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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
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 ,
l PHILADELPHIA. PA.19101 m si e4i.4ooo FEB 171984 tuomicaina amo atsrancu nce.aratur Mr. Thomas E. Murley, Director United States Nuclear Regulatory Commission Office of Inspection and Enforcement, Region I 631 Park Avenue King of Prussia, PA 19406 Subjec t: USNRC IE Region I Letter dated January 10, 1984 RE: Site Inspection of October 17-November 30, 1983 Inspection Report No. 50-352/83-19 & 50-353/83-07 Limerick Generating Station - Units 1 and 2 File: QUAL 1-2-2 (352/83-19 & 353/83-07)
Dear Mr. Murley:
In response to the subject letter regarding items identified during the subject inspection of construction activities authorized by NRC License Nos. CPPR-106 and 107, we transmit herewith the following:
Attachment I - Response to Appendix A Also enclosed is an af fidavit relating to the response.
Should you have any questions concerning these items, we would be pleased to discuss them with you.
Sincerely, lulenfager v JPE/drd/840130-3 Engineering & Research Department At tachment Copy to: Director of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 S. K. Chaudhary, USNRC Resident Inspector 8405300558 840521
- .~ e Com0NWEALTH OF PENNSYLVANIA :
ss.
COUNTY OF PHILADELPHIA :
JOSEPH W. CALLAGHER, being first duly sworn, deposes and says:
That he is Manager, Engineering and Research Department of Philadelphia Electric Company, the holder of Construction Permits CPPR-106 and CPPR-107 for Limerick Generating Station Units 1 and 2; that he has read the foregoing Response to Inspection Report No.
50-352/83-19 and. 50-353/83-07 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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() V U Subscribed and sworn to before me this /) day of. l$ WY 0$22lh_1
- Notary Public PATRICIA D. SCHOLL
- Notary Pubite, Philsdelphia ' Philaddphia Co.
My Commission Expires Tebruary 10,1986
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- RESPONSETOhPPENDIXA
.VI'OLATION Is I 10 CFRL50', Appendix B, Criterion V, requires' that activities.af fecting
. quality be prescribed by a'ppropriate procedures and accomplished in accordance with these procedures.
.Bechtel Power' Corporation, Job Rule M-21 is the procedure established to provide direction ~ to construction personnel regarding cleanliness controls on systeas which have been turned-over to the licensee's Startup Organization.
Contrary to the above,' as of November 30, 1983, Job Rule M-21 had not been ef fectively implemented as evidenced by the f ailure to provide suitable cleanliness controls following disassembly of' a feedwater system contairment isolation valve IN41-1F010A. The valve body was ,
open, the internal surfaces of- the valve anJ its atuched piping were exposed to tha containment; environment, and standing water of undetermined quality had accumulated in the valve.
RESPONSE TO VIOLATION I Cleanliness controls associated with the identified valve and for
- Startup Work. Orders in progress at that time were corrected as' necessary to identify cleanliness- requirements _ to meet the. requirements 1 of Job Eule M-21.
To prevent recurrence of this condition, several! actions have been taken:
1)~ Post Turnover Maintenance field engineers, superintendents, and craf t personnel have been reinstructed in.the; requirements 3 of Job. Rule M-21 (Performing Work on Flushed Systems) .
- 2) Job Rules which contain references to Post Turnover -Maintenance have been revised 'to also apply to Startup Work Orders.
- 3) A Quality' Control Engineer hasbeen assigned full' time to -
oversee construction and housekeeping practices associated
. with the requirements' of , Job Rule M-21.~ '
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VIOLATION 2
- 10 CFR 50, Appendix B, Criterion X requires the establishment of a program that assures that examinations, measurements, or tests of caterials or products processed be performed for each- work operation where necessary to assure quality. .
I Section.17.2A.10.of the Final Safety Analysis Report and Volume I, Section 10 of the Limerick Generating Station Quality Assurance Plan establish this program.
