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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 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 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 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 ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS 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 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 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 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 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 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl 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 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 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 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 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 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 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 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 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 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 ML20044A4651990-06-18018 June 1990 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 900801 in King of Prussia,Pa to Discuss Recent Changes to Format for Requalification/Initial Exams. Agenda & Info Re Lodging Accomodations Encl 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) ML20042F1331990-04-26026 April 1990 Forwards Requalification Reexam Repts 50-352/90-14(OL) & 50-353/90-13(OL) Administered on 900406.Two Operators That Passed Exam Can Resume Performing Licensed Duties NUREG-0991, Forwards Safety Evaluation Accepting Response to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Impact on Plant Operation1990-04-23023 April 1990 Forwards Safety Evaluation Accepting Response to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Impact on Plant Operation IR 05000353/19890321990-03-12012 March 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-353/89-32 ML20033F1121990-03-0707 March 1990 Forwards Enforcement Conference Rept 50-352/90-04 on 900223 Re Violations Involving 10CFR50,App R Fire Safe Shutdown Issues at Plant.Notice of Significant Licensee Meeting 90-023 Also Encl ML20011F7371990-02-26026 February 1990 Forwards Safeguards Insp Repts 50-352/90-05 & 50-353/90-04 on 900129-0202.No Violations Noted ML20055C3091990-02-14014 February 1990 Forwards Safety Insp Repts 50-352/90-03 & 50-353/90-03 on 900116-19.No Violations Noted ML20248G6601989-09-27027 September 1989 Forwards Operational Readiness Insp Rept 50-353/89-81 on 890730-0804 & Notice of Violation 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 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 ML20246C0351989-06-30030 June 1989 Forwards Safety Insp Repts 50-352/89-10 & 50-353/89-16 on 890423-0528 & Notice of Violation 1990-08-06
[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 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 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 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 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 IR 05000352/19980051999-01-11011 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 IR 05000352/19980041998-09-11011 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 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
March 1, 1990
SUBJECT:
Limerick Generating Station, Unit 2
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Reply to Notice of Violation NRC Inspection Report No. 50-353/89-32
Dear Sirst Attached is Philadelphia Electric Company's reply to the
" Notice of Violation" contained in NRC Inspection Report No. 50-353/89-32 for Limerick Generating Station (LGS), Unit 2.
NRC letter dated January 31, 1990, forwarded NRC Inspection Report No. 50-353/89-32 containing the " Notice of Violation."
This violation of NRC requirements pertains to the control of Special Nuclear Material and was identified during an NRC inspection conducted between December 11-15, 1989, at LGS, Unit 2.
The attachment to this letter provides restr.tement of the violation and our response.
If you have any questions, or require additional information, please contact uc.
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Very truly yours,
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DMS:nik Attachment c
cc:
W. T. Russell, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS QONO@SM g 7_
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AttCchm nt P293 1 of 6 i
Inspection No. 50-353/89-32
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Reply to Notice of Violation c
Restatement of the Violation As a result of the inspection conducted on December 11-15i 1989, and in accordance with the General Statement of Policy and Procedures for NRC Enforcement Actions, 10 CFR Part 2, Appendix C
_(Enforcement Policy 1989), the*following violation was
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identified:
10 CPR 70.51 (b)(1) requires that each licensee shall keep records showing the receipt, inventory (including location),
disposal, acquisition, and transfer of all special nuclear material (SNM) in his possession regardless of its origin or method of acquisition.
Also, 10 CFR 74.13 (a)(1) and 74.15 (a)
require, respectively, preparation and submission of Material Balance Reports concerning SNM received or transferred, and documentation of receipts or transfers by completion and distribution of Nuclear Material Transaction Reports.
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Contrary to the above, the inspector determined on December 15, 1989 thatt.
Two dunking chambers containing approximately 5 grams of uranium-235 (received from Reuter-Stokes, Inc. on shipment ZSZ-XIS-03 dated May 19, 1989) were not recorded nor reported to the NRC on a Nuclear Material Transaction Report, and Material Balance Report as required; The same two dunking chambers containing approximately 5 grams of uranium-235 were shipped offsite on September 29, 1989 to Public Service Electric and Gas Co., were not
' documented on a Nuclear Material Transaction Report and
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reported to the NRC on Material Balance Report, as required.
This is a Severity Level IV Violation (Supplement III).
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l RESPONSE
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Admission of Alleoed V3olation Philadelphia Electric Company acknowledges the violation.
