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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld ML20195G4591999-06-10010 June 1999 Forwards MORs for May 1999 & Revised Repts for Apr 1999 for LGS Units 1 & 2 ML20195H0531999-06-0909 June 1999 Forwards Revised Bases Pages B3/4 10-2 & B3/4 2-4 for LGS Units 1 & 2,in Order to Clarify That Requirements for Reactor Enclosure Secondary Containment Apply to Extended Area Encompassing Both Reactor Enclosure & Refueling Area ML20195E7701999-06-0707 June 1999 Provides Notification of Change to NPDES Permit PA0052221, for Bradshaw Reservoir Facility Which Supports Operation of Lgs,Units 1 & 2,per EPP Section 3.2 ML20195C7631999-06-0101 June 1999 Notifies NRC That PECO Energy Has Completed Installation of New Large Capacity,Passive Strainers on RHR & Core Spray Sys Pump Suction Lines at Lgs,Unit 2,in Response to Ieb 96-003 ML20195D5381999-05-26026 May 1999 Forwards 1998 Occupational Exposure Tabulation Rept for LGS Units 1 & 2. Encl Is Diskette & Instructions.Rept Is Being re-submitted to Reset 12 Month Time Period.Without Disk ML20195B2821999-05-24024 May 1999 Requests That NRC Distribution Lists for LGS Be Updated. Marked-up Distribution List Showing Changes Is Attached ML20196L2891999-05-20020 May 1999 Provides Status Update of Thermo-Lag 330-1 Fire Barrier Corrective Actions,Iaw Commitments Made in ML20195B2951999-05-20020 May 1999 Forwards Rev 0 to LGS Unit 2 Reload 5,Cycle 6 COLR, IAW TS Section 6.9.1.12.Values Listed Have Been Determined Using NRC-approved Methodology & Are Established Such That All Applicable Limits of Plants Safety Analysis Are Met 05000352/LER-1999-003, Forwards LER 99-003-00,re Rps,Pcrvics Actuations.Ler Contains Special Rept Info for HPCI & Reactor Core Isolation Cooling Sys Injections Into Rv1999-05-19019 May 1999 Forwards LER 99-003-00,re Rps,Pcrvics Actuations.Ler Contains Special Rept Info for HPCI & Reactor Core Isolation Cooling Sys Injections Into Rv 05000353/LER-1999-002, Forwards LER 99-002-00,automatic Actuations of Primary Containment & Reactor Vessel Isolation Control Sys & Other Common Plant ESF Due to Loss of Power to a Rps/Ups Power Distribution Panel on 9904191999-05-18018 May 1999 Forwards LER 99-002-00,automatic Actuations of Primary Containment & Reactor Vessel Isolation Control Sys & Other Common Plant ESF Due to Loss of Power to a Rps/Ups Power Distribution Panel on 990419 ML20206E2001999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept (Non- Radiological) for Limerick Generating Station,Units 1 & 2. Rept Submitted IAW Section 5.4.1 of App B of Fols,Epp (Non- Radiological) & Describes Implementation of EPP for 1998 ML20206D8801999-04-27027 April 1999 Forwards Rev 2 to LGS Unit 1 Reload 7,Cycle 8 COLR, IAW TS Section 6.9.1.12.COLR Provides cycle-specific Parameter Limits for Noted Info ML20206A5461999-04-21021 April 1999 Responds to Conference Call Between Util & NRC on 990420,re TS Change Request 98-07-2,revising TS Section 2.0 to Incorporate Revised MCPR Safety Limits.Attached Ltr Contains Info Requested ML20205T0441999-04-17017 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept 15, IAW TS Section 6.9.1.7.REMP for 1998,confirmed That LGS Environ Effects from Radioactive Release Were Well Below LGS TSs & Other Applicable Regulatory Limits ML20205Q7581999-04-15015 April 1999 Forwards Response to RAI Re ISI Program First & Second 10-Yr Interval Relief Requests.Revs to Identified by Vertical Bar in Right Margin 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K3671990-09-14014 September 1990 Informs of Revised Commitments Re Crud Induced Localized Corrosion Related to Fuel Cladding Failures.Deep Bed Demineralizers Installation Activities Will Be Performed in Unit 1 Subsequent to Third Refueling Outage ML20065D4421990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Proposed Schedules for Operator Licensing Exams, Requalification Exams & Generic Fundamental Exams Encl ML20064A5831990-09-0707 September 1990 Responds to Violations Noted in Insp Repts 50-352/90-17 & 