|
---|
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] |
Text
I
.s .
PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHI A, PA.19101 JUN 0 71984 (215)841-4502 v aC E-PRIESID E N T Ehuesea s nesse Aho nasaancM Mr. A. Schwencer, Chief Docket Nos.: 50-352 Licensing Branch No. 2 50-353 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Limerick Generating Station, Units 1&2 SER Confirmatory Issue #1
Reference:
NUREG-0991 File: GOVT l-1 (NRC)
Dear Mr. Schwencer:
Confirmatory issue #1 of the reference requires Philadelphia Electric to revise FSAR Tables 3.2-1 and 3.2-2. Attached are draft FSAR pages that will be included in FSAR Revision 34 which will be submitted in July. The attached pages provide additional information describing Limerick compliance with Regu2 story Guide 1.26, Revision 3, and the codes and standards used in construction.
Providing this information satisfies the SER requirement to enable closure of confirmatory issue #1.
Sincerely, y
JLP/gra/060584'925 cc: See Attached Service. List 1
l 8406120367 B40607 i PDR ADOCK 05000352 E PDR p y b --__ _ .)
-~
cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Troy B. Conner, Jr. , Esq. (w/o enclosure)
Ann P. Hodgdon, Esq. (w/o enclosure)
Mr. Frank R. Rmano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Charles W. Elliot, Esq. (w/o enclosure)
Zori G. Ferkin, Esq. (w/o enclosure)
Mr. Thanas Gerusky (w/o enclosure)
Director, Penna. Erergency (w/o enclosure)
Managment Agency Angua R. Love, Esq. (w/o enclosure)
David Wersan, Esq. (w/o enclosure)
Robert J. Sugarman, Esq. (w/o enclosure)
Spence W. Perry, Esq. (w/o enclosure)
Jay M. Gutierrez, Esq. (w/o enclosure)
Atanic Safety & Licensing (w/o enclosure)
Appeal Board Atanic Safety & Licensing (w/o enclosure)
Board Panel Docket & Service Section (w/o enclosure)
Martha W. Bush, Esq. (w/o enclosure)
Mr. James Wiggins (w/o enclosure)
Mr. Timothy R. S. Campbell (w/o enclosure)
Ms. Phyllis Zitzer (w/o enclosure)
Judge Peter A. Morris (w/o enclosure) i.
DRAFT M
y.yo LGS FSAR
~, TABLE 3.2-1 (Cont'd) (Page 30 of 38)
- 7) - Recirculation loop piping (28")
- 8) Recirculation loop suspension {
,9) RHR valves 20" gate valve
- 10) Core spray valves i 12" check valve (air-operated) l
- 11) Nuclear Class I piping (all except main steam and recirculation) l NRC approval of the request was given on 11/18/75 in a letter from R.C. De Young to E.G. Bauer of PEco.
,The applicable code for design, fabrication, and testing of the main steam isolation valves is the ASME Standard Code for Pumps and Valves for Nuclear Power - 1968 Draf t including March 1970 Addenda.
[8] See Guide Section 1.29. 3.2.1 for discusion of conformance to Regulatory
- 19) Instrument and sampling lines Quality Group, s6ismic category, and quality assurance requirements are as follows:
A. Instrument lines 1.
From the process boundary through the process root '
valve (including restriction orifice adapter), or, for lines penetrating primary containment, through.
the containment isolation valve or excess flow check valve, whichever applies: same Quality Group, seismic category, and quality assurance requirements as the process line !
- 2. Downstream of the boundary defined in 1, above 1
a.
s sienetrating primary containment and - -
whc ociated instruments are red to Sid Arrawo function rform a e netton ("o-Insgr active") are -
rou , seismic
. Cahyv y 4, and are Ar" Lines penetrating primary .:ontainment 4Dd -
S/A /tr7&MN whose assocint&d instrument required a undar ntegrity fg'g7 ("Q-nass sin their
- _ y=!<*u Groun n yselspic Cate ,
, and are_ 0-Itsted. .
