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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] |
Text
j s i PHILADELPHIA ELECTRIC COMPANY LIMERICK GENER ATING STATION ,
P. O. BOX A S AN ATOO A. PENNSYLV ANI A 19464 1
tais) 327 troo ==t.
" ' ^ " , ' ' ' , " , ",, , ' , * " , ' , ' , " " " ' ;
6...................... Docket No. 50-353 License No. NPF-85 e U.S. Nuclear Regulatory Commission !
ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Limerick Generating Station, Unit 2 Response to Recommendations Noted in :
Inspection Report No. 50-353/89-32 The NRC letter dated January 31, 1990, transmitted Inspection Report No. 50-353/89-32 for the Limerick Generating Station, Unit 2. This inspection covered selected TMI Action Plan Requirements (Post Accident Sampling Systems - PASS). This letter requested that we respond to the noted recommendations contained'in this report within 60 days. The attached response restates each recommendation identified in the January 31, 1990 letter followed by our response.
I If you have any questions or require additional information, please do not hesitate to contact us.
i Very truly yours, i , i l
l WGS:nik Attachment cc: W. T. Russell, Administrator, Region I USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS 9004110159 900330 0
' PDR ADOCK 09000353 I Q PDC 8 n -
i
, ATTACHMENT 1 Paga 1 of 8 i 50-353/89-32 '
Reply to Recommendations Regarding .
The Post Accident Sampling System POST ACCIDENT SAMPLING SYSTEM, ITEN II.B.3 ITEM 1 '
NRC Recommendation (Ref. 4.5.1 (pg. 5))
Procedure EP-231, " Operation of Post-Accident Sampling System (PASS)", does not specify dose rate limits for PASS samples. Specific numerical guidance is not given in Procedure EP-231 but rather statements.such as "acceptabic dose rates" are used throughout the procedure.
Response
Emergency Preparedness procedure EP-231 has been reviewed by the Chemistry Department. The Limerick Generating. Station (LGS) Chemistry Department, in conjunction with the LGS Health Physics Department, will determine PASS sample dose rate limits and will revise EP-231 to incorporate the specific dose rate limits.
This revision will be completed along with the revision of several other Emergency Preparedness procedures that will incorporate recommendations in this response letter.
The procedure revisions will be cross reviewed to ensure the actions in each procedure are coordinated without conflicts and will be completed by June 30, 1990.
ITEM 2 NRC Recommendation (Ref. 4.5.2 {pg. 5}) ,
The samples taken during this operational test were taken with the reactor shut down. Limitations on plant operations during start-up testing have prevented the taking of samples from the reactor coolant system at operating temperature and pressure and comparing the results with samples obtained from normal system sampling l points.
i l
l-l l
l
i
. ATTACHMENT 1 P0go 2 of 8 50-353/89-32 .
}
Response
Unit 2 reactor coolant PASS samples have been taken and compared with a routine reactor coolant sample at a sufficient operating temperature and pressure. When an !
adequate amount of radioactivity is present in the reactor coolant the procedure will be repeated and the results of the sample comparison will be provided to the NRC Senior.
Resident Inspector.
ITEM 3 .
NRC Recommendation (Ref. 4.7.1 {pg. 7})
The licensee's procedures for sample preparation, specifically procedures EP-241, " Sample Preparation and Handling of Highly Radioactive Liquid Samples", and EP-243, l
" Sample Preparation and Handling of Highly Radioactive Gas
- Samples", do not specify dilution criteria for sample ,
analysis for either chemical or gamma isotopic analysis.
No specific guidance is-given to ensure that the diluted ,
samples will be within the calibration range of the ;
analytical instrumentation or contain radioactivity concentrations which will not exceed dead time limitations for the gamma spectrometer -
Response ,
l EP-241 and EP-243 will be revised by June 30, 1990. l l This revision will provide guidance as to ensure that e I diluted samples will remain within the calibrated range of the a'nalytical instrument or not exceed the dead time limitations of the gamma spectrometer.
ITEM 4 NRC Recommendation (Ref. 4.7.2 {pg. 7})
l The volume of the PASS liquid dilution valve has not been incorporated into the licensee's dilution procedure.
The measured volume of this dilution valve is 0.08 ml versus the designed volume of 0.10 ml.
I
ATTACHMENT 1
, Paga 3 of 8 50-353/89-32
Response
Procedure EP-241 will be revised by June 30, 1990.
This revision will incorporate the measured volume of the !
PASS liquid dilution valve, 0.08 ml, versus the design volume of 0.10 ml.
