MOV maintenance Under the PEco program, all future MCV maintenance MOVATS results.
will be reviewed against this list to determine what testing nust be perforTned prior to returning any safety-related MOV to service.
Item (e)
"Within 180 days of the date of this bullettn, submit a written (1) repo report to the NRC that:
contains the program to acecrnplish items (b) through (d) abovf including a schedule for convietlen of these items."
PEco Response (Ccriolete)
Reference (3) provided PECo's respersse to this action item.
Item (f)
"Provide a written report on convietion of the above program. This report sbx1d provide (1) a verification of cernpletion of the requested program, (2) a swmary of the findings as to valve operabt.11ty prior to any adjustments as a result of this bulletin, and (3) a strrmary of data In accordance with Table 2, Suggested Data Strrmary Format. The NRC staff Intends to use this Thisdata to report ass 1st in the resolution of Generic Issue II.E.6.1.
shall be submitted to the NRC within 60 days of,icerroletion of the program. Table 2 should be expanded, if appropriate, to Include a sm mary of all data recurred to evaluate the response to this bulletin."
PECo Response This doctment cerroletes the reporting reautrements ofA I.E.
Bulletin 85-03 actton item (f) for Limeriek Unlt 1.
supplementary report to address Limerick Unit 2 speelfic Infonretlon will be provided wtthin three (3) months following certoletion of the remaining Unit 2 work scope (Projected cerroletlon 3/68).
As explained in eari ter discussions, motor-operator switch settings were/are being ver! fled to be adequate As aduring thea result, startup/ construction phase of Limerick 1/2.
smmary of the as-found findings as prescribed by thefully Limerick bulletin are not considered appropriate for Limerick.
r.crrolles with the primary purpose and intent of the bulletin by having Instituted a ecmorehensive program to assure the adequacy of its MOV switch settings.
PECo MOV PROGRAMS BEYOND f.E. BULLETIN 85-03 During the Limerick Unit I construction Crefurbishstartup phase, and testall safety-related MOVs have tndergone a program to inspect,This program was initlated in respon the Limitoroue notor-operators.
to Sig%Ificant heficiency Report - 38 through a joint effortOver on the part of Bechtel Power Corporation, Limitorque Corp. and P which is currently planned to be irrelemented on ,a_Q Limerick Unit 2 MOVs.
Personnel involved with the "hands-on" aspect of the progrern are trained to perform the specified activities and are certifled by The Limitoroue Rework program is described in procedure Limitorcue.
8031-FM-4 (attached).
CONCLUSION This report has provided a conplete Limerick Unit I response for PECo has exceeded the all action items of I.E. Bulletin 85-03 bulletin's requirements by having implemented a ccrrorehensive OnnotoT-operator rework prograrn applicable to Limitorque safety-related MOVs.
the basis of Limerick's previously established program and since no physical MOV adjustments were determined to be necessary as a result of ccrrollance with action items (a), (b) or (c), PECo has detennined that the existing condition and capability of the subject valves were and continue to be adequate to assure performance of their design basis safety ftnction.
REFERENCES 1.E. Bulletin 85-03, "Motor-operated Valve Comron Mode Failure (1) During Plant Transients Due to irrproper Switch Settings, Noverrber 15, 1985 BWROG Report on the Operational Design Basis of Selected (2) Safety-Related Motor-Operated Valves, NEDC-21322, Septerrber 1986 (3) J. S. Koncer (PECo) letter to Dr. T. E. Murley JNRC),
dated October 2,1986 (4) E. L. Gordon (NRC) letter to T. A. Pickens (BWROG), dated January 30, 1987 (5) J. J. Millto letter to C. B. Wyler, dated L.;tober 7,1987 (6) Precedure FE-14, Procedure to Adjust and Set Limitorque Stem Thrust, revision 5 (7) Procedure FE-16, Procedure to Evaluate "As-found" Limitorque Stem Thrust, Revision 5 Preventive Maintenance Procedure for (8) Procedure PMQ-500-087, Electrical Checkout and Adjustment of Q-L!sted Limitorque Operators, Revision 1 (9) Procedure 8031-FM-4, L1mitorque Rework Program and l
Supplemental Technical and Maintenance Instruction for all l
l Limitorque Motor Operators at Limerick, Revision 7 (10) Procedure EE11.10, Procedure to Insoect and Test Motor Operated Valves, Revision 2 l
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TSN/pdO9298705 i
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NOTES AND REFERENCES FOR TABLES 1 AND 2 NOTES:
- Does not perform an active safety-related function per the BWROG Report.
or RCIC (Table 2) system
- Initiation of HPCI due to accident (Table 1) conditions, hCircledvalvenumberrepresentsvalvesrequiredtobe tested per BWROG Report, paragraph 4.3. -
Design differential pressures are obtained from the (1) Design Specification for the valve.
