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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:NRC TO UTILITY
MONTHYEARML20062G4531990-11-20020 November 1990 Forwards SE Supporting Util Actions to Address Indication in Reactor Vessel Recirculation Riser nozzle-to-safe End Weld ML20062G4021990-11-19019 November 1990 Forwards Safety Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted ML20062F1771990-11-13013 November 1990 Confirms Dates of 901126-30 for NRC Equipment Qualification Insp of Facility ML20058F1981990-11-0505 November 1990 Advises That 901002 Response to Generic Ltr (GL) 90-03, Relaxation of Staff Position in GL 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058E6121990-10-29029 October 1990 Forwards Radiological Safety Insp Repts 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20058C1331990-10-23023 October 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 910121 & Requalification Program Evaluation Scheduled for Wks of 910114 & 21.Ref Matl Listed on Encl Should Be Provided by 901029 ML20058A6241990-10-18018 October 1990 Forwards Insp Repts 50-352/90-22 &50-353/90-21 on 900912-19. No Violations Noted ML20062B7891990-10-12012 October 1990 Forwards Safety Insp Repts 50-352/90-20 & 50-353/90-19 on 900813-0916.No Violations Noted ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable IR 05000352/19900801990-09-28028 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/90-80 & 50-353/90-80.Requests Status of Planned Revs to Procedures & Expected Completion Dates in 910130 Response ML20059F6561990-08-29029 August 1990 Forwards Notice of Withdrawal of 900516 Application for Amend to License NPF-39,revising Tech Specs to Allow one- Time Extension of Visual Insp Period for Three Small Inaccessible Snubbers in Drywell ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20058M5981990-08-0303 August 1990 Forwards Safety Insp Repts 50-352/90-17 & 50-353/90-16 on 900522-0701 & Notice of Violation.Inspectors Continued to Note Problems W/Procedure Compliance & in Technical Adequacy & Implementation of Procedures ML20058M3311990-08-0303 August 1990 Forwards Radiological Safety Insp Repts 50-352/90-19 & 50-353/90-18 on 900709-13.No Violations Noted.Weakness Observed in Maint of Station Health Physics Procedures ML20055E8641990-07-10010 July 1990 Comments on Util 891228 Response to Generic Ltr (GL) 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Requests Proposed Schedule for Completion of GL Program Along W/Justification for Alternative Schedule ML20055F5591990-07-0303 July 1990 Forwards Safety Insp Repts 50-352/90-80 & 50-353/90-80 on 900521-25.Plant Transient Response Implementing Plan (Trip) Technically Acceptable.Unresolved Items Noted.Impact of Insp Findings on Peach Bottom Trip Procedures Should Be Reviewed ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20058K1961990-05-31031 May 1990 Forwards Results & Conclusions of Regulatory Effectiveness Review on 900507-11.Encl Withheld (Ref 10CFR73.21) ML20055C3091990-02-14014 February 1990 Forwards Safety Insp Repts 50-352/90-03 & 50-353/90-03 on 900116-19.No Violations Noted ML20248E7421989-09-27027 September 1989 Forwards Exam Repts 50-352/89-13OL & 50-353/89-22OL Administered on 890612-16 & 19.NRC Concerned About Effectiveness of Util Candidate Screening & Evaluation Process That Permitted Marginal Individual for NRC Exam ML20248G6601989-09-27027 September 1989 Forwards Operational Readiness Insp Rept 50-353/89-81 on 890730-0804 & Notice of Violation ML20248E5181989-09-22022 September 1989 Forwards Safety Insp Repts 50-352/89-15 & 50-353/89-24 on 890626-0730.No Violations Noted.Repts Delineate NRC Concerns Identified During mid-cycle SALP Review & Licensee self-assessment of Conduct of Operations ML20248G9611989-09-21021 September 1989 Forwards Amend 7 to Indemnity Agreement B-101,reflecting Increase in Primary Layer of Liability Insurance.Amends Conform to Changes Made to Price-Anderson Act Enacted on 880820 NUREG-1376, Forwards Tech Specs,NUREG-1376 & Sser 9 Re Application for OL for Facility.W/O Encls1989-09-11011 September 1989 Forwards Tech Specs,NUREG-1376 & Sser 9 Re Application for OL for Facility.W/O Encls ML20247N2331989-09-0808 September 1989 Forwards Insp Repts 50-352/89-17 & 50-353/89-25 on 890724-27.No Violations Noted.Corrective Actions Re Failure of Operators to Properly Classify Events Effective ML20247E7991989-09-0606 September 1989 Forwards Safety Insp Rept 50-352/89-16 on 890807-11.No Violations Noted ML20246D5641989-08-23023 August 1989 Forwards Corrective Action Insp Rept 50-353/89-201 During Wk of 890424 Re Independent Design Assessment.Assessment Provided Needed Addl Assurance That Plant Design Met Licensing Commitments ML20246N4111989-08-15015 August 