50-353/90-16 Re Differential Pressure for Pumps.Corrective Actions:Licensee Will No Longer Use Expanded Ranges as Acceptance Criteria for Inservice Testing Program Tests ML20064A4821990-08-31031 August 1990 Forwards Rev 20 to Emergency Plan.Changes Necessitated by Annual Emergency Plan Update & Administrative in Nature ML20059E6071990-08-29029 August 1990 Forwards Semiannual Effluent Release Rept,Jan-June 1990 & Rev 8 to Odcm ML20059B0751990-08-24024 August 1990 Forwards Rev 0 to Updated FSAR for Limerick Generating Station,Units 1 & 2,Vols 1-19.W/one Oversize Encl. Proprietary Vol 7A (App 3B) Withheld (Ref 10CFR2.790) ML20064A6471990-08-24024 August 1990 Forwards Public Version of Revised Epips,Consisting of Rev 10 to EP-101,Rev 2 to EP-112,Rev 13 to EP-208,Rev 11 to EP-230 & Rev 22 to EP-291 ML20059E9861990-08-24024 August 1990 Provides Justification for Applicability of Reload Methodology Topical Repts to Facility & Requests NRC Approval for Application of Reload Analysis Methodologies ML20058N9591990-08-13013 August 1990 Forwards Revised Response to Violations Noted in Insp Repts 50-352/90-13 & 50-353/90-13.Corrective Actions:Ltr Issued to All Plant Personnel Providing Instructions on Proper Use & Handling of Controlled Documents in Controlled Locations ML20058N1771990-08-10010 August 1990 Responds to NRC Re Unresolved Items Noted in Insp Repts 50-352/90-80 & 50-353/90-80.Plant-specific Technical Guideline Has Been Revised to Ref Contingency Numbers Rather than Transient Response Implementation Plan Procedures ML20063P9461990-08-10010 August 1990 Provides Plans for Ultimate Disposition of Recirculation Inlet Nozzle to Safe End Weld Indication.Alternative Corrective Actions to Disposition Nozzle to Safe End Weld Indication Include Repair by Weld Overlay W/O Monitoring ML20058N1281990-08-0909 August 1990 Forwards Correction to Rev 10 to EPIP EP-234, Obtaining Containment Gas Samples from Containment Leak Detector During Emergencies ML20058N1991990-08-0909 August 1990 Advises of Change of Address for Correspondence Re Util Operations.All Incoming Correspondence Must Be Directed to One of Listed Addresses ML20058P1261990-08-0909 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Limerick Units 1 & 2 & Rev 1 to June 1990 Rept ML20058M9951990-08-0808 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-352/90-15 & 50-353/90-14.Corrective Actions:Personnel Counseled on Importance of Procedure Compliance & Operations Manual Revised ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML20055J0241990-07-26026 July 1990 Forwards Response to NRC Regulatory Effectiveness Review Rept for Plant.Response Withheld Per 10CFR73.21 ML20056A9731990-07-25025 July 1990 Forwards Facility Written Exam Comments for NRC Insp Repts 50-352/90-10 & 50-353/90-11.Written Exam for Reactor Operator & Senior Reactor Operator Considered Comprehensive & Thorough ML20055H8511990-07-24024 July 1990 Responds to NRC 900720 Request for Addl Info Re Util 900516 Request for Exemption from Full Participation During 1990 Onsite/Offsite Emergency Exercise.Nrc Region I & FEMA Support Feb 1991 Exercise,Per 900718 Telcon ML20055H8331990-07-20020 July 1990 Submits Change of Addresses for Correspondence Re Util Nuclear Operations ML20055H0231990-07-12012 July 1990 Forwards Public Version of Revised Epips,Including Rev 10 to EP-210,Rev 19 to EP-231 & Rev 13 to EP-237 ML20044A1041990-06-22022 June 1990 Forwards Application for Amends to Licenses NPF-39 & NPF-85, Consisting of Tech Spec Change Requests 90-03-0 & 90-04-0, Revising Surveillance Requirement 4.9.6.1 for Section 3.9.6 Refueling Platform Re Main Hoists/Auxiliary Hoists ML20043J0371990-06-20020 June 1990 Forwards Description,Scope,Objectives for Plant 1990 Annual Emergency Exercise Scheduled for 900920,per 890809 Ltr.Util Will Submit Revised Objectives for Exercise to Reflect Limited Participation,If Exemption Request Approved ML20043H6081990-06-19019 June 1990 Corrects 900427 Response to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing - 10CFR55 & Conforming