- ~
d- Lines not penetrating primary containment whose associa.ted instruments are Q-active are
- s ,$gi F4 pol ,p f a
" " ' ' ' " ' " ,d,-
. . DRAFT __
F DRAET' TMLE '3 2. - l MGf 30 of ;16 ft)pA [9]. A. 2. st. . f 6 ct. . Q-GROpps A Lines penetrating primary containment and whose associated instruments.are required to function o perform a safety function ("0-active")g Quality Group B, seismic Category ;, and are 0-listed.
fCO$
6, Ci-GA0"# A Lines penetrsting primary containment and whose assoc!ated instruments are only required to maintain their pressure boundary integrity
("Q-passive") e Quality Group' seismic Category I, t '*/ are 0-listed.
occoME' C C.
9 'b#0"# 8 Lines penetrating primary containment and whose associat6d instruments are only required to maintain their pressure boundary integrity
("D-passive") Quality Group D, seismic Category I, ai.d are Q-lis.ted.
/
BEcm c '
l l
4 l s .
l k-1 .%
~
ERAFT .
Mh(l
\
' '=
f.
LGS FSAR TABLE 3.2-1 (Cont'd) (Page 31 of 38)
Quality Group B, seismic Category 1, and D- )
l listed. -
Q. E' Lines not penetrating primary containment whose associated instruments are D-passive are Quality Group D, seismic Category I, and Q-listed. l
- -f* AK Other line. are Quality Group D, non-seismic Category 1, and not 0-listed.
o E Certain ad..pters in non-safety-related, non -
d' listed instrument' lines are not manufactured per ANSI B31.1.
B. Sampling lines'
- 1. From process line to root valve: Same quality group, seismic category, and quality assurance as 1
. process line. 1
- 2. From root valve through sample rack isolation i valve
- a. Sampling lines from 0-listed Quality Group A, B, and C process lines are Ouality Group B, seismic Category I, and 0-listed.
- b. Sampling lines from non-0-listed Quality Group C process lines are Quality Group B or D, non-seismic Category 1, and not 0-listed
- c. Sampling 11aos.from Duality Group D process lines are C Jality Group D, non-seismic Category I, and not 0.-listed. ,
- 3. Downstream of sarnple rack isolation valve Quality Group D, non-seismic Category 1, and not Q-listed i [10)Not used
[11] Components include any assembly of interconnected parts that constitutes an identifisble device or piece of equipment.
For example sup lies, an,d signalelectrical components rocetisors; include sensors, and mechanical power-components inc ude turbines, str iners, and orifices.
, .[13] Refer to Sectidn 7.1 for descriptions of conformance with y .
I m 379, I m 308, I m 323, and I m 344.
Rev. 9, 08/82
'k, .*
~
DRAFT LGS FSAR (3)
Such items are not included in the "0" List.
3.2.2 j SYSTEM 00ALITY GROUP CLASSIFICATIONS General Design Criterion 1 of 10 CFR Part 50, Appendix A, requires safety be that structures, designed systems, and components important to fabricated, erected,
~
standards commensur, ate with their importance to safety.and tested to qualit Components requirementsof forthe Classreactor 1 coolant pressure boundary meet the Mechanical Engineers (ASME) components of the American Society of B&PV Code,Section III, or equivalent Regulatory Guide 1.26, Rev. 3, by 10 CFR Part 50.55.a.
quality standards, as required describes a quality classification system that may be used to determine applicable standards for other components in nuclear power plants. Quality group classifications are assigned to systems and components in accordance with the reliance placed on these systems to:
a.
Prevent, or mitigate the consequences of, accidents and malfunctions originating within the RCPB d i b.
Permit shutdown of the reactor, and maintain it in the
,N a safe shutdown condition M c.
Contain radioactive material
\ ) A tabulation of quality group classification for each co so defined is shown in Table 3.2-1 under the heading, " Quality I
Group Classification."
) The applicable codes and standards of i
N) each given . quality in'"tth group, 2.2 2. as described by Regulatory Guide 1.26, are ef quality group classification of the piping,The valves, locations of these componen and
'j indicated on the system piping and instrumentation diag the pertinent section of the FSAR.
N to FSAR figure number is provided in SectionA cross1.7. reference of system
! Lh System quality group classifications, and design and fabrication requirements as indicated in Table 3.2-1, Regulatory Guide 1.26, except as'noted below. meet the guidelines of i The Limerick design is based on quality group commitments made before. Regulatory Guide 1.26 was issued
( ' alternate approaches to the guide have een 3 and in some cases used, as follows:
-a.