ITEM 5 NRC Recommendation (Ref. 4.7.3 {pg. 7})
The licensee has performed calibrations of the gamma ,
spectrometer at source-to-detector distances of up to approximately 36 inches. This requires counting samples with the shield lid open. The licensee's assessment of '
radiation levels during accident conditions indicates that under certain situations the counting room will experience a exposure rate of 8-10 mR/hr from noble gas. The licensee stated that samples could not be counted under these conditions. However, the licensee's procedures do not provide specific limits on sample exposure rates so that the samples can be counted in a shield with the lid closed after purging the radioactive noble gases from the shield.
l This applies, in particular, to charcoal cartridge (or i silver zeolite) samples which cannot be diluted.
Response
l Specific sample exposure rate limits will be incorporated into procedures EP-231, EP-241, EP-243, and EP-242, " Sample Preparation and Handling of Highly i
Radioactive Particulate Filters and Iodine cartridges," by l
June 30, 1990. These procedure revisions will permit -
samples to be counted in a shield with the lid closed.
ITEM 6 NRC Recommendation (Ref. 4.7.4 {pg. 8})
The licensee's noble gas gamma isotopic results from a containment atmosphere sample are reported at conditions of standard temperature and pressure (STP). However, Procedure EP-C-326, " Procedures for Estimating Core Damage During Accident Conditions", requires that actual sample vial temperature and pressure to be reported so that the noble gas activity result can be corrected to containment
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. Pag 3 4 of 8 50-353/89-32 temperature and pressure conditions. A procedure change should be made so that the reported sample results are in the correct form to be used in Procedure EP-C-326 to assess ;
core damage. '
Response
Procedure EP-C-326 has been revised, and now includes a method to count the noble gas activity result at STP conditions to containment temperature and pressure conditions.
NOBLE GAS EPPLUENT MONITOR, ITEM II.Pl-1 ITEM 7 NRC Recommendation (Ref. 5.3.1 (pg. 10})
l Since the monitoring enclosure is located immediately adjacent to the top of the north stack, it is possible that under some post-accident meteorological conditions the enclosure could be permeated by radioactive gases. Their I intake during a system purge would defeat the purpose of the purge by filling the idled piping. This will result in false indications when the system resets for normal operation. It is therefore recommended that a supply of clean air or inert gas be supplied to purge pathways.
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Response
i We consider this modification to be unnecessary. We acknowledge that the possibility exists of radiogases infiltrating into the north stack instrument room. This condition could create false indication on the low range of the Wide Range Accident Monitor (WRAM) during purges with room air. This is a standby condition during high effluent activity. However, upon recovery to the low range detector, accurate effluent readings will not be obtained for one minute and twenty-two seconds based on line length from sample tubes to detector assuming one Standard Cubic Feet per Minute (SCFM). The effects on the detector due to purge air contamination would only last fifty seconds assuming 1 SCFM. Therefore, the purge air effects will not interfere with the sample once valid data is available. We consider this modification to be unnecessary.
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ITEM 8 ,
NRC Recommendation,(Ref. 5.3.2 {pg. 10})
Due to the close proximity of the monitoring enclosure !
to the north stack, a high radiation field is. expected :
under post-accident conditions. Doses to technicians l obtaining a backup gas sample could approach the GDC-19 ;
criteria. The substitution of a procedure to calculate gas concentrations in the duct from survey readings near the .
duct would materially 3ower,the associated doses.
Response
We acknowledge the possibility'of approaching GDC-19 ,
criteria when obtaining a backup accident gaseous effluent sample. We will develop a procedure by June 1, 1990 to ;
evaluate the radioactive release based on dose rate ;
readings as taken off-the vent duct work. This procedure will utilize Design Basis Accident isotopic mixtures and >
stack flow rates to determine a total release rate.
SAMPLING AND ANALYSES OF PLANT EFFLUENTS, ITEM II.F.1-2 ITEM 9 NRC Recommendation (Ref. 6.3.l(pg. 12})
The procedure for the limitation of grab sample activity should be clarified. An alternative means of i evaluating the amount of activity collected should be devised in case the activity exceeds the capability of the count room equipment.
Response ,
Procedure EP-237, " Obtaining the Iodine / Particulate and/or Gas Samples from the North Vent Wide Range Gas Monitor," revised to include grab sample radioactivity limitations. Methods to estimate sample radioactivity for t samples which exceed counting capabilities will be evaluated by June 30, 1990. The decision resulting from i this evaluation will be provided to the Sr. Resident Inspector as well as implementation plans as appropriate.