.c (2) Calculated valve differential pressures are per ,
Bechtel Calc. Misc-47.
(3) Deleted (4) U designates upstream D designates downstream is not required to be tested per BWROG Report, (5) valve (6) paragraph 4.4. Change from values previously reported in Referenc a differential pressure values are presented with each set of assumptions. The (7) corresponding to a different highest values are used for conservatism although they may be
,- beyond the BWROG design basis.
= -- _ ..
j .. .
TABLE 3 4
RE Til2UST REQUIREMEffTS FOR VALVES WITH HAX1 HUN CAIEULATED DIFF l' EXCh6 DING ORICINAL DESIGN DIFFERENTIAL PRESSURE
'. I Dedign l Actual Requ13ed thrust
! Valve Design Maximus Calc. Thrust (4) for HarJous
, Valve Differentist Thrust J j BWROC Ceneric Differential (Ibf)(6) (Ibf) l Calc. Differentist Volve I.D. Pressure (psid){ Pressure per 1 Pressure (Ibf)(5) l l Valve Ref. No. j l
Number ' l BWROC Report (psid) l '
13,454 18,540 ; 16876 I 1000 1172
, liv-49-IF022(1) ( 5 i l
! f 1,032 1,620 '
1507(2) l 30 59 IIV-49-IF084 { VIII j l I 64,920 130,500 81500 l 1 1000 1206 5 I IIV-55-lF008(1) ' 31,060 { 33,670 l 26041 i
1000 1206 ;
6 l l
llV-55-lF011(1) { l i
22.600 21100 l 1494 19,821 2 1400
) IIV-55-IF012 l 21,611 8170 I 94 6,407 '
4 I 70
! IIV-55-IF042 10,220 6657 1207 1,640 7 50 llV-55-IF071(-) l L 1,641 2,620 l 2271(3) __
t 1 30 L . 59 _
VIII (
I IlV-55-IF095 l 1
I no active safety function per BUROC. ._
i (1) Test valve: HV-49-!F080 I
(2) Thrust specified is suitable for dif f. pressure of 160 paid per duplicate valve l
(i.e. 1507 lbf) V 55-IFU93 (3) Thrust specified is suitable for dif f. pressure of 185 paid per duplicate valve ll -
l (i.e. 2271 lbf) f t (H0 VATS)
I (4) Actual thrust as obtained from motor operated valve analysse and testing sys em measurements. f t r
' (5) Calculated values were based on standard theseprocedures values.
provided by the operator manu ac ure The applicable HOCFs have'been revised to reflect (6) Design thrust per Valve Hotor Operator Compatab111ty Forms.
Sl~ET 1 OF 2 ,
1 I TABIE 4 SSURE ACT11AI RfTOltrED 11110S1S FOR VAfNES Willi MAX 1MlM CAlfUIATED DIFFERINTIAI, P LESS 111AN ORIGINAi, DESIGN DIFFERlWTIAI. PPESSURE
! } Design Actual J Valve Design Maxinnen Calc. % rust (4) Reference Ibetsment Valve Differential %cust for Design % rust
] FMPOG Ceneric Differential Pressure per 15m0G (Ibf)(3) (Ibf)
< Valve I.D. Pressure (psid)
Number Valve Ref. No. (1) Report (psid) (2) l l
16,293 19,620 P-1040-81-2
! 1500 1362 1
IN-49-1E013 4,432 5,840 P-104C-122-2 1300 1278 IN-49-lF019 2 2,047 2,780 P-102C-107-2 125 22 ,
3 IN-49-IF010 2,047 8,450 P-102C-107-2 f 125 49 4
IN-49-IF029 2,047 6,520 P-102C-107-2 125 49 IN-49-lF031 4a 259 1,080 P-114A-110-8 75 31 1
IN-49-1F002 7 j 16,293 17,740 P-iO48-81-2 1500 1171 IN-49-I F012 8 i .