1989 Forwards FEMA Rept on 890614 Plant Remedial Exercise.Rept Indicates That Deficiency Identified in Lower Pottsgrove Township During 880405 full-participation Exercise.Offsite Preparedness Adequate ML20245K0161989-08-11011 August 1989 Advises That 890403 Response to Generic Ltr 83-28,Item 2.1 Parts 1 & 2 Acceptable ML20245G1511989-08-10010 August 1989 Discusses Emergency Preparedness Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of 75,000 ML20245J8171989-08-0909 August 1989 Advises That Listed Schedule Should Be Used for All Emergency Exercises,Including Submittal & Review of Objectives & Scenario Packages Prior to Exercise ML20245H7151989-08-0909 August 1989 Discusses Insp Rept 50-352/89-14 on 890629 & Forwards Notice of Violation.Insp Reviewed Circumstances Involving Transport of Contaminated Waste from Unit to Quadrex Recycle Ctr in Oak Ridge,Tn on 890620 ML20245G6721989-08-0808 August 1989 Forwards Environ Assessment & Finding of No Significant Impact Re Request for Exemption from 10CFR50.44(c)(3)(i) to Extend Permitted Time of Operation W/Noninerted Containment Until Completion of 100 H Warranty Run ML20248C3571989-07-31031 July 1989 Forwards Request for Addl Info Re Consideration of Severe Accident Mitigation Design Alternatives.Response Requested within 30 Days of Ltr Receipt ML20248D8901989-07-28028 July 1989 Forwards Safety Insp Repts 50-352/89-12 & 50-353/89-19 on 890529-0625 & Notice of Violation.Fire Protection Issues, Discussed in Section 3.1,may Represent Potential Enforcement Issues NUREG-1371, Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl1989-07-25025 July 1989 Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl ML20247N4761989-07-25025 July 1989 Forwards Enforcement Conference Rept 50-352/89-14 on 890717. Apparent Violation Noted in Insp Rept 50-352/89-14 Re Area of Transportation of Radioactive Matl Discussed ML20246N1801989-07-13013 July 1989 Forwards Preoperational Insp Rept 50-353/89-20 on 890530- 0621.Programs Adequate to Support Testing & Startup ML20246N4171989-07-12012 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/89-80 & 50-353/89-80 ML20246K5461989-07-11011 July 1989 Forwards Reactive Safety Insp Rept 50-352/89-14 on 890629. Violations Noted.Concern Expressed Re Lack of Control in Area of Properly Packaging Matl to Ensure External Radiation Levels Mantained.Enforcement Conference Scheduled ML20246G2921989-07-0707 July 1989 Forwards Safety Insp Rept 50-353/89-21 on 890530-0602.No Violations Noted ML20246F5911989-07-0606 July 1989 Forwards to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Ltr Ack Receipt of Petition Filed by Ecology Ctr & States Petition Filed Under 10CFR2.206 NUREG-1360, Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl1989-07-0303 July 1989 Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl ML20246B6061989-06-27027 June 1989 Ack Receipt of Re Alleged Discrimination Against Employee for Engaging in Protected Activities.Nrc Considers Matter Closed by Review of Info ML20245F0401989-06-22022 June 1989 Forwards License NPF-83 Authorizing Fuel Loading & Precriticality Testing of Util & Fr Notice.Amend 4 to Indemnity Agreement B-101 Also Encl ML20245H6901989-06-21021 June 1989 Forwards Safety Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607.Violations Noted.Enforcement Conference Will Be Held on 890705 to Discuss Operators Inability to Properly Classify Certain Events During walk-through Exams ML20245F2941989-06-20020 June 1989 Approves Util 880621 Power Ascension Test Program for Facility,Per Reg Guide 1.68,for Execution ML20245E6141989-06-20020 June 1989 Forwards SER Accepting Util 890331 & 0602 Responses to NRC Bulletin 88-005, Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co at Williamstown,Nj ML20245F2991989-06-16016 June 1989 Forwards Safety Insp Rept 50-353/89-23 on 890605-07.No Violations or Deviations Noted 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212J6561999-09-29029 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 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 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 ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed 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 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 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 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 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 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 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 ML20206Q5871999-05-14014 May 1999 Advises That Info Contained in ,Which Submitted Revised Procedures for Plant EP Response Procedures Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R3031999-05-11011 