Amends. ML20055C7621990-06-18018 June 1990 Informs NRC of Plans Re Licensing of Senior Reactor Operators (Sros) Limited to Fuel Handling at Plants.Util in Process of Implementing New Program for Establishment & Maint of Licensed SROs Limited to Fuel Handling at Plants ML20055C7471990-06-15015 June 1990 Requests That Listed Operator Licenses Be Discontinued ML20043G1331990-06-14014 June 1990 Responds to NRC 900614 Ltr Re Violations Noted in Insp Repts 50-352/90-13 & 50-353/90-12.Corrective Actions:Boxes of Completed Procedures Improperly Stored Shipped to Util Storage Vault by 900406 ML20043G9981990-06-12012 June 1990 Forwards, Core Operating Limits Rept for Unit 1 Reload 2, Cycle 3 & Core Operating Limits Rept for Unit 2,Cycle 1. Repts Submitted in Support of Tech Spec Change Request 89-13 Re Parameter Limits,Per Generic Ltr 88-16 ML20043G7311990-06-0808 June 1990 Provides Addl Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Welds Examined During Last Refueling Outage Addressed ML20043G7501990-06-0808 June 1990 Requests Withdrawal of 900516 Tech Spec Change Request 90-11-1 Re Extension of Snubber Visual Insp Period.Change No Longer Needed Since Unit Shutdown on 900605 & Visual Insp of Three Affected Snubbers Performed on 900607 ML20043F8021990-06-0808 June 1990 Forwards Monthly Operating Repts for May 1990 for Limerick Units 1 & 2 & Revised Pages to Mar 1990 Rept for Unit 2 & Apr 1990 Rept for Units 1 & 2 ML20043D8101990-05-29029 May 1990 Forwards Application for Amends to Licenses NPF-39 & NPF-85, Consisting of Tech Specs Change Request 89-07 to Relocate Radiological Effluent Tech Specs to ODCM or Process Control Program,Per Generic Ltr 89-01 ML20043E6571990-05-25025 May 1990 Forwards Public Version of Rev 135 to Epips,Including Rev 11 to EP-202,Rev 14 to EP-282,Rev 12 to EP-284,Rev 8 to EP-312 & Rev 9 to EP-410.W/DH Grimsley 900607 Release Memo ML20055C5121990-05-18018 May 1990 Provides Info Inadvertently Omitted in Re Property Insurance Coverage for Plants.Limerick Generating Station Unit 2 Should Have Been Ref as Being Included Under Insurance Coverage ML20043A7881990-05-16016 May 1990 Requests Exemption from Requirement to Perform Biennial full-participation Onsite/Offsite Emergency Exercise for Plant During 1990 ML20055C4851990-05-15015 May 1990 Forwards Annual Financial Repts for 1989 for Philadelphia Electric Co,Pse&G,Atlantic Energy,Inc & Delmarva Power & Light Co ML20043B1501990-05-14014 May 1990 Forwards Public Version of Rev 134 to Epips,Consisting of Rev 10 to EP-230,Rev 4 to EP-255,Rev 1 to EP-302,Rev 7 to EP-304 & Rev 3 to EP-314.Release Memo Encl ML20043A2361990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-352/90-07 & 50-353/90-06.Corrective Actions:Sampling Review of Plant Baseline Data Will Be Performed to Ensure Product Code Number Correctness for Components ML20042F4481990-05-0101 May 1990 Advises That Plant Transient Response Implementing Plan Procedures & Related Ref Matls Provided to Dj Florek,Nrc Region I,On 900430.Documents Provided in Response to NRC 900327 Ltr Re Preparation for Planned NRC Insp of Procedure ML20042E8741990-04-27027 April 1990 Responds to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing. Certifies That Limerick Operator Requalification Training Program Renewed on 900125 & Peach Bottom Subj Program Renewed on 890622 ML20042E0881990-04-0909 April 1990 Forwards Addl Info Re 891011 Tech Spec Change Request 89-09 to Reduce Number of Suppression chamber-to-drywell Vacuum Breakers Required to Be Operable ML20042E0201990-04-0606 April 1990 Forwards Vols 1-3 to Preservice Insp Summary Rept, & Books 1-3 to Form NIS-2 for Preservice Insp Interval 1985-1990, Per 10CFR50.55a(g) & ASME Code Section Xi,Paragraph IWA-6230 ML20012E2151990-03-20020 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' for Peach Bottom.Response for Limerick Generating Station Will Be Provided by 900504 ML20012C2931990-03-12012 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey, Per 900118 Request ML20012D9511990-03-0909 March 1990 Forwards