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Attachm0nt
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P;ge 2 of 6 Inspection No. 50-353/89-32
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Reason for the Violation This violation has been attributed to the following causes identified below.
1)
Procedures - While administrative controls existed for controlling Special Nuclear Material (SNM), the i
procedure implementing the administrative policies was
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inadequate in that
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o it did not contain a detailed procedural step for the onsite processing of a Nuclear Material Transaction Report, DOE /NRC Form 741, and o
no formalized method of communication existed between the plant and corporate groups which handle SNM accountability.
2)
Training - No formalized training in' SNM documentation, identification, security, and regulatory requirements existed for the group responsible to physically track SNM, or the various other personnel working with SNM items.
On May 20, 1989, Reuter Stokes Inc. shipped one wooden box containing SNM (5 grams of 93% Uranium-235) in the form of two fuel loading chambers (i.e., detectors) to Limerick Generating Station (LGS).
On May 22, 1989, the shipment arrived at LGS, and accompanying the shipment were three copies of DOE /NRC Form 741.
This form listed the serial numbers of the fuel loading chambers and other pertinent information regarding the shipment.
The three forms were forwarded to the LGS Reactor Engineering Department for dispositioning in accordance with Administrative Procedure A-44, "Special Nuclear Material Accountability."
We note however, that Reuter Stokes, Inc. should have forwarded one of the three copies of the DOE /NRC Form 741 to the Philadelphia Electric Company (PECo) business address (i.e., the corporate group involved in handling SNM accountability) as directed by NUREG/BR-0006, " Instructions f or Completing Nuclear Material Transaction Reports."
As previously stated in Item 1 above, a factor to the cause of this violation was that Procedure A-44 did not contain a detailed procedural step that explicitly directed onsite personnel how to process a DOE /NRC Form 741.
As a result, the three copies of DOE /NRC Form 741 associated with the shipment were inadvertently placed into the Reactor Engineering SNM correspondence file without the required receipt acknowledgement being sent to Reuter Stokes, Inc. as directed by NUREG/BR-0006.
Formal acknowledgement of SNM receipt by PECo is normally made from the corpora *e office.
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Attcch: nt P g] 3 cf 6
Inspection No. 50-353/89-32 s
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As previously stated in Item 2 above, a second factor to the cause of this violation was that the Reactor Engineering group, responsible to physically track the onsite inventory of SNM, were not trained in SNM, documentation, identification, or regulatory requirements.
Since the Reactor Engineering group was not trained in the handling of SNM documentation (i.e., DOE /NRC Form 741), they failed to recognize that receipt acknowledgement of the SNM had not been made.
As a result of mis-handling this DOE /NRC Form 741, the association between the Form 741 and the fuel loading chambers was never established.
Therefore, the fuel loading chambers were presumed to be a commonly used boron trifluoride detector, which contains no SNM, and were not recorded into the LGS SNM Accountability System.
This system is used by the corporate office to generate the Material Balance Report, DOE /NRC Form 742.
Consequently, between Mar 23, 1989 and September 27, 1989, the fuel loading chambers were not treated as SNM.
As a result, receipt of the SNM was not recorded or reported to Reuter Stokes, INC. and to Martin Marietta Energy Systems (SNM accounting consultant for the DOE /NRC) on a DOE /NRC
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Form 741 as directed by NUREG/BR-0006.
Additionally, receipt of the SNM was not reported to the NRC on the DOE /NRC Form 742 as required by 10 CFR 74.13, that was issued by PECo dated September 30, 1989.
Between May 23, 1989 and September 27, 1989, the fuel loading chambers were moved to the LGS refueling floor, unpackaged, inspected, and stored on the refueling floor in preparation for their use during Unit 2 fuel loading operations.
However, the fuel loading chambers were never used, and were never contaminated.
Therefore, the fuel loading chambers were repackaged and prepared to be shipped back to Reuter Stokes, Inc.
I Between September 27, 1989 and September 29, 1989, the fuel loading chambers were prepared for shipment offsite.
The I
original destination for the shipment was revised from Reuter Stokes, Inc. to Hope-Creek Generating Station, since Hope Creek personnel requested the use of these fuel loading chambers.
Exit surveys were conducted by Health Physics personnel, and the chambers were moved from the refueling floor to the new fuel storage area for shipment to Hope Creek Generating Station.
On l
September 29, 1989, the fuel loading chambers were shipped by Abla Network Inc., under contract to Public Service Electric and
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Gas (PSE&G) Company, to the Hope Creek Generating Station.