May 1999 Informs That on 990407,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Forwards Copies of Both Forms of Exam,Including Answer Keys & Grading Results of Facility ML20206N1111999-05-0707 May 1999 Forwards Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206H2651999-05-0606 May 1999 Informs That on 990112 Licensee Submitted to NRC Core Shroud Insp Plan for Plant,Unit 2,in Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors ML20206G5131999-05-0303 May 1999 Approves Change of Completion Date for Implementation of Thermo-Lag Fire Barrier Corrective Actions at Plant from End of April 1999 Limerick Unit 2 RFO to 990930 ML20206H8301999-04-30030 April 1999 Forwards Exam Repts 50-352/99-301 & 50-353/99-301 on 990312-19 (Administration) & 22-26 (Grading).Four of Five RO Applicants & Three of Four SRO Applicants Passed All Portions of Exams ML20206E6951999-04-30030 April 1999 Advises That Plant,Unit 2 Cycle 6 Safety Limit Mcpr, ,contained in PECO Energy Co 990311 Application & 990204 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20206F4221999-04-27027 April 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990312 & 990315-19 at Facility.Completed ES-501-2,power Plant Licensing Exam Results Summary & Summary of Overall Exam Results Encl.Without Encl ML20205N2291999-04-0909 April 1999 Discusses Limerick Generating Station Plant Performance Review Conducted for Period April 1998 Through 990115 & Informs of NRC Planned Insp Effort Resulting from Review. Historial Listing of Plant Issues,Encl IR 05000352/19980091999-03-30030 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-09 & 50-353/98-09 Issued on 990106.Actions Will Be Examined During Future Insp of Licensed Program ML20205C2711999-03-26026 March 1999 Forwards Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301.One Violation Noted & Being Treated as Non-Cited Violation.Staff Conduct of Activities During Insp Generally Characterized by Safe & Conservative Decision Making ML20205G7651999-03-22022 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 90 Days of Receipt of Ltr ML20204G9721999-03-11011 March 1999 Informs of Completion of Review of Changes Proposed by PECO Energy Co to Lgs,Units 1 & 2,EALs.Proposed EALs Incorporate Guidance in NUMARC/NESP-007,Rev 2.Forwards Safety Evaluation Supporting Proposed Changes ML20204H8171999-03-10010 March 1999 Discusses Request That NEDC-32645P, Limerick Generating Station,Units 1 & 2,SRV Setpoint Tolerance Relaxation Licensing Rept, Rev 2,dtd Dec 1998,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20207J0611999-03-0808 March 1999 Provides Authorization to Administer Initial Written Exams to Listed Applicants on 990312.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 990315-19 at Limerick Generating Station ML20203G6721999-02-17017 February 1999 Second Partial Response to FOIA Request for Documents. Records in App D Encl & Being Made Available in Pdr.App E Records Being Withheld in Part (Ref FOIA Exemption 5) & App F Records Completely Withheld (Ref FOIA Exemptions 6 & 7) ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J0261999-02-0303 February 1999 Informs of Completion of Licensing Action for NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors ML20203A6111999-01-22022 January 1999 Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705 ML20199F9251999-01-11011 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-05 & 50-353/98-05 ML20199C6501999-01-0606 January 1999 Forwards Insp Repts 50-352/98-09 & 50-353/98-09 on 981018- 1130 & Notice of Violation.Violation of Concern Because Technicians Exercised Poor Judgement & Deviated from Procedure in Attempt to Resolve Problem Without Mgt ML20198H4951998-12-18018 December 1998 Forwards Results of Audit of Licensee Year 2000 Program for Limerick Generating Station,Units 1 & 2 ML20198A3721998-12-10010 December 1998 Forwards Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20198B1751998-12-0808 December 1998 Advises of Planned Insp Effort Resulting from Limerick mid-year Insp Resource Planning Meeting Held on 981110. Historical Listing of Plant Issues & Details of Insp Plan for Next Six Months Encl IR 05000352/19980081998-11-23023 November 1998 Discusses licensee-identified Issue Involving Potential for Bypass of Suppression Pool as Documented in Insp Repts 50-352/98-08 & 50-353/98-08.NOV Will Not Be Issued & Civil Penalty Will Not Be Proposed ML20196C3311998-11-23023 November 1998 Forwards Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violation Identified.Security Program Insp Identified That Security Program Effectively Protects Public Health & Safety ML20195D1491998-11-13013 November 1998 Forwards RAI Re on-going Review of IPEEE Submittal Dtd 951014.Understands That Licensee