Regarding systems important for reactor shutdown, as
~
c [M discussed guide, in paragraph C.1.b (Quality Group B) of the
- y. the control rod drive (CRD) system hydraulic i - . control units (HCU) are classified as "special
_9 equipment". by GE because the codes and standards of a quality group are not strictly applicable to the HCOs.
ti Rev. 20, 05/83 3.2-4
DRAFT f6-5 YS LGS FSAR A detailed discussion is given in the notes of.
Table 3.2-1.
b.
.The Quality Group B class;fication may terminate on some steam of remotesystem manualconnected closure, piping at the first valve capable automatically, closed valve. rather than at a normally, or Additionally, Quality Group B is applied only to piping 2-1/2 inches in diameter and larger, similar to the guidelines of Regulatory Category Guide 1.29 for application o,f the seismic I classification.
c.
>T;.c Ouality norme!
Occup spcat O. fu;l P;;l cooling sist;c is primarily Section 3.2.1, However, as discussed in provided. backup cooling and makeup sources are These sources are at least Quality Group C, as are the system. connecting portions of the normal cooling d.
The standby in Figures diesel 9.5-9 generator through piping is designed as shown 9.5-12. Supplementary material i certification, design, and examination requirements have been applied to the off-skid portions of the emergency diesel auxiliary systems to ensure that their quality is essentially equivalent to ASME Section III, Class 3.
The Section technical differences III, Class 3 are between few. The ANSI B31.1 and ASME major differences were addressed listed below. by supplemental requirements and are t
l
[Certaincomponentsinthenormalspentfuelpool
! cooling system were designed, fabricated, procured, installed, and tested to the requirements of ASME Section III, Class 3, prior to May 1978. After May 1978, system design, fabrication, materials,.
l procurement, installation, and testing are, at a __
minimum, in accordance with Quality Group D and the intent of Regulatory Guide 1.143, Rev. 1.
DRAFT 3.2-5 Rev. 20, 05/83
If.S PSAS ,.
Jypf .'
TABLE 3.2-1 (Cont'd) ..
(Page a of 38 CUALITY SOURCE GROUP OF P RI NCIP AJ.
lbCA- CLASSI-- CODES AND SWJtECQUE9t*fd!I I *(,1 FSAR SUPPLY TICW SEISMIC FICA
EECn95 __Lll*. ..L232 .LJJ!... ..L132_.. CATEGORY L3Jf.
LIST
. Ial!_ Cg:mguT5 2.
- 3. RCIC barometric condenser Piptnq and valves, RCTB GE R D B 31.1
- 4. P Piping within outersost containment C A III-I II N isolation valves, discharges to P C D B31.1 1
1 Y
f 71 i 91 T es t suppression pool Y I e8 )
S.
- 6. Piping and valves, other safety-related Portion of piping for RCIC P R B 111-2 7.
' turbine drains P R D BJ t. t 1 Y
[93fe81 Deleted ! Y f 551
- 8. Pumos, RCIC condensate and condenser vacuum GE R D
- 9. Pump, RCIC Mr STD II N
- 10. Electrical modules, with GE R B 111-2 safety function GE R,CS - I Y E EE E-323, 1 349, 279 Y fit),f12) 8.
EggMyel Btat.Espoval 3Y35te 5.4.7 1 Heat eachangers, primary (processi side
- 2. Heat eacnangers, CE secondary R B 111-2/TEP A C tservice watert side GE R gb VIII-l/
I Y
- 3. Piping, reactor vessel head spray 1 Y TEMA C line, beyond 1irst isolation valve P C B O
4 Piping, RCP8 III-2 I 5 P Y f 461 Piping, containment sprav line P C A III-t 1 finside containmentt C B Y 6 III-3 1 f 7 3 (9) f e8 3 Piping and
- 7. Valves, valves, other safety-related isolation P R Y
fe8W 581 I B 111-2
- 4. Pumpe GE/P C, R A,8 I Y f481 111-1,2
- 9. . Mot or s, pump GE R B 111-2 I Y (7)
- 10. Mechanical components GE R - 1 Y CE NEMA-MG-t
- 11. Electrical modules, with safety R 8 Mr STD
! Y function P/GE R CS -
I EE E- 32 3, 1 Y f 1I)
- 12. Conta insent eguray nogales I Y f t i l, f 3 2 )
P 344, 279 C -
MF STD C. Cgg.t_serav SYg133 I Y I 59)
- 1. Paping and valves, RCPS .