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. Pago 6 of 8 50-353/89-32 i
ITEM 10 NRC Recommendation (Ref. 6.3.2 {pg. 12}) ,
Procedures for the determination of the activity '
collected on other than grab samples should be provided so as to establish the total activity released during a prolonged post-eccident release.
Response
The LGS Technical Support Health Physicist (HP) contacted the lead NRC Inspector on March 1, 1990 to gain clarification to the phrase "other than grab samples." The lead inspector stated that this recommendation referred to
" Particulate and iodine samples taken from the Wide Range Accident Monitor (WRAM) sample skid." As a result of this conversation, the recommendation is understood to state thatt no guidance is provided for handling high activity particulate and iodine samples taken from the WRAM sample '
conditioning skid.
The appropriate EP Procedures will be revised by June 30, 1990 to provide guidance for the determination of activity collected from the WRAM sample skid. This will enable qualified personnel to establish the total amount of radioactivity released during a prolonged post-accident release.
ITEM 11 NRC Recommendation (Ref. 6.3.3 {pg. 12 +
A small hand truck should be provided to facilitate the transport of the shield cask and activity samples through the level portions of the building leading.to the chemistry laboratory.
Response
The Chemistry Department has ordered a hand truck to be used during the transport of the shield cask and activity samples through the level portions of the building leading to the chemistry laboratory.
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. P g3 7 of 8 50-353/89-32 ITEM 12 i .
NRC Recommendation (Ref. 6.3.4 {pg. 12))
It appears that the location of the WRGM was chosen to !
minimize the length of sampling lines in accordance with the guidance of ANSI N13.1-1969. Since the promulgation of r this guidance, it has been demonstrated that long (100' to 200') sampling lines with a diameter of 1" to 2" at flows ,
of 1 to 2 CFM provide for high transmission of particulates and elemental lodines. However, long sampling lines of !
1/4" piping with a flow at 0.06 CFM such as the WRGM high range flow path provide very low and uncertain transmission. Some licensees have located the WRGM in a readily accessible area with low background at some .,.
distance from the plant stack and provided for the continuous operation of the high volume pump. A flow ,
splitter is then installed close to the WRGM and feeds a 1/4" low flow line to the mid/high range sample path. ;
Movenant of the WRGM,to a location more remote from the stack would significantly reduce the climbing hazards and transit exposures to personnel. This is also recommended
! in view of the time and dose constraints that are imposed t i on the frequency of obtaining samples from the WRGM at its I j present location, i Response t We acknowledge the advantages of relocating the WRAM '
(referenced above as WRGM) with respect to high -
transmission of particulates and elemental lodines, climbing hazards, and transit exposures to personnel. An ,
I evaluation is being performed to consider the benefits of relocating the WRAM to a more accessible location. This evaluation will consider worker safety, sampling accuracy and financial prudency. The evaluation is expected to'be completed by May 16, 1990 and will determine.our ultimate decision on relocation of the WRAM. The results of this l evaluation will be provided to the NRC Senior Resident l Inspector.
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IMPROVED IN-PLANT IODINE INSTRUMENTATION UNDER ACCIDENT I CONDITIONS, ITEM II.D.3.3 ITEM 13 NRC Recommendation (Ref. 8.3.1 (pg. 14))
The policies and procedures regarding post-accident i iodine monitoring need to be improved by the addition of guidance for supervisors and technicians. Current procedures rely extensively on discretion and knowledge of the HP personnel. However, most personnel are only familiar with the hazards involved in routine operations but not with the severe conditions that may occur in plant after an accident. Information such as recommended air sample size when extremely high activity is suspected, cartridge purge guidelines, and selection of cartridge type (charcoal vs. silver zeolite) should be provided. The exposure values in General Design Criterion 19 should also be provided in the procedures as guidance in decision making.
Response -
Procedure HP-213," Airborne Activity Survey Techniques,"
will be revised by April 30, 1990. This revision will incorporate a recommended maximum air sample size based on dost rate constraints of laboratory equipment and realistic values for airborne activity during an accident. In conjunction with this procedure revision of air sample size, a letter to file will also be written providing the .
technical basis justifying the values used in the i procedure.
Additionally, this revision of procedure HP-213 will include special instructions for minimizing personnel exposure below the levels listed in GDC 19. These special ,
instructions will address conditions during the handling of !
air samples that are suspected to contain extremely high !
radioactivity. This revision of procedure HP-213 will also incorporate guidance for the selection of cartridge type (charcoal vs. silver zeolite) and instructions for the use of procedure HP-204, " Rapid Assessment of Radiolodine !
Concentration." l I
Finally, guidelines for purging silver zeolite cartridges will be incorporated into applicable chemistry sampling procedures by April 30, 1990.
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