Will Inform NRC in Writing, by 981130,on How Question Re Effects of New Probable Max Precipitation at Plant,Units 2 & 3 Will Be Addressed IR 05000352/19980061998-10-15015 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-06 & 50-353/98-06 on 980826.Finds C/As for Violation Involving Failure to Select Performance Measures to Be Acceptable ML20154F8191998-10-0101 October 1998 Forwards Notice of Withdrawal of 960503 & Suppl Application for Amend to Fols.Amend Would Have Modified Facility TSs Pertaining to Rev to Frequency of Testing Stand Gas Treatment Sys & Reactor Encl Recirculation Sys ML20154A3461998-09-25025 September 1998 Forwards Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Weaknesses Noted with Reactor Engineering Support to Rod Pattern Adjustment ML20153G4291998-09-24024 September 1998 Forwards Request for Addl Info Re Licensee Revised Emergency Action Level Guidelines for Limerick Generating Station, Units 1 & 2 & Peach Bottom Atomic Power Station,Units 2 & 3. Response Requested within 30 Days of Receipt of Ltr ML20153D0151998-09-21021 September 1998 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Plant, Units 1 & 2 ML20151X2421998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-04 & 50-353/98-04 on 980805 ML20151W9601998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Were Selected as SRAs for Region I ML20237D5421998-08-26026 August 1998 Ack Receipt of & Fee for $55,000 in Payment for Civil Penalty Proposed by NRC in .C/As Will Be Examined During Future Insps 1999-09-09
[Table view] |
Text
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F NOV f1985 Docket fics. 50-352/353 Mr. Edward G. Bauer, Jr.
Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101
Dear Mr. Bauer:
SUBJECT:
GENERIC LETTER NO. 83-28, ITEM 1.2 REVIEW A review has recently been perfomed of the Philadelphia Electric Company response to the Generic Letter 83-28 Item 1.2, " Post-Trip Review: Data and Information Capabilities" for the Lincrick Generating Station. Ycur letter of June 7,1985 indicates that all of the response for Item 1.2 is contained in your earlier letter of November 10, 1983. Accordingly, this review was based principally on the November 10, 1983 letter. As indicated in the enclosed Technical Evaluation Report it is possible that the plant design meets the applicable criteria but has not been sufficiently described.
We request that your staff review the enclosed report in preparation for a discussion within several weeks of the date of this letter on those issues requiring additional infonnation.
Sincerely,
. Original Signed by Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
TER-by Science Applications, Inc.
cc: See next page DISTRIBUTION: {CIsck'et?Fils Nt!C PDR Local PDR PRC System NSIC LBe2 Reading EHyltoii~~ RMartin Vogler,0 ELD ACRS (16) JPartlow BGrimes EJordan JPage RGallo, Rg I L PM LB#2/DL/8C-i:lb . WButler 11/7/85 11/}/85 L
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T t NUCLEAR REGULATORY COMMISSION g :y WASHINGTON, D C. 20S55
\*****/ NOV 7 1985 Docket Nos. 50-352/353 Mr. Edward G. Bauer, Jr.
Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101
Dear Mr. Bauer:
SUBJECT:
GENERIC LETTER NO. 83-28, ITEli 1.2 REVIEW A review has recently been perforn'ed of the Philadelphia Electric Company response to the Generic Letter 83-28 Item 1.2, " Post-Trip Review: Data and Information Capabilities" for the Limerick Generating Station. Your letter of June 7,1985 indicates that all of the response for Item 1.2 is contained in your earlier letter of November 10, 1983. Accordingly, this review was based principally on the November 10, 1983 letter. As indicated in the enclosed Technical Evaluation Report it is possible that the plant design meets the applicable criteria but has not been sufficiently described.
We request that your staff review the enclosed report in preparation for a discussien within several weeks of the date of this letter on those issues requiring additional information.
Sincerely, N
Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
TER by Science Applications, Inc.
cc: See next page l
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- Mr. Edward G. Bauer, Jr Limerick Generating Station Philadelphia Electric Company Units 1 & 2 cc:
Troy B. Conner, Jr., Esquire Mr. Marvin I. Lewis Conner and Wetterhahn 6504 Bradford Terrace 1747 Pennsylvania Ave, N.W. Philadelphia, Pennsylvania 19149 Washington, D. C. 20006 Zori G. Ferkin Frank R. Romano, Chairman Assistant Counsel Air & Water Pollution Patrol Governor's Energy Council 61 Forest Avenue 1625 N. Front Street Ambler, Pennsylvania 19002 Harrisburg, Pennsylvania 17105 Federic M. Wentz Charles W. Elliott, Esquire County Solicitor Brose & Poswistilo, 1101 Bldg.