Contrary to the above, the progra n establishe.d for engineering and quality inspection of pipe support hangers failed to assure the quality of two -saf ety-related hangers in- that, _as of Novenber 7,1983, hangers VRR-IRS-HHA-1 and HHB-1, for ths reactor recirculation sys tem suction piping were inadequately designad and installed and the inadequacies were not . identified during the engineering and quality inspections which
- , had been completed.
- RESPONSE'TO VIOLATION 2 The interferences identified by the Inspector did not develop until' af ter Field Engineering and QC acceptance of HHB-1 and Field Engineering release for pre-ops of HHA-1. These interferences developed as a result of the vibration caused by the recire pump operation. . However, . subsequent
- to the interferences developing, Field Engineering performed rework on '
hanger .HHB-1 which QC inspected. The rework was limited- and did not
- involve the interfering members of .the support. The interferences were .
not identified because of the apparently limited inspection of the-reworked hanger.. '
s .
The Inspector identified interferences have been resolved by implementing l
p tan option which was included in an FDDR prior to the interference- being; -
L Identified. The option was not used durit.g initial installation because i the. Field Engineers did not foresee the developement of the interferences.
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- i. To determine the ~ extent of' this condition QC completed inspectbns of the:
24 GE designed recirculation and unin steam hangers. These inspections '
U identified several nonconf ormances, the majority of which result from the lack of installation tolerances. Investigation into the-cause of -
these nonconf ormances - is..'not complete.: Theref ore, a follow-up response 4 to this violation will be.made by;3/31/84. ,
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. RESPONSE TO APPENDIX A VIOLATION 3' 10 CFR 50, Appendix B, Criterion <V requires .that activities affecting quality be prescribed by documented procedures and accomplished in accordance with the established procedures.
' Project procedure PSP-G-3.1 specifies nonconformance reporting requirements
.and permits oniv one nonconforming condition to be reported in each noncon-formance report (NCR).-
Contrary to the above, the project nrocedure for NCR reporting was not followed in that. as of November ~ 30, 1983, NCR 6507 was revised to include additional nonconformances.
RESPONSE ~TO VIOLATION 3 j
The additions made to Nonconformance Report (NCR) No. 6507, although admittedly not provided for in the existing procedure, did document the nonconforming conditions and associated dispositions to adequately meet the requirements -
of 10 CFR 50, Appendix'B, Criterion XV.
To prevent recurrence and to provide for the.various situations encountered during the processing of Nonconformance Reports.(NCR's), Project Procedure 3
PSP-G-3.1.was revised to provide for reprocessing the original NCR if the existing condition was not resolved or if a new condition was created by the disposition. .The PSP was also revised-to require a.new NCR be gen-l' erated when additional nonconforming items are' discovered. The exact i instructions in the PSP are:
- - "If ~" Rework" or " Repair" performed to .the original disposition did not satisfactorily resolve the existing condition
- or created a' new condition, the Construction Quality Control Engin4er per-forming _ the reinspection shall document the results as a revision l to block 19 of the NCR form, and reprocess the NCR for additional disposition.
i If ' additional nonconforming items are discovered as a result of ~
the reinspection, a new Nonconformance Report shall-be initiated.
The Quality Control Engineer performing the reinspection shall ,
use discretion in determining which of the 'above conditions applies. -
. Any question shall be resolved -by the responsible lead discipline-
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-Quality Control Engineer."
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. Additional training has been given on1the above matter.
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i FEB 171984 Mr. Thonna E. Murley, Director United States Nuclear ReLulatory Commisujon Office of Inspection and 1:nforcantient, Region I 631 Park Avenue King of Pruccia, PA 19406 Subj ec t: USNRC 11:, Ret,1un I Letter dated January 10, 1934 RE: Site lucpection of October 17-Novetaber 10, 1983
. Inspection Report No. 50 ')S2/83-19 & 50-353/if'J-07 Limerick Generating Station - Unita 1 and 2 File: QUAL 1-2-2 (352/83-19 f. '151/83-07)
Dear Mr. Murley:
In response to the nubject letter regardin;>. itetau identified during the subject inupoction of cunutruction netivities authorize.1 by MRC License Nos. CPPR-106 and 107, to transmit herewith the followine,:
A ttachinent I ilesponnu to Appoiuli:: A Also enclos,ed is an affidavit relating to the response.