On November '14, 1989, Martin Marietta Energy Systems (RMES)
notified PECo that there was a 5 gram SNM discrepancy between their records and the PECo Material Balance Report, DOE /NRC Form 742, for September 30, 1989.
After being notified, PECo identified the serial numbers of the SNM in question to be the two fuel loading chambers that had been shipped to Hope Creek Generating Station on September 29, 1989.
Since it was not
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Attachment
Page 4 of-6 Inspection No. 50-353/89-32 r
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recognized by PECo that the shipment contained SNM, no DOE /NRC Form 741 was processed for transmittal to MMES and to PSE&G.
Additionally, this shipment was not reported to the NRC on the DOE /NRC Form 742 that was issued by PECo dated September 30, 1989.
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Corrective Actions Taken and Results Achieved On November 16, 1989, PECo acknowledged receipt of the shipment of the fuel loading chambers to LGS on a duplicate DOE /GRC Form 741 reissued by Reuter Stokes Inc.
Copies of the Form 741 were transmitted on November 16, 1989, to Reuter Stokes, Inc. and to MMES as directed by NUREG/BR-0006.
On December 7, 1989, a DOE /NRC Form 741 was issued from PECo to MMES and to PSE&G for the shipment of the fuel loading chambers to Hope Creek Generating Station that occurred on September 29, 1989.
Per conversation between PECo and MMES on November 14, 1989, PECo will document both the receipt and shipment of the fuel loading chambers on the next Semi-annual DOE /NRC Form 742.
This report will be completed by April 30, 1990.
Corrective Actions to Avoid Future Non-Compliance 1.
Reactor Engineering implementing procedures will be developed to supplement Procedure A-44, "Special Nuclear Material Accountability," and will include the following:
o Provide detailed instructions for the onsite handling of a DOE /NRC Form 741.
These instructions will include the formal transmittal of the DOE /NRC Form 741 to the corporate office.
This will ensure that every DOE /NRC Form 741 is recorded into the LGS SNM Accountability System and included into the next required DOE /NRC Form 742.
o Provide guidance to assure that communication is coordinated between the plant and corporate groups which handle SNM accountability.
These items will be completed and implemented by April 30, 1990.
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Attachment Paga 5 of 6 Inspection No. 50-353/89-32
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2.
Reactor Engineers and the various other personnel working with SNM items will receive formal training in SNM identification, handling, security, and regulatory requirements.
This training will include a yearly one day requalification training for the Reactor Engineers.
The SNM formal training sessions will begin during the 1991 calendar year.
While the lesson plans for this '
formal training are being developed, Reactor Engineering personnel will receive training within their group on the handling and identification of SNM.
This interim training will be completed by May 31, 1990.
In addition to the Corrective Actions identified in Items 1 and 2 as stated above, the following additional actions will be implemented.
A.
Detailed routine procedures to supplement Procedure A-44 will be written tot o
govern the recording and logging of all movement of SNM at LGS, and o
control the handling, security, and tagging requirements of SNM.
These items will be completed and implemented by April 30, 1990.
B.
Procedure A-44 will be revised to accomplish the following.
o Provide guidance to outline work group interactions and regulations governing the procedures to be implemented in the additional Action A, as stated above.
o Provide for tagging of all SNM in storage or transit by requiring the use of distinctive tags.
The tags will identify the SNM and will require Reactor Engineering approval prior to the SNM being moved.
The significance of SNM tags will be addressed as part of General Employee Training (GET).
These items will be completed and implemented by April 30, 1990.
C.
Additional Reactor Engineering implementing procedures will be developed to supplement Procedure A-44 to atsomplish the following:
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Control the increased physical barriers for SNM
that will be developed (i.e., locked storage cage i
for SNM and LGS storeroom computer coding that
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notifies Reactor Engineering when SNM is being
" signed out" or removed from the storeroom).
This item will be completed and implemented by i
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September 15, 1990.
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o A detailed routine procedure will be written to supplement. Surveillance Test Procedure ST-3-097-I 350-0, " Annual Inventory of Special Nuclear i
Material," to conduct increased periodic auditing
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of SNM at LGS.
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This item will be completed and implemented by April 30, 1990.
The Corrective Actions above were identified by using the
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Human Performance Evaluation System (HPES) toot cause analysis techniques in conjunction with an appointed task force.
Date When Full Compliance Will Be Achieved Full compliance will be achieved by April 30, 1990 when PECo submits to the NRC the next Semi-annual DOE /NRC Form 742.
This report will document both the receipt and shipment of the i
fuel loading chambers.
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