County of Montgotery 32511.10th Street "
Courthouse Easton, Pennsylvania 18402 Norristown, Pennsylvania 19404 Eugene J. Bradley Ms. N. Mulligan Philadelphia Electric Company Limerick Ecology Acticn Associate General Counsel 762 Queen St.
2301 Market Street Pottstown, Pennsylvania 19464 Philadelphia, Pennsylvania 19101 Mr. Karl Abrahtn Thenas Gerusky, Director Public Affairs Officer Bureau of Radiation Protection Region I Dept. of Enviromental Resources U.S. huclear Regulatory Commission 5th Floor, Fulton Bank Bldg.
631 Park Avenue Third and Locust Streets King of Prussia, PA 19806 Harrisburg, Pennsylvania 17120 Mr. Gene Kelly Senict Resident Inspector U.S. huclear Regulatory Conmission P. O. Box 47 Sanatoga, Pennsylvania 19464
Philadelphia Electric Company Limerick Generating. Station 1/2 cc:
Sugannan, Denworth & Hellegers Director, Pennsylvania Eniergency 16th Floor Center Plaza Management Agency 101 North Broad Street Basement, Transportation &
Philadelphia, Fennsylvania 19106 Safety Building Harrisburg, Pennsylvania 17120 Robert L. Anthony Angus Love, Esq.
Friends of the Earth 107 East Main Street cf the Delaware Valley Horristown, Pennsylvania 19402 103 Vernon Lane, Box 186 Moylun, Pennsylvania 19065 Helen F. Hoyt, Chairman Kathryn S. Lewis, Esq. Adninistrative Judge Municipal Services Bldo. Atomic Safety & Licensing Board 15th and JFK Blvd. U.S. fluclear Regulatory Comission Philadelphia, Pennsylvania 19102 Washington, D. C. 20555 David W rsan, Esq. Dr. Jerry Harbour Assistant Consunier Adyccate Administrative Judge
! Office of Censurcr Advocate Atomic Safety & Licensing Board 14'.5 Strawberry Square U.S. huclear Regulatory Comission Hi,rrisburg, Pennsylvania 17120 Washington, D. C. 20555 Steven P. Hershey, Esq. Dr. Richard F. Cole Comunity Legal Services, Inc. Administrative Judge Law Center North Central - Bevry Bldg. Atomic Safety & Licensing Board 3701 North Board Street U.S. Nuclear Regulatory Comission Philadelphia, Pennsylvania 19140 Washington, D. C. 20555 Mr. J. T. Robb, NS-1 Mr. Spence W. Perry, Esq.
Philadelphia Electric Company Associate General Counsel 2301 Market Street Federal Emergency. Management Agency Philadelphia, Pennylsvania 19101 Room 840 500 C St., S.W.
. Timothy R. S. Campbell, Director Washington, D. C. 20472 Department of Emergency Services 14 East Biddle Street West Chester, Pennsylvania 19380 t
~_ _ - .- _ ___
. . Enclosure SAIC-85/1525-4 REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic. Implications of Salem ATWS Events) Item 1.2 4
" POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR LIMERICK GENERATING STATION, UNITS 1 & 2 (50-352, 50-353)
Technical Evaluation Report Prepared by Science Applications International Corporation 1710 Goodridge Drive McLean, Virginia 22102 f-Prepared for U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract No. NRC-03-82-096 i
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i FOREWORD This report contains the technical evaluation of the Limerick Generating Station, Units 1&2 response to Generic Letter 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events). Item 1.2 " Post Trip Review: Data and Information Capabilities."
For the purposes of this evaluation, the review criteria, presented in part 2 of this report, were divided into five separate categories. These are:
- 1. The parameters monitored by the sequence of events and the time history recorders,
- 2. The performance characteristics of the sequence of events recorders,
- 3. The performance characteristics of the time history recorders,
- 4. The data output format, and
- 5. The long-term data retention capability for post-trip review material.
All available responses to Generic Letter 83-28 were evaluated. The plant for which this report is applicable was found to have adequately responded to, and met, category 2.
The report describes the specific methods used to determine the cate-gorization of the responses to Generic Letter 83-28. Since this evaluation report was intended to apply to more than one nuclear power plant specifics regarding how each plant met (or failed to meet) the review criteria are not presented. Instead, the evaluation presents a categorization of the responses according to which categories of review criteria are satisfied and which are not. The evaluations are based on specific criteria (Section 2) derived from the requirements as stated in the generic letter.