Should you have any questionu concerning these item 1, t.e t,ould be pleased to diucous them with you.
Sineercly,
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Qp Q 4# fodineering IV Research Department
!!-" JPE/drd/840130-3 Manager p' Attachinent
,b p Copy to: Director of Inspection and rnforcetaent ,
United States Mucionr Regulatory Coccission Washington, DC ?.0555 S. K. Chaudhary, USURC Resident luspector
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RESPONSE TO APPENI)lX A ,
i E VIOLATION I 10 CFR 50, Appendix B, Criterion V, requires that ac tivities afl ecting in quality be prescribed by appropriate proceduren and accomplishe,)
accordance with these procedures.
Bechtel Power Corporation, Job Rule M-21 in the procedure estabt ished to provide direction to construct ion personnel rey,ardt oiny, cleanl t he i ne"8 fleennee' controlu un .systemn whicli luive been turned-over Startup Organization.
Contrary to the above, as of November 10, l *RI's , Job Hol etoM-71 failure prwind ids-not been uf fec tively Lmplemented an ev idenced by I he suitable cleanliness controls f ollowing dianssemblyThe of avalve f eedwa bodyt was er system containment isolation valve llV41-lF010A.i t s a ttached piping were open, the internal surfacen of the valve nial exposed to the containment unvironment, and nLanding wa ter of.
undetermined quality had neeumulated in the vn Ive.
HijS,PONSlj ,TO, VT01.AT1,0N 1 ,
Cleanliness controls associated with thatthe identifled t ime valve andasf or were corrected necessary Startup Work Orders in progress a t to identi f y cleanliness requ irements to meet I he requ irement n cf .lub Rulu M-21.
To prevent recurrence of .this condition, several actions have Icen taken:
1)
Pos t Turnover Maintenance fluid engineern, 'superintendente, alKI craf t person.nel have been reinstructed in the /equiremente of Job Itulo M-21 (Perf orming Work on Flunbed Systeme) .
nance
- 2) Job Rules which contain ref erences to Pout Turnover Mainte have been revised to also apply to Startup Work Orders.
- 3) - A Quality Control. Engineer has been assigned full time to oversee construction and housekeeping practices associated with the requirements of Job Rule M-21.
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RESPONSE TO APPEND 1X A l i
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VIOLATION 2 i j
10 CFR 50, Appendix B, Criterion X requires the establishment of' a d program that assures that examinations, measu rements , or testn of materials or products processed be performed for each work operation where necessary to assure quality.
Sec tion 17.2A.10 of the l'inal Safet y Analynin Report and Volume I, Section 10 of the Limerick Cunerating Station Quality Assurance Plan ectablish this program.
Contrary to the above, the progmm established for engineering and assure the quality quality inspec tion of pipe sup.iort hangers f ailed tu of two saf ety-related hangers in that, as of Novanber 7,1983, hangers VRR-IRS-IlllA-1 and lillB-1, fur the reae tor reeI reulatIon synien sue tlun piping were inadequately designed and installed und the inadequ.seles were not identified during the engineering and quality inspections which had Seen completed.
HMSPONSM TO VIOI.ATJON 2 The interferences identified by the Inspector did not develop until af ter Field Engineering and QC aeceptance of 111lll-1 and Field Hngineering release for pre-ups of IlllA-1. These interf erences developed as a result
' of the vibration caused by the recire pump operation, llowever , subsequent to the interferences developing, Field Mngineering performed rework on innger 11118 - 1 which QC Inspected. The rework was limited and did not.
Involve the interfering members of the suppor't. '?he interferences were not identified .because of the apparently limited :41spection of the reworked hr.nger.
The Inspector identified interferences have been resuived by implementing an option which una included in an FDDR prior to the interference being identified. The option was not used during initial installation because
- the Field Engineers did not focusee the developement of the interferences.