Public Version of Revised Epips,Including Rev 10 to EP-203,Rev 12 to EP-317 & Rev 18 to EP-292.W/DH Grimsley 900322 Release Memo ML20012A3631990-03-0101 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-353/89-32 on 891211-15.Corrective Action:Util Will Document Both Receipt & Shipment of Fuel Loading Chambers on Next Semiannual Doe/Nrc Form 742 ML20012A1151990-02-28028 February 1990 Forwards Semiannual Effluent Release Rept 11,Jul Through Dec 1989 & Annual Tower 1 Joint Frequency Distributions of Wind Direction & Speed by Atmosphere Stability,Rept 5 for 1989. W/O Annual Tower 1 Rept ML20012A2621990-02-16016 February 1990 Forwards Public Version of Revs 124 & 125 to Epips, Consisting of Rev 9 to EP-201,Rev 20 to EP-291 & Rev 21 to EP-291 ML20006E7731990-02-16016 February 1990 Requests Discontinuation of Listed Operator Licenses ML20006E6511990-02-15015 February 1990 Discusses & Forwards Results of Field Verification Testing of Unit Spds,Per Licensee Commitment to Submit Rept within 30 Days After Unit SPDS Declared Operational.No Significant Problems Encountered W/Spds During Power Ascension Testing 1990-09-07
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ __
d' . ,
,e e
e-PHILADELPHIA ELECTRIC CON'PANY 2301 M ARKET STREET P.O. BOX 8699 f
PHILADELPHIA. PA.19101 Cuw A R D G. B AU ER. J R. 2isi e4i-ww
.......s.o..,
a.o.. ..am.a..s.6 IsUG ENE J. BR ADLEY associate es.a.a6 cousesst DON ALD SLANKEN i CUDOLPH A. CHILLEMI
/ 9 C. C. MIR K H A LL T. H. M AHER CORN ELL ,
PAUL AUERBACH assista.T o.ms. A6 c ou-sek
)
EDW ARD J. CULLEN. J R.
THOM AS H. MILLER. J R.
l'.E N E A. Mc M EN N A assesTaNT CoWNsEL Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nucicar Regulatory Commission Washington, DC 20555
Subject:
Limerick Generating Station, Units 1 and 2 Request for Information from the Power Systems Branch
Reference:
Meeting with the Power System Branch Reviewer s E. Tomlinson, and Philadelphia Electric Company on March 9-10, 1983
Dear Mr. Schwencer:
The attached documents are draft revisions to the responses to questions 430.68, .72, .7S, and .114.
These changes will be formally incorporated into the FSAR revision scheduled for June, 1983.
Sincerely, Euge e J. radley JTR/bls/D-12 00 cc: See Attached Service List 8305180419 830513 DR ADOCK 05000352 PDR
0 - . .
cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Judge Peter A. Morris (w/o enclosure)
Troy B. Conner, Jr. , Esq. (w/o enclosure)
Ann P. Ilodgdon (w/o enclosure)
Mr. Frank R. Romano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Mr. Marvin I. Lewis (w/o enclosure)
Judith A. Dorsey, Esq. (w/o enclosure)
Charles W. Elliott, Esq. (w/o enclosure)
Mr. Alan J. Nogee (w/o enclosure)
Thomas Y. Au, Esq. (w/o enclosure)
Mr. Thomas Gerusky (w/o enclosure)
Director, Pennsylvania Emergency Management Agency (w/o enclosure)
Mr. Steven P.11ershey (w/o enclosure)
James M. Neill, Esq. (w/o enclosure)
Donald S. Bronstein, Esq. (w/o enclosure)
Mr. Joseph 11. White, III (w/o enclosure)
Walter W. Cohen, Esq. (w/o enclosure)
Robert J. Sugarman, Esq. (w/o enclosure)
Rodney D. Johnson (w/o enclosure)
Atomic Safety and Licensing Appeal Board (w/o enclosure)
Atomic Safety and Licensing Board Panel (w/o enclosure)
Docket and Service Section (w/o enclosure) l l
I i
- maj m
.M u e Me 4'60.~1'5 -'- _ -
~~C
~~ ~
!D esel generator auxi11ary systems piping and components are
! c..assified in the TSAR text and Table 3.2.1 as conforming to ASM* _ _
Section III Class 3, ANSI B31.1, or manufacturer's standard. It t is not entirely clear where the respective classifications begin or end. In any event, this is not acceptable. We require the
- entire diesel generator auxiliary systems to be designed to ASME Section III Class 3, or Quality Group C, in accordance with
! Regulatory Guide 1.26. Revise your TSAR accordingly. Also, -
provide the industry standards that were used in the design, ~ -
j manufacture, and inspection of the diesel engine mounted piping ,
~*
and components. Revise the appropriate P& ids to show where [
quality group changes occur. !