6.3 g 5 2. Ploing and valves, other P/GE safetv- C A 9~ 3.
rela ted Pumps P R S 111-4
!!!-2 I
1 Y
Y I 71 ( 91 f 481
[ 9 ] [ e81
- 4. Motors, pump CE R B III-2
- 5. Electrical modules, with GE R -
1 Y safety function GE NEM-MG- 1 1 Y R. CS -
IEEE-323 1 Y D. 344, 279 f Il 1. ( 121 H ig h: rg g E 5919.S9914 Dt _lA1EC1190.J UFCI I NYsite 1.. NPCI turbine 6.3
. 2. Piping and valves, RCPB GE R -
- 3. P MF $~0 1 Piping and valves, other safety- P/CE C A III-I I Y f 371 related R B Y f 71 ( 91 ( e81 III-2 1 Y f 91 f 481 Rev. 23, 08/83
.s eS rSAR &
y,,gg ,
. TABLE 3.2*1 (Cont 'd)
- tp4 t, , }t ye 7fALITY SOURCE GaotfP OF .LOCA- PRINO! PAL CLAS$1- COOFS AND 51sIEWS2Mroprw- [=0] PSAR SUPPLY ?!ON !!!SFIC Q-ggc2g:p _,tjje. ,L2J: FICA *t 0M SYANDaJtOS
_tjj:,,, ,,tgj:,,, C%TECORY LIST t}]:,,,, tg.1:, Cp53nn
- e. Ploing, return test itne to condensate sterage tant beyond P R A B, B aw,o 133 2 33gf tg '
. 5. second leolation valve Piping, rema inde r w
P A B, D 6 B31.1 Pumos, HPCI and booster RW,0 11 M 1
Electrical modules, with safety GE R B III-2 I function GE R,CS -
IEEE-323, Y 8
9 HPCI barometric condenser 3t=. 219 i Y f II ), ( 12 )
Pumpe, HPCI condensate CE R D B 31.1 and condenser vacuum G2 R D !! N Mr SYD 31 M
- 10. Piping within out atmoet containmer.t isolation valves, dischargee to P C D B31.1 1 Y suppreeston pool [ e8 )
S t. Portion of pioing for RPCI P turbine drains R D B31.1 E.
I Y (55) I IldsettY.L1991LCgnirpt
- 1. Standby 11guld control 2rs1En 9. 3.5 t tanIt
- 2. Test tank CE R 8
- 3. Piping and valves, PCPB GE R 111-2 1 Y
.#~ D API-620
- 4. Piping and valves, other P 1
((C C N gp safety related , P R A
B 111-1 III-2 I Y ( 7) [ es)
- 5. Piping, service and drain 1 Y
- 6. Pumpe P
[9](e6)
R D
- 7. B31.1 Motors, pump G E, P R 8 111-2 t/I!A N
- 8. Electrical modules, GE, P R
~h NEMA-MG-1 I I with safety function GE C R,CS - IEEF-323, Y I
3te, 279 t Y [ 11), [ 12 )
111 gygL,3YosAGE AND BA29LIf9;EE8CICE.Jff33KL.JIEYICItN
- 4. Storace. Revippetti 9.1.1, 1
Spent fuel storage racks 9.1.2 M[igg O
P R taloo used
- 2. Channel storage rache f or new fuel) -
AA 1 Y
- 3. In-vesse t recto GE R -
- 4. GE Mr $to 11 Defective f uel storage containers CE R -
Mr SYD 1 N
R - Y MP STD I Y B.
Ditl.f991_.C9911ng and_C1980lfD_Ir21te 9.1= 3
- 1. Heat exchangers
- 2. Stimmer surge tante P R C
- 3. P ttt-3/TEMA C 11% N ( 18 1
- e. Filter demineraliser Resin and precoat tanks vessels P R
PW C 111-3 I Y e
C 111-3 t 5 P 11 N [ li )
6 Piping and valres, cooling Inop RW D A PI-6 51 11 M Ploing and valves, RHR intertie P i 181 R C PN91 P ) 1. I
-1 P S B 114 M III-2 I ( 9 ) ( 18 ) [ M 1 f 521 l Y [e8)
Pev. 20/05/d]
i
$e[ $ '
.__.....________. . ______________I!Ott_J 2-1_ICenLinsc1L___ _ ______
____________________________esst_13 Principal Quelity Con st ruc-W rca Group . tion PS43 of Quality Loca- Cla ssi- . a re Codes and 1:stin succit' 1i93 11Gt1190.EJ / sited!IdE Seicoic Assurance Pr in-tpa l Components (640 1 l- Seitsett Etssite!!Di C9 tete 11 (1) * (2)* (3)* .