4,613 6,676 P-ll4A-247-1 1337 1287 IN-50-lF046 9 l
' 39,047 49,370 P-104C-54-1 1337 1130 1 I i IN-50-lF045 9,456 17,580 P-104C-56-1 1337 1130 II IN-49-lF007 12,280 P-104C-56-1 1130 9,456 III 1337 l 1N-49-1EV0tf 4,840 P-ll4A-110-8 1130 4,613 t
! V 1337
! IN-49-IF076 2,498 3,740 P-103-98-3RR 50 31 IN-49-lit 60 VI 1,507 1,300(6) P-102A-213-58R 160 j 59 n i IN-49-lFOBO l VII , -
4 e
1- ----r--- --rm-- -- - - ap
, . ?-wsa w- -
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bilt.tSi i pr a' ,
TAllLE 4 ACIIIAT. REl'ORTED Vil0 SIS FOR VALVES WITil MAXIMUM CAtf0tATED DIFFERE LESS 'IllAN ORIGINAL DESIGN DIFFERENTIAL PRESSURE ._
Maxinnan Calc. Lesign Actual Valve D: sign % rust (4) Reference Ibcument Valve Differential W rust Valve I.D. BWROG Generic Differential Pressure per BWROG (lbf)(3) (lbf) for Design % rust' Valve Ref. No. Pressure (psid)
Nunber (1) Report (psid) (2) .
40,130 54,980 P-104B-168-1 1625 1454 1
IN-55-lF105 P-104B-93-2 50,050 91,800 1625 1463 IIV-55-lF006 la 6,407 12,520 P-1020-172-1 125 23 IN-55-lF004 3 1
11,461(5) (5) P-119A-166-1 125 94 IIV-55-lF041 4a 55,866 110360 P-1048-94-2 1625 1171 IIV-55-lF007 8 1,484 2,510 l'114A-246-1 410 55 IIV-56-IF059 9 41,888 93,600 P-1040-95-2 1337 1130 IIV-55-lF001 I P-1 HC- 52-1 107,932 116,000 1337 1130 II IIV-55-1F002 P-164C-52-1 107,932 137,500 1237 1130 liv-55-IF003 III 4,613 5,220 P-114A-110-8 1337 1130 1:V-55-1P100 V N 3,557 3,820 l'103-99-4BR 50 31 IIV-55-1F072 VI 2,271 3,130 l'102A-212-4BR 185 59 llV-55-IF093 ,
VII NorTES- 1) 2)
Design dif ferential pressure was obtained fran the valve Design Specif t
3) opening or closing directions. Design thnist per the valve Motor Operator Canpatability Form b differential pressure.
4)
Actual thrust as obtained fran motor operated valve analysis and testing syston measuranents (FKNATS).
5) value is torque (in--lbs), actual torque ' as confinned by testing of similar units.
6)
Actual thrust of 1300 lbs is acceptable since design thrust for dp of 50 psi is 1032 lbs per hientical valve llV-49-IF084, Mien interpolated to 59 psi thrustAlternativ required is 1071 lbs.
4 TABLE 5 CONFIRMATORY DIFFERENTIAL PRESSURE TESTING OF HPCI SYSTEM MOTO PRE-OP TEST SUPPLEMENTAL AFO SURVEILLANCE D-P TEST RESULTS TEST TYPE E COlOITIONS INFORMATION VALVE il DESCRIPTION Satisfactory Open D-P Test None IN-55-IF105 Injection Valve
@ 1320 psid IN-55-lF006 Satisfactory Open D-P Test Open valve and return it close IN-55-1F012 Minin(m Flow against puip discharge head Bypass Valve @ 1320 psid at rated conditions.
Satisfactory N/A Open valve against differential HV-55-1F041 Puir Suction - pressure generated by pressurizing Suppression Pool line via vent valve to 100 psig.
Isolation Valve Satisfactory N/A Close valve and return it to IN-55-IF008 Test loop Throttle throttle position against puio ;
Valve discharge head at rated conditions."