_3 N Oo%AN r
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. _ _ _, :w.ckem_. 3 2 ~2.A_he__h v<.hdk.ho _^ M v<.2 N
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4
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- w-ve .a em,,w. .me.mm -=a.m,9 - -m-= +='er-h-** " * = ' - * " " + * * * * * *8"'""
ma. , 4.. m e---4---. maut e+--- e-=m-i---*'~e = = * '* * **" ** -" * " ' - ' * *" ' * ' *N"*'"*" ' * ' *
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.~. .
LGS FSAR
- (; OUEST10N 430.75 (Sections 3.2, 9.5.4, 9.5.5, 9.5.6, 9.5.7,
, 9.5.8)
Dj esel generator auxiliary systems piping and components are cJassified in the FSAR text and Table 3.2.1 as conforming to ASME Section III Class 3, ANSI B31.1, or manufacturer's standard. It is not entirely clear where.the respective classifications begin or end. In any event, this is not acceptable. We require the entire diesel generator auxiliary systems to be designed to ASME Section III Class 3, or Quality Group C, in accordance with Regulatory Guide 1.26. Revise your FSAR accordingly.
Also, -
provide the industry standards that were used in the design, manufacture, and components. and inspection of the diesel engine mounted piping Revise the a quality group changes occur. ppropriate P& ids to show where
RESPONSE
F The diesel generator auxiliary systems are the following: l
- a. Fuel oil system (Figure 9.5-8) l
.- b. Cooling water system which includes the jacket water
(; cooling loop and the air cooler coolant loop (Figure 9.5-9) j
- c. Starting system (Figure 9.5-10)
{
- d. Lubrication system (Figure 9.5-11) l
, e. Combustion air intake and exhaust system (Figure 9.5-12) l Piping and equipment ~~in these systems is provided in accordance with ASME Section III Class 3, ANSI B31.1, and manufacturer's
'3standards
. ,2 e, asJindicated W 9. 2.2.on. d. the above referenced figures #addFTable [
l All piping and equipment has been designed to withstand seismic accelerations and operating loads, regardless of design code. .
l
' The manufacturer has developed a highly reliable engine piping system over the 44 years that the design of this basic engine has been in use. .
The design code used for each piping seismic segment or component i
meets or exceeds the commitment made in the Limerick PSAR, Appendix A_and Figure _ A.11 y
/_
- w. .
.. i.2.2.a w e m ,,AR ..
- 'i D p g g 7' /.
,(
-. / ,
g -
-~ ,.>
Limeribk" T , . _
ASME III Supplementa'ryd ' ,.
~
ANSI D21.1 Requirements -
Class 3 -
~
Requires ASME Requires materials AS$ materialt'were [
materials and that conform to procured and CMTRs .
certified.., either ASME or were supplied ' '
material test ASTM specification 3 reports (CMTR) s for all piping ' _'
larger than m 3/4 inch nomi ,_q nal pipe size..-- - ,
Certificates '
of compliance' s-may be substi- '
Y tuted for CMTRs S' for' piping less '
s ' '
. 4 that 3/4 inch.
^r s
Req 5i$essais- pequ' ires des 14n PipincjNs designed for pressure,'t 'to seismic Category .
mic design'in s addition to temperature, and I with minimum wall .
the B31.1 and normal opera- thicknesses in con
- requirements ting loads. formance with e ASME III, Class 3.
Requires lig- {feqyires only All pipe welds
- uid penetrant, visual inspection greater than magnetic retti- of welds at the 2 incheG are cle, or radio-design pressure radiographed.
w graphic exami- and temperature nation for of the auxiliary circumferen- systems. J s
~
tial welds .
greater than 2 inches nomi nal pipe size.
1 Requires initial All piping is Requires pneu- '
matic testing service leak test pneumatically , _
tested to 1.25 x as 1.25 x de- desiQn pressure.
sign pressure >_ ;-
/ / / / / 1 > s s / . ,,
s / / / 1
/ / / / / / / / / / .d / / /
/ / .
+ .
t Rev. 19. W 53 3.2-6
b[
, . W@
The on-skid piping and components in-the diesel-generator auxiliary systems were provided in accordance with ASME Section III Class 3 or X manufacturer's standards, as shown in Figures 9.5-8 through 9.5-12.
Auxiliary system components were supplied to ASME III[3 to the greatest t- exten$' practicable at the time of procurement. The referenced figures indicate that this encompasses most of the equipment within the main process loop of each skid-mounted auxiliary system.
f i
l All skid-mounted components, regardless of design code', have been designed to withstand seismic accelerations (Seismic Category I) as well as normal diesel operating loads. Each assembled diesel-generator skid was subjected to a series of operating tests including load acceptance and rejection, air start capacity, variable load, overspeed, 300 hr.