To determine the extent of this condition QC completed inspections of the 4
24 GE designed recirculation and unin steam hangers. These inspections identified several. nonconf ormances, the majority of which result from the lack of installation tolerances. Investigation into the cause of these nonconformances is not complete. Therefore, a follow-up response -
to this violation will be made by 3/31/84.
I 2/3 352/83-19 353/83-07
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RMSPONSE TO APPHNDIX_A_
VIOLATION 3 l 10 CFR 50, Appendix II, Critorion V requires that activities af fecting
. quality be prescribed by ' documented procedures and accomplished in accordance with the established procedures.
- Project procedure PSP-C '3. I specif f us nonconformance report i ng requirements and permits only one nonconforming condition to be reported in each noncon-Lformance report (NCR).
Contrary to the above, the oro.iees orncedure lor NCR r..nortion wau not followed in that. as of November 30, 1983, NCR bS07 was revised to include additional nonconformances.
RESPONSE TO VIOLATION 3 The additions made to Nonconformance Report (f;CR) No. 6507, although admittedly not provided for in the existing procedure, did document the n'onconforming conditions and associated dispos Ltions to adequately meet the requirements of 10 CFR 50, Appendix 11, Criterion XV.
To prevent recurrence und to providu Lbrthe va r i ous u1Luationu encountered during the processing of Nonconformance Reportu (NCR's), Project Procedure PSP-C-3.1 was revised to provide for reprocessing the originai NCR ii the existing condition was not renol ved 'or if a new condit ion wan created by the disposition. The PSP wau also revised to require a new NCR be gun-3 erated when additional nonconforming itemn are discovered. The exact instructions in the PSP are:
"if " Rework" or " Repair" performed to. the origingt disposition '
did not satisfootorily resolve' the existing condition or created a new condition, the Countruct ion Quali ty cont rol Munineer pi r-forming the reinnpcetion'nhall document the renullu an a revision to block 19 of the NCR form, and reprocess the NCR for additional disposition.
If additional nonconforming items are diseuvered as a result of the reinspection, a new Nonconformance Report shall be initiated.
The-Quality Control Engineer performing the reinspection shall use discretion in determining which of the above conditicieapplies..
Any question shall be- resolved by the responnible lead discipline Quality Control Engineer." .
Additional training has been given on the ahuve matter.
1 3/3 352/83-19 353/83-07:
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.h e 9 PHil sADELPHlA ELECTRIC COMPANY s 2301 MANKET STREET
, P.O. BOX 8699 PH:LADELPHIA. PA.19101 1215[041 4000
" orch 26, 18s?.4
'r. da.rus f'. "ut ley, Director l' . i u s' fit a n . 2- ..uclear Keaulatory Conr,f rnion office of li.op etion ari d Enforcerent, Per f on 1 63] fark ? venue l i t.;' of I rur.c i a , Pn. 19406 Subj e ct : US .AC IF Re.gion 1 Letter deted Jr.ccory 10, 19b4 Re: Site Ins pection of October 17-fovember 3D, l'B'3 Inspection Peport Fo. 50-352/U3-10 and 50-353/U3-07 Feference: J. S. 5'e r pe r Le t t er to T. F. . urley, dated 2/17/H4 Iile: QUAL 1-2-2 (352/03-19) over r. ;urjev:
In m:r reenense to Violsrion 2 nf Insm'etion Penort W . 5t'-3 5?/:' 3-19 cc ev oitted to a follen. up rm ponse by 3/31/t4. I!our- ve r, tbc correcti're cetjon Jteted in our previous responre bar, not yet been ccro!cto .. 1( 1 e' ' e '+ c e t to coirnlete prorrear tie corrective 1 r t i n'19 'y f./ ~10/'a and vill inter- y: of eer
- 4. r thit tire.
f.1ould you have any ruestions concerning this itee, i e 1o013 be p l e t's ed t o dis. cut s t her vi th you.
M nce rcl:',
C J. 5. Peeper F A:.ir cc: S. F. Chaudhary, SRC Re:;ident luspector (Lir.erick)
J . *i . 'i n : ins , $7kC 1:esident Inspector (Litrerick)
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