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TABLE OF CONTENTS Page Section I
Introduction. . . . . . . . . . . . . . . . . . . . . . . . .
2
- 1. Background. . . . . . . . . . . . . . . . . . . . . . . . . .
3
- 2. Review Criteria . . . . . . . . . . . . . . . . . . . . . . .
- 3. Evaluation. . . . . . . . . . . . . . . . . . . . . . . . . . 8
- 4. Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . 9 10
- 5. Re fe re nc e s . . . . . . . . . . . . . . . . . . . . . . . . . .
C. J offo,LTZ+W* Wocud r# TWecow ~ . - * *
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INTRODUCTION SAIC has reviewed the utility's response to Generic Letter 83-28, item 1.2 " Post-Trip Review: Data and Information Capability." The response (see references) contained sufficient information to determine that the data and information capabilities at these plants are acceptable in the following areas.
e The sequence-of-events recorder (s) performance charac-teristics.
However, the data and information capabilities, as described in the submittal, either fail to meet the review criteria or provide insufficient information to allow determination of the adequacy of the data and information capabilities in the following areas.
i e The parameters monitored by both the sequence-of-events and time history recorders.
e The time history recorder (s) performance char'acteris-tics.
e The output format of the recorded data.
e The long-term data retention, record keeping, capa-bility.
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- 1. Background On February 25, 1984, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during the plant startup and the reactor was tripped manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the under voltage trip attachment. Prior to this incident; on February 22, 1983; at Unit 1 of the Salem Nuclear Power Plant an automatic trip signal was generated based on steam generator low-low level during plant startup.
j In this case the reactor was tripped manually by the operator almost coinci-dentally with the automatic trip. At that time, because the utility did not have a requirement for the systematic evaluation of the reactor trip, no investigation was performed to determine whether the reactor was tripped automatically as expected or manually. The utilities' written procedures required only that the cause of the trip be determined and identified the responsible personnel that could authorize a restart if the cause of the i
trip is known. Following the second trip which clearly indicated the problem with the trip breakers, the question was raised on whether the circuit breakers had functioned properly during the earlier incident. The most useful source of information in this case, namely the sequence of events printout which would have indicated whether the reactor was tripped automatically or manually during the February 22 incident, was not retained after the incident. Thus, no judgment on the proper functioning of the trip
, system during the earlier incident could be made.
Following these incidents; on February 28, 1983; the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem Unit incidents is reported in NUREG-1000 " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." Based on the results of this study, a set of required actions were developed and included in Generic Letter 83-28 which was issued on July 8,1983 and sent to all licensees of operating reactors, applicants for operating license, and construction permit holders. The required actions in this generic letter consist of four categories. These are: (1) Post-Trip Review, (2) Equipment l
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4 Classification and Vender Interface, (3) Post Maintenance Testing, and (4)
Reactor Trip System Reliability Improvements.
The first required action of the generic letter, Post-Trip Review, is the subject of this TER and consists of action item 1.1 " Program Description and Procedure" and action item 1.2 " Data and Information Capability." In the next section the review criteria used to assess the adequacy of the utilities' responses to the requirements of action item 1.2 will be
- discussed.
- 2. Review Criteria
! The intent of the Post Trip Review requirements of Generic Letter 83-28 j is to ensure that the licensee has adequate procedures and data and j information sources to understand the cause(s) and progression of a reactor trip. This understanding should go beyond a simple identification of the
- course of the event. It should include the capability to determine the root cause of- the reactor trip and to determine whether safety limits have been exceeded and if so to what extent. Sufficient information about the reactor trip event should be available so that a decision on the acceptability of a reactor restart can be made.
i j The following are the review criteria developed for the requirements of
- Generic Letter 83-28, action item 1.2
The equipment that provides the digital sequence of events (SOE) record and the analog time history records of an unscheduled shutdown should pro-l vide a reliable source of the necessary information to be used in the post e
! trip review. Each plant variable which is necessary to determine the cause(s) and progression of the event (s) following a plant trip should be i monitored by at least one recorder [such as a sequence-of-events recorder or a plant process computer for digital parameters; and . strip charts, a plant
(, process computer or analog recorder for analog (time history) variables].