M , normal operating, and contract acceptance tests. In addition to the operating tests, specific component tests milis, were condue' ed 06 Mi<did OW-
- 1. Fuel Oil Injectors - These were functionally tested and calibrated to deliver a metered amount of fuel to the combustion chamber. Each injector has a unique serial number which permits trahbility 4e % shop test and calibration records. '
- 2. Flexible Hose Assemblies and Pipe Coupling Connectors -
These components (located as shown in Figures 9.5-8 through Yaev skL 02.
9.5-12)g manufacturchinique design faguiremtiab t.chich art,ustd ko htsovt flexibility in the piping systems)and are not supplied
/
rQ w-.
g 2
toASMEIII[3. Ilowever, these components were fabricated in accordance with engineering specifications and each component was hydrotested to a pure. gran%r b 125 t;mes design pressure.
- 3. ASMEIII[3andNon-ASMEIII[3 Piping-Allpipingsystems
[ardlessofdesigncode were hydrostatically tested to 1.5 times the design pressure . These tests are documented in the shop test records, All diesel components were supplied or manufactured in accordance with the s.ngpite/s ~ quality control standardsee,ivdicaked belous'
- 1. SubsuppliedComponents-Designandprocurementcontrolswere l
l '
l used in the procurement of all subsupplied components. These components were purchased to detailed engineering specifications and drawings. Upon receipt, all components (or a representative sample) were inspected against the specification, drawings and purchase order requirements, and affixed with appropriate tags to be removed at the point ek ute M %4 manufacturing cycle. Periodicreviewsof wego emluc$ed subsupplier performance and audits of vendor records to ensure that the quality of the items provided remained acceptable.
Typical examples of subsupplied items procured under this program 4.cluda .
a) Air start solenoid valves, filters,91strainers *,
and compressors
&y(
b) Inlet and exhaust expansion joints and the exhaust silencer c) Motor driven fuel oil, jacket water, and lube oil pumps 1
d) Combustion air caolers, lube oil and jacket water standby heaters 4t-e) Fuel and lube oil strainers f) Jacket water, air cooler coolant, and lube oil thermostatic bypass valves I l
l g) Electrical and pneumatic instrumentation and controls. l
- 2. Supplier-Manufactured Components - Equipment and components designed and manufactured by the diesel-generator suppthr were designed in accordance with WriBae daMy Cc%kve\ proc.adw
.amunnen which required appropriate reviews and approvals of all detail drawings, specifications, procedures and instructions.
During the manufacturing process, visual inspection, dimensional l
checks, final inspections, and customer hold and witness points were utilized. Procedures wereDeveioped and ukhut for rejectO a A ponents, recall of materials, and internal audits.ETypical examples of supplier-manufactured components I
incorporating the above . standards include the following:
~
DRAET a) Air admission check valves, pilot valves, and air start distributort b) Engine-mounted intake and exhaust air piping, scavenger air receivers,gevacuation system components c) Fuel injectors, dirty fuel drip tank, fuel and oil drip pan d) Governor control linkage.
The above standards are fully documented in the diesel-generator suppliers' Quality Assurance Plan which addresses the eighteen criteria l contained within 10CFR50, Appendix B. It is uwl $or all diesel l
generators supplied by this manufacturer for use in nuclear plants, 1
i-and has received the approval of the appropriate operating utilities and the NRC.
obeve The conhras desc.nbd gwere usaml Soc. all piping and components supW.d A dim genwoAcv wa 4tlunw. b a&&lMm, assuuss the applicant invoked supplemental quality M requirements on the following diesel-generator and auxiliary system components:
1 Subsupplier Items:
Generators, generator controls, and static exciters Starting air receivers and inlet valves
- .Iacket water, lube oil and air cooler coolant heat exchangers
E' .
-e-DRAET Lube oil strainers and filters Governors Inlet air filters Turbochargers Fuel oil day tank i Lube oil storage tank Jacket water expansion tank.
- 2. Diesel-Generator Supplier 4fanufactured Items 1 Engine blocks Sukaseoilpan Cylinder liners Exhaust belts Pistons and piston inserts Crankshafts and connecting-rods Vertical drive assembly wd Scavenging air blower gears, housings mpellers Engine-driven lube oil, jacket water and air cooler coolant pumps Jacket liners Skid-mounted piping and valves provided to AS>lE III/ 3.
The additional quality assurance requirements invoked by the applicant include: (1) periodic documented subsupplier audits (including plant visits); (2) review and approval of subsupplier QA programs and manuals)
(3) test and inspection audits; (4) calibration of test gauges before and after use; and (5) control of calibration records and acceptance devices.
A '
.' -Q.
OM* Mew 40,,
h'ith the(above design, manufacturing and testing control $,e + .