tyg
- e p, M me.1ttie.Is9ts1190.t trettit Cantt91 3rste,stre
. 6.7 / I
( l g* Piping and valves up to first innlation valve of the inboard /
/
mehststes P R A 1, Piping and valves, other l l !!!-1 1 T P R S 111-2
),81osar anotors l I T GF 9 - '
utaa-nc-1 I T Itt t 32 3/34 4 (3 2)
AFB %A AW '
- 4. McMus 4E R .--
IG'E-3Z3 I Y q 2) sccc-W D D 22
>ri "Il 4
rt i4 d
DRA?T
- . 'e e
LGS FSAR TABLE 3.2-1 (Cont'd) (Page 25 of 38)
NOTES ON LGS DESIGN CRITERIA
SUMMARY
[ 1] GE - General Electric P - Philadelphia Electric Company
[2] Location R - Reactor Enclosure C - Containment T - Turbine Enclosure CS - Control Structure RW - Radwaste and Of fgas Enclosure G - Diesel-Generator Enclosure AB - Auxiliary Boiler Enclosure F - Fuel Oil Pump Structure , l W - Water Treatment Enclosure
~
ST - Sewage Treatment Enclosure A - Administration Building S - Spray Pond Pump Structure SP - Schuylkill Pump Structure PP - Perkiomen Pump Structure CW - Circulating Water Pump Structure 0 - Outdoors, Onsite i
HS - Hot Maintenance Shop
[ 3 ] A,B,C,D - Quality group classificaL'on ahded in-Regulatory Guide 1.26, see also 6 ables 3.2-2 And 3.2.-37
= Not applicable to quality group c assification Rev. 23, 08/83
DRAET (S-56 LGS FSAR TABLE 3.2-1 (Cont'd5 (Page 33 of 38.
feedwater and RCIC line taps (outside primary containment is classified Group B. The RWCU tap into the feedwater line inside primary containment is classified Group B up to the outboard containment isolation valve (41-1016). Valve 41-1016 and piping up to the tap into the feedwater line is classified Group A.
(17)The high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) turbines do not fall within the applicable design codes. To ensure that the turbine is fabricated to the standards commensurate with their safety and performance requirements, General Electric has established specific design requirements for this component in their specification.
(18)Certain major liquid, solid, and gaseous radwaste system components were designed, fabricated, procured, installed, and tested to the requirements of ASME Section III, (Jca95A 0ivisi;r 3, prior to May 1978. After May 1978, system design, fabrication, materials, procurement, installation, and testing are, at a minimum, in accordance with quality group D'and the intent of Regulatory Guide 1.143, Rev. 1, subject to the following clarif.' cations and exceptions:
- a. Certain atmospheric tanks are welded to API /AWS standards in lieu of ASME Section IX.
- b. Curbs or elevated _ thresholds are not provided for indoor tanks because of the watertight integrity of the surrounding structure.
- c. Hydrotest pressure is held for 10 minutes, in accordance with ASME Section III, rather than 30 minutes.
- d. The cadwaste enclosure is designed in accordance with seismic Category-I criteria (Section 3.8.4). Limerick does not use Regulatory Guide 1.60, as stated in Section 1.8. Alternate methods are discussed in Sections 3.7 and 3.8.
- e. Limerick's quality program during construction does not require audits of activities associated with radwaste systems, and items of noncomformance and their-regulation are not always documented.
, f. Cleaning and welding of piping is conducted in
'accordance with the specified piping quality group.
(19)See Section 3.2.2 for discussion of conformance to Regulatory Guide 1.26.
DRAFT Rev. 27, 12/83-
ps nb .
LES PSAF 1
TABLE 3.2-2
- - . . ...__...h._......._.....I.._"_.
. . _ _ _.f. _[.'1.