Each device used to record an analog or digital plant variable should be
( described in sufficient detail so that a determination can be made as to
! whether the following performance characteristics are met:
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1 e Each sequence-of-events recorder should be capable of detecting l and recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses asso-ciated with each monitored safety-related system can be ascer-tained, and that a determination can be made as to whether the time response is within acceptable limits based on FSAR Chapter 15 Accident Analyses. The recommended guideline for the SOE time discrimination is approximately 100 msec. If current SOE recorders do not have this time discrimination capability the licensee or applicant should show that the current time discrimi-nation capability is sufficient for an adequate reconstruction of the course of the reactor trip. As a minimum this should include the ability to adequately reconstruct the accident scenarios pre-sented in Chapter 15 of the plant FSAR.
e Each analog time history data recorder should have a sr.mple inter-val small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the licensee or applicant should be able to reconstruct the course of the accident sequences evaluated in the accident analysis of the plant FSAR (Chapter 15). The recommended guideline for the sample interval is 10 sec. If the time history equipment does not meet this guideline, the licensee or applicant should show that the current time history capability is sufficient to accurately recon-struct the accident sequences presented in Chapter 15 of the FSAR.
e To support the post trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should be capable of updating and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
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l e The information gathered by the sequence-of-events anti time l history data collectors should be stored in a manner that will allow for retrieval and analysis. The data may be retained in l either hardcopy (computer printout, strip chart output, etc.) or l in an accessible memory (magnetic disc or tape). This information should be presented in a readable and meaningful format, taking 4
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into consideration good human factors practices (such as those outlined in NUREG-0700).
e All equipment used to record sequence of events and time history information should be powered from a reliable and non-interruptible power source. The power source used need not be safety related.
The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause of the reactor trip, the progression of the reactor trip, and the response of the plant parameters and systems to the reactor trip. Specifically, all input parameters associated with reactor trips, safety injections and other safety-related systems as well as output parameters sufficient to record the proper functioning of these systems should be recorded for use in the post trip review. The parameters- deemed necessary, as a minimum, to perform a post-trip review (one that would determine if the plant. remained within its design envelope) are presented on Tables 1,2-1 and 1.2-2. If the appli-cants' or licensees' SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables the applicant or licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope for the appro-priate accident conditions; such as those analyzed in Chapter 15 of the plant Safety Analysis Report.
Information gathered during the post trip review is required input for future post trip reviews. Data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plar.t vital paramcter and equipment response to future unscheduled shut-downs. It is therefore necessary that information gathered during all post trip reviews be maintained in an accessible manner for the life of the plant.
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Table 1.2-1. PWR Parameter List SOE Time History Recorder Recorder Parameter / Signal x Reactor Trip (1) x Safet'y Injection x Containment Isolation (1) x Turbine Trip x Control Rod Position (1) x x Neutron Flux, Power x x Containment Pressure (2) Containment Radiation x Containment Sump Level (1) x x Primary System Pressure (1) x x Primary System Temperature (1) x Pressurizer Level (1) x Reactor Coolant Pump Status (1) x x Primary System Flow-(3) Safety Inj.; Flow, Pump /Va'.ve Status x MSIV Position x x Steam Generator Pressure (1) x x Steam Generator Level (1) x x Feedwater Flow (1) x x Steam Flow (3) Auxiliary Feedwater System; Flow.
Pump /Value Status x AC and DC System Status (Bus Voltage) -
x Diesel Generator Status (Start /Stop, On/Off) x PORY Position (1): Trip parameters (2): Parameter may be monitored by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
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l Table 1.2-2. SWR Parameter List ,
I SOE Time H.istory Recorder Recorder Parameter / Signal x Reactor Trip x Safety Injection x Containment Isolation x Turbine Trip x Control Rod Position x (1) x Neutron Flux, Power x (1) Main Steam Radiation (2) Containment (Dry Well) Radiation x (1) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x (1) x Primary System Pressure x (1) x Primary System Level x MSIV Position x (1) Turbine Stop Valve / Control Valve Position x Turbine Bypass Valve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow. Pump Status x (1) Scram Discharge Level x (1) ,
Condenser Vacuum x AC and DC System Status (Bus Voltage)
(3)(4) Safety Injection; Flow. Pump / Valve Status x Diesel Generator Status (On/Off, Start /Stop)
(1): Trip parameters.
(2): Parameter may be recorded by either an SOE or time history recorder.
(3.): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
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- 3. Evaluation i
The parameters identified in part 2 of this report as a part of the review criteria are those deemed necessary to perform an adequate post-trip review. The recording of these parameters on equipment that meets the guidelines of the review criteria will result in a source of information that can be used to determine the cause of the reactor trip and the plant response to the trip, including the responses of important plant systems.