E'" 'o the on-skid and off-skid piping and components e,e equivalent to Quality Group C. ko*e heew Mg
- N- h GidCLArca.\ (,, punt., ) hphk%
hu Sbs W s,h.'-of3, h h - e A g v %.staa .
ko hiswJ.c. hI a.u.dAs.. Mtvvwabg =$s. og 4
b:sAs t>L+s%,N g cagu.g . AtwwaJs win be. ephe Mov- o
% % 6 \ e k,- h e k. & A v.a t w s. @
i.s& g b u g g os6& a ;h e ,
l itw% subgchd.
1 1 covenu.a mm & 5. 2 -U l
uow.u,% y u b&Ap9onaa2.ka*i&Dib A
,a s e g n aa l
~ - _ _ _ _ _ _ _ _ _ . _ _ . _ . _
DRAFT
~
r' .
%oh % T7_ l
.. Describe your design provisions made to protect the fuel oil
! storage tank fill and vent lines from damage by tornado missiles.
l I
._tZo v h n A k a.s o a v a .-
i
._ -W _N % _ .1 . .M.4C.MMk l
.lo_s6._hk_h_k L A9_gh, Aud ed sbwghde Ji h &_ m a ans, A b_w % _m m q u _h l ..h_wdh_h g A._gAovn.Ao_vva.uua,._A. a&A.h,__ -
f A,_vtssv.d._us.pw.2M_M_nueu._4.__% _u>eys l
%de Q_%vm&sarGa.,_ Des:yyourmw
.__lh vvtA_Ao_ abw3pv_cmWwe . epm mgAa,
! Atsa p ura.bys. __. _
i e--m.e.- w wme.e.
em m-
=
me .i-_
""h* '-m _w.-+-emma.+%- mm-mummmminis-_m....
"" * " " = - +* .-m,--- -my.,_ ..w_. m ,
- +--+*m- e i,e,e .---we-- ,m_ __ , ,,__ ,, , , . , , , , . - , , _ _,, _ , , , , __ _, ,
-* - - * - *-*****6e- -me--m=.ausmae.. , , , , . _ , _ , , . . ,, , _ _ _ , _ ,, _ _ _ ,
c ~OUESTION (Srcticn 430.729.5.4) DRA"FT Describe your design provisions made to protect the fuel oil storage tank fill and vent lines fror, damage by tornado missiles.
RESPONSE
- y %
The 1 and vent lines have a minimum extension above ground The ven ne for each tank is backed up by a separate m l relief valve e, making the probability of lo oth lines very low. Altern aths of filling /ve e.g., manhole of tank) are available fo e in th ely event of damage by tornado missiles. Cross co tons are also'provided in the ach diesel to allow any fuel oil supply and n lines diesel to be s ed from any storage (Figure 9.5-8).
Credib) nado missile damage to the fill r a vent line I
not affect the safe shutdown of the plant.
- d N A kwek &
(
(
l 430.72-1 Rev. 12, 10/82 e
be .
~
DRAFT r c,4 ana nian c _u. a sui S n en y knJa kr pixvided en copl3 ood ha %y4 ;
qa udequaJ comma _1eabr, es c4owu_)s P,9u a 9.G-3, Med b, G <el 1% le & egalyd_wK a separk a ?sv!
gonL vn r Ii m M H 4iI co nn ecHaa_ cud th v a r- !i,g en-eal ,,f q m;amd d; & e_a],ao .L_,,a l
).u_-)% w h/ - x v e-a- o C s L w w L _yh s m J . m isc; h ;
4LL1lsmy es19u Astr.<m o/e._pamn- in %_sysk L ak < chin uJ opuckin_& LA%,Lu a) Alnak p<As_&i co'IHy mLuah_ysd hak o <e o us u , b la. c g > n, L A ,c w u b). % vea lia L end huk it ka& dup
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},Consideradesignb.asisseismiceventcoincidentwithlossof _
yoffsite power and failure of all non-seismic llequipment/ components. Under these conditions, discuss how
' minimum lighting levels will be maintained in.the control room ,
until such time as the emergency diesel generators have come on line and emergency ac lighting has been restored. Using these same conditions, state whether lighting would be required in any
/
iother part of the plant for the time interval between loss of foffsite power and availability of onsite power.
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" y.:axp LGS FSAR -
3 s gi g:?: g OUESTION 430.68 (Section 9.5.3)
Consider a design b. asis seismic event coincident with loss of offsite power and failure of all non-seismic equipment / components. Under these conditions, discuss how minimum lighting levels will be maintained in the control room until such time as the emergency diesel generators have come on line and emergency ac lighting has been restored. Using these same conditions, state whether lighting would be required in any other part of the plant for the time interval between loss of
. offsite power and availability of onsite power.