.. N. . ~$..M. ._,I M" N
CODE CLASSIPICAIIONS CCMPCNENT GROUP A GROUP B GDOUP C CROUP D (El Pressure ASME BSPV Code, Section ASME BSPV Code, Section ASME BCPV Code, Sectica ASME REFV Code, Section vessels III, Nuclear Power Plant III, Nuclear Power Plant III, Nuclear Power Plant VIII, Division 1 Ccaponente-CLASS 1 Componente-CLASS 2 Componente-CLASS 3 Piping As above As above As above(3) ANSI E 31.1 Po u r Piping N PM Pumps W) As above As above As above Manufacturer's Standards Valves As above As above As above ANSI 2 31.1 0-15 psig -
As above As above API-620, or ASME Boiler and Storage Pressure vessel Code Tanks Section VIII, Division 1
( Atmospheric -
As above As above cas AyI-650, Abu D 100, ANSI Storage t 94.1, or ASME Eoiler and Tanks Pressure vessel Ccde Section VIII, Division 1 9
ft) Certain portions of the radwaste. systems meet the additional requirements of Quality Gruup D (Augmented), as defined in NBC Branch Technical Position ETSE 11-1, Parts B.4 and B.S. ~
488 Atmospheric storage tanks fabricated to Grcot C requirements may be u?ed in a Group D or Grcup D (Augmented) system.
O x -m_
- > 0 ri 23 l >
71
-4
w- -.- .
/.x k Y k/tt'qkt()dk-rff?f
~
/
$ h Y $* -
- 3) ASME Section III piping, systems (including pipe sMts) e onstructe in accordance with ASME .*
Section III, 1971 Edition with Addenda through Winter 1971 ex 7pt:
- a. Piping material conforms to ASME Section III, 1971 Editionj or to later Editions or Addenda n -b. Field fabricat. ion, installation, examination and testing are
'(
in accordance with ASMF Section III,
-1974 Edition, with Addenda through Winter 1974.
g c. Paragraphs NC- and ND-4436 of ASME Section III, 1980 Edition with Addenda through Winter 1981 is used for installation of attachments to Class 2 and 3 piping systems after testing.
O < .
- .Tpproved Pipe _ supp_ Marchorts 10, are constructedain accordance ANjiI B31.7
- f in with Addenda with ASM 1971. Snubbers supplied throughwith the ar the AE 1969 Edition g1 -
accordance g i Section III, 1977. Edition with Addenda through Winter 1977 Me QL-bat ir.stallatierr-te in g accordance with the 1969 Edition of ANSI B31.7 with Addenda approved March 10, 1971.
j o. Stress analysis is in accordance with ASME Section III, 1971 Edition with Addenda through Winter ,
1972, except: . ,
- 1. Class 1 piping systems stress analysis is in accordance with the 1977 Edition with Addenda .
through Summer 1979. ,,
- 2. Class 2 and 3 flange stress analysis is in accordance with the 1977 Edition with Addenda .,,,.
through Summer 1979.
- f. Containment penetration flued heads are manufactured in accordance with ASME Section'III with Addenda through Summer 1974 and installed per 3.b above. Diaphragm penetration flued heads are j with A manufacturedinaccordancewiththe1980Editionofthe[codgq/,g_dsfenda nd installed per 3.h above.
throug
- s. ,a +. aw ,s -e isetuds$w~, 3 $Y ids w'sthvyf + 4/db' a n 47K d wa msow/sefsd aum ans~aw,ca<e,,,,A Lg o
_ A,,,,
as & /%9 &Ma / #" m? dA Ad yd sad a, gig 6sk a eadedd'd mmke wW >64 27 Sd4h / 4/mr fee /;,1 as 464
- aagh 4 77
$ 0 71 N I W m ' $d b seds,ee as aprf **l 77awoh Zat'lh ,g'Xj,79iskg,f,,,,es/m-iff,;
/971 ca%6 %
4,. cea ,;oed,6W)oba@/ ;,,44',,,l, ,;g ,g g && '"*"**^ 'M 4
/4 Mf enh? /4wed He %b /976 sagd '" j" P'"PW ^"
,e ,,e D R A _P t
.M G'"# g;rQ s-gr
- y. Sap r snd C a dri-e my 0 l I se s//sded 4 pro s pa;,pq sphw as 1,4 Ashd a sassa a f se er au ~
s/ /4 ses Mi .x ad us AV4J fraph dM Mrs
- f. AWh pads {aklse el y d /iduen l Ayes sd axd a & asasy e/wh) >%/ d a/e /
ff bcA MMas/ //i/46s1 sat nsl dswadde/ A k an AS"'6 ffEwy k'ld//cm/h,for4 opywlessnet.it>s. ow[
sr msdo' d 7/2 anw4ses &M psmpsz,sh A'cd-/.273 d/4 /9fidhid/A ANWh[dd aM' /dd #ap/
dimmes fjd. .