> The parameters identified in this submittal as being recorded by the sequence.of events and time history recorders do not correspond to the parameters specified in part 2 of this report.
l The review criteria require that the equipment being used to record the sequence of events and time history data required for a post-trip review meet certain performance characteristics. These characteristics are intended to ensure that, if the proper parameters are recorded, the record- '
ing equipment will provide an adequate source of information for an effec-tive post-trip review. The information provided in this submittal does not indicate that the time history equipment used would meet the intent of the performance criteria outlined in part 2 of this report. Information supplied in the submittal does indicate that the SOE equipment meets the performance criteria specified in part 2 of this report.
! The data and information recorded for use in the post-trip review should be output in a format that allows for ease of identification and use of the data to meet the review criterion that calls for information in a readable and meaningful format. The information contained in this submittal does not indicate that this criterion is met.
The data and information used during a post-trip review should be retained as part of the plant files. This information could prove useful during future post-trip reviews. Therefore, one criterion is that infor-5 mation used during a post-trip review be maintained in an accessible manner for the life of the plant. The information contained within this submittal 4
does not indicate that this criterion will be met.
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- 4. Conclusion i
The information supplied in response to Generic Letter 83-28 indicates that the current post-trip review data and information capabilities are adequate in the following area:
- 1. The sequence of events recorders meet the minimum performance characteristics.
The information supplied in response to Generic Letter 83-28 does not indicate that the post-trip review data and information capabilities are adequate in the following areas.
- 1. Based upon the information contained in the submittal, all of the parameters specified in part 2 of this report that should be recorded for use in a post-trip review are not recorded.
- 2. Time history recorders, as described in the submittal, do not meet the minimum performance characteristics.
- 3. As described in the submittal, the recorded data may not be output in a readable and meaningful format.
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- 4. The data retention procedures, as described in the submittal, do not indicate that the information recorded for the post-trip review is maintained in an accessible manner for the life of the pl a nt .
It is possible that the current data and information capabilities at this nuclear power plant are adequate to meet the intent of these review criteria, but were not completely described. Under these circumstances, the licensee should provide an updated, more complete, description to show in more detail the data and information capabilities at this nuclear power plant. If the information provided accurately represents all current data and information capabilties, then the licensee should either show that the data ar.3 information capabilities meet the intent of the criteria in part 2 of this report, or detail future modifications ,that would enable the licensee to meet the intent of the evaluation criteria.
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REFERENCES NRC Generic Letter 83-28. " Letter to all licensees of operating reactors, applicants for operating license, and holders of construction permits regarding Required Actions Based on Generic Implications of Salem ATWS Events." July 8, 1983.
NUREG-1000 Generic Implications of ATWS Events at the Salem Nuclear Power Plant, April 1983.
Letter from V.S. Boyer, Philadelphia Electric Company, to D.G. Eisenhut NRC, dated November 10, 1983, Accession Number 8311150271 in response to Generic Letter 83-28.
Letter from V.S. Boyer, philadelphia Electric Company, to D.G. Eisenhut NRC, dated August 31, 1984, Accession Number 8409100176 in response to Item 1.1 of Generic Letter 83-28.
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- 1. Parameters recorded: Unsatisfactory See attached table for discrepancies.
- 2. SOE recorders performance characteristics: Satisfactory Plant process computer: 2ms time discrimination with non-interruptible power supply
- 3. Time history recorders performance characteristics: Unsatisfactory ERFDS: sampling rate varies, longest is I sec; no duration of log is provided; non-interruptible power supply Strip charts are also used, but little or no information is provided.
- 4. Data output format: Unsatisfactory SOE data: time, parameter name/descriptor and ID are output Analog: no information is provided.
- 5. Data retention capability: Unsatisfactory Data is retained but for an unspecified length of time.
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4 Desirable BWR Parameters for Post-Trip Review (circled parameters are not recorded)
SOE Time History Recorder Recorder ~ Parameter / Signal Reactor Trip Safety Injection
, Containment Isolation Turbine Trip Control Rod Position x (1) x Neutron Flux, Power x (1) Main Steam Radiation (2) Containment (Dry Well) Radiation x (1) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x (1) x Primary System Pressure
.x (1) x Primary System level
@ MSIV Position x (1) Turbine Stop Valve / Control Valve Position
@ Turbine Bypass Valve Position x Feedwater Flow x Steam Flow
, (3) Recirculation; Flow. Pump Status x (1) Scram Discharge Level x (1) Condenser Vacuum x AC and DC System Status (Bus Voltage)
(3)(4) Safety Injection; Flow. Pump / Valve Status
- x Diesel Generator Status (On/Off. -
Start /Stop)
(1): Trip parameters.
(2): Parameter may be recorded by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
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