Satisfactory N/A Close valve and return It to IN-55-IF011 Test Loop Isolation open against puip discharge head Valve at rated conditions.
N Satisfactory Open D-P None IN-55-IF007 Puap Discharge
- Test @ 1320 psid
' Valve Satisfactory Close valve and return it to open Turbine Accessory N/A against purp discharge head @
a IN-56-1F05')
Cooling Valve rated conditions.:
{
7 Satisfactory' l Valve is opened and closed against 4
Open D-P Test FN-55-IF001 Stean Admission @ 1160 psid (Cold) live steem flow at rated conditions:
i Valve to Turbine during quarterly system surveillance l
} tests.
{
f 9
" s 2- .
PRE-OP TEST SUPPLEENTAL #0 SURVEILIJWC5 D-P TEST RESUI.TS, TEST TYPE C CONDITIONS INFORMATION VALVE I DESCRIPTION Satisfactory Open D-P Test None tiv-55-lF002 Inboard Stean @ 1160 psid Isolation Valve Satisfactory j
Open D-P Test Close valve agalrist live steam '
IN-55-1F003 Outboard Steam
@ 1160 psid flow vdille running in test isolation valve mode at rated conditions."
Satisfactory Close valve against contairment Vacutm Breaker Onen D-P Test ILRT pressure prior to I
IN-55-1F093 @ 200 psid IN-$5-1F095 Isolation Valves contalrunent depressurization.
4 t0TES:
"Rated Conditions - The system terrperature and pressure conditions representative of 100's reactor power and steam flow. System punp discharge pressure sufficient to provide rated flow to Llie reactor. '
i a
. 4/aud/10228705 i
4
't I
j i a
TABLE 6 CONFIRMATORY DIFFERENTIAL PRESSURE TESTING OF RCIC SYSTEM MOTOR-PRE-OP TEST SUPPLEN NTAL Ato SURVEILL)NCE D-P TEST RESULTS~
INFORMATION TEST TYPE & COtoITIONS VALVE il DESCRIPTION Satisfactory Open D-P Test None Injection Valve IN-49-IF013 @ 1275 psid Satisfactory Open D-P Test Open valve and return it close IN f i9-lF019 Minimtm Flow against puno discharge pressure Bypass Valve @ 1240 psid at. rated conditions. ,
Satisfactory Open velve against D-P developed Pum Suction - N/A by pressurizing suction line tN f 9-1F031 i
Suppression Pool via vent valve to 100 psig.
Isolat.lon valve Close valve and return it to throttle Satisfactory Test. Loop N/A position against punp discharge IN-49-lF022 Throttle Valve pressure at rated conditions.
Satisfactory Close valve and return it to open Turbine Accessory N/A tN-50-1F046 against pum discharge pressure Cooling Valve at. rated conditions.
Satisfactory Open D-P Test Valveisroutinelyopenedand IN-50-1F045 Steam Admission Valve @ 1170 psid (Cold) closed against IIve steam flow at to Turbine rated conditions during quarterly
! surveillance test.
Satisfactory Open D-P Test None
- tN-49-lF007 inboard Steam @ 1160 psid (Cold) j isolation Valve Satisfactory Open D-P Test While in test mode valve closed IN-49-IF008 Outboard Steam @ 1160 psid (Cold) against Ilve stean flow at rated isolat.lon Valve conditions.
. . . ...o PRE-OP TEST SUPPLEMENTAL #D SURVEILLANCE D-P TEST RESULTS TEST TYPE & COtOITIONS INFORMATION VALVE I DESCRIPTION -
Satisfactory init. late RCIC Ilne warme by Stean Line N/A IN-49-1F076 opening valve against rated Wannup Valve pressure then close valve. .
Satisfactory Open D-P Open then close valve against IN-49-lF 080 Vacutm Breaker Test @ 200 psid containnent ILRT pressure prior tN-49-1F084 Isolation Valves to contalnnent depressurization.
"Rated Conditions - The systan tenverature and pressure conditions representative of NOTES:
100% reactor power and stean flow. System pmp discharge pressure sufficient to provide rated flow to the reactor.
TSN/pd10238704 N
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