- i. k dsbllba s/ A6supp tVds/ h max /dde 7% myanam lYblNWS/5 A d assit/szes of fa.e NB/N6/AO-pyz?-/
o/Ne /fM 6TdEd sf //s 4/M;C 6f dd 64A .48,da Emy4 : fa r m y # B .
DRAFT
Oggy3 L.GS FSAR FS~5NO 7Ag(E 3.2 .3 '
6.L.AS5 fICAT1M Aab CobE d.BmPL t A stCG REQutzWEN TS Fot. N555 ,M 6CH AN I C AL c o nt P df> c~d T 4
_ ~
ASME III Group Code Classes Components Ordered Components Ordered Classi- 1968 1971 on or after Jan. 1, on or after fication Ed. Ed. 19 70 t_o July 1,1971 July 1, 1971 A A 1 ASME I
, ASME II ASME III, A ASME III, 1
. ASME IX ASME IX ANSI B16.5 ANSI B16.5 ANSI B16.ll ANSI B31.7 ANSI B31.1 NA & NB Subsections ANSI B31.7 I TEMA C NP & VC I Notes G)(5)
TEMA C Note dt)
D B ,C 2, Mdb ASME III,db,C ASME III, 2& Md0 ANSI B31.7,II NA&NC Subsections NP&VC,II NA&NE Subsections TEMA C TEMA C TANKS TANKS fotes Notes (6) 6 -
3 -ASME VIII,Div. l' ASME III, 3 ANSI B31.7, III NA&ND Subsections NP&VC,III TEMA C/ TEMA C TANKS TANKS Notes ($ Notes (5)
'I) - -
ASME VIII,Div. 1 ASME VIII,Div. 1 ANSI B31.1.0 ANSI B31.1.9 TEMA C TEMA C TANKS (O TANKS (3)
Notes (g) Notes (y)
~ ~
NOT ES:
(i) Metal containment vessel (as applicable) and ex tensions of
~ ~
containment only. - ~ * ~ ~ * *
~
^
DRAFT sz 1
TAP 1f 5.z -3 (LO^ t )
l l
1
(?) PECo's request to use alternat:ve codes to those required 1.9 10 CFR Part SC.55a for primary pressure boundary components was sent to the NRC on 7/15/75. The applicable codes, code dates, and addenda are listed in the request letter for the following components which are still included in the Limerick design:
1 Reactor pressure vessel 2' Main steam safety / relief valves 35 Main steam piping (26") from RPV to 2nd isolation valve 4' Main steam line suspension 5' Recirculation pump 6: Recirculation gate valves (motor-operated :
28" suction 28" discharge 7! Recirculation loop piping (28")
- 8) Recirculation loop suspension
- 9) RHR valves 20" gate valve
- 10) Core spray valves 12" check valve (air-operated)
- 11) Nuclear Class I piping (all except main stear and recirculation)
NRC approval of the request was given on 11/18/75 in a letter from R.C. De Young to E.G. Bauer of PECo.
The applicable code for design, fabrication, and testing of the main steam isolation valves is the ASME Standard Code fo'r Pumps and Valves for Nuclear Power - 1968 Draft including March 197C Addenda.
(3 ; Class D tanks shall be designed, constructed, and tested to meet the intent of API Standards 620/650, AWWA Standard D100, or ANSI B96.1 Standa rd for Aluminus Tanks.
(41 For pumps classified Group D and operating above 150 psi or 2120F, ASME Section VIII, Div. 1 shall be used as a guide in ca lcula ting the wall thickness f or pressure retainina parts 'and in sizing the cover bolting. For pumps operating below 150 psi and 21207, manufacturer's s'ta nda rd pump for service intended say be used.
( 5) For pumps classified A, B, or C applicable Subsect ions N B, N C, or ND respectitcly in ASME Boiler and Pressure Vessel Code,Section III shall be used as a guide in calcula ti ng the thickness of p re ss u re retaining portions of the pump and in sizinq cover Dolting.
DRAFT