RESPONSE
During a design basis seismic event coincident with loss of offsite power and failure of{th: non : icei de preer ceurce, the cc:ntr:1 :::: :nd ;ener:1 :r- p?:Et lighting r!!! be rect: red vi:
"O Opereter actier
-theerer;enryecli;htin;[l_hir??recendr.
i: re;. ired durin; thic t e period for th: ::f: Chutd un of th; pl:nt. nder this
- 100:
postpted scen rie, all areas of the plant 1i;htin; fer ih10 chert ti=0 peried;
-wi!! :::periene teurver, n 0; crater 7. tier in required ir :ny of the :::::
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430.68-1 Rev. 13, 11/82
% e.s. m . r. LGS FSAR u
- b. Emnroency de Lichtino DRAFT (
Emergency de lightir.g consists of a combination of ac-dc lighting fixtures r.ormally supplied from the Class IE buses. Upon loss of the Class 1E ac source, an automatic transfer switch transfers this lighting immediately to the 125V de non-Class 1E station battery source. The 125V de non-Class 1E station battery source ,
will provide power to the emergency ac-dc lighting system for one hour .All emergency ac-dc lighting fixtures are incan scent type.
Q3ngggg& Emergency lighting in remote structures and areas where U the above de source is not available consists of battery-powered self-contained units.
Emergency de lighting fixtures and illuminated exit signs are located in the control room, stairways, and along exit routes from each floor throughout the plant.
Table 9.5-12 identifies the illumination intensities for the vital and hazardous areas where emergency lighting is provided for normal plant operation and and the evacuation of personnel in the event of an accident. The table provides both the normal and emergency operating conditions for these areas. These illumination levels conform to the IES Lighting Handbook recommended levels. Column 4 of Table 9.5-12 shows the 125V de power-supplied lighting illumination intensity levels that are maintained in the control room and other areas of the plant between loss of offsite power and availability of onsite power.
Table 9.5-13 identifies the areas where remote actions are re' quired to safely shutdown the plant in the event of a control room fire, auxiliary equipment room fire, or a failure of the remote shutdown system. The lighting levels provided at these locations is shown.
The emergency ac/dc lighting system provides approximately 10 to 20 percent of the total lighting of the plant. The percentage of t emergency lighting fed from each division of Class 1E power is as follows:
- a. Division 1 = 6%
- b. Division 2 = 32% '
- c. Division 3 = 12%
- d. Division 4 = 50%
The emergency lighting load is not divided equally among the four diesel generators due to plant utilization. Emergency lighting, both ac and de, has been provided for all areas shown in Table < .
(
9.5-13. In these areas, the loss of the diesel generator would Rev. 19, 04/83 9.5-26 1
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LIGHTING SYSTEM .-
INTENSITIES OF ILLUMINATION l i
j Normal Maintained l BneLuency Lighting - Foot Candles l l Foot Candles i AC Supplied l DC Supplied l i
QCATION(1) 3 1 1 1 1 l 30 10 Silhouette l l ment (PGCC) Room l l l 1 1 1 1 I l i I i i 1
om El. 269'-0a j 100 l 20 l 3 l I -1 I I j
1.
- (circulating Water j 20 l Silhouette j l '
! I I I I l
- 1 1 1 'l Room El. 2548-0a j 30 l 10 l Silhouette 1 1 1 30 j 10 l 3 i l Room El. 239'-0" l ,
l l '
Room El. 289 l 30 l 10 l .:fEMneme44e-3 l l t I i I .
1 1 j Area El. 217'-0a ;
30 l Silhouette j l 1 ; l m I trol Room to Emerg. l As indicated by l l l
. j applicable areas j j l l
! j below l 5 l Silhouette j i
l i I I
- trol Room to Reactor' j As indicated by .j j .[ .
l applicable areas l l l below ,
l re j refueling floor -30 l l l -
operating areas -20 l l l
- non-operating -10 l Silhouette l l .
331'-0" l areas j j j -
1 I L I "rd
'r Enclosure { l l l '
0" ,
30 l 10 ,
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DRAFT dh NM,Mi -
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The diesel engine exhaust' piping shown'on Figure 1.2-36 is not in
' - ' ~
concurrence with the description in Section 9.5.8. Figure 1.2-36 shows a 45 degree fitting at the end exhaust piping, while the text discusses an elbow at the same location. Revise your FSAR to resolve this inconsistency. Also, expand your FSAR discussion to show how the presence of water, dust, ice, or snow in the exhaust system would be detected and what provisions will be made for removal of same. _ , , , ,
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