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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 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 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 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 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 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 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 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 ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 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 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 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 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 OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT
MONTHYEARML20246P4001989-03-23023 March 1989 Advises That Financial Assurances for Protection of Common Defense & Security Provided by Alchemie Accepted.Notifies That Any Activities by Alchemie Involving Access to Classified Machines & Info Must Be Under DOE Security ML20153G7431988-04-29029 April 1988 Advises That Second Graded Plant Exercise Will Be Conducted on 880607-09.State & Local Officials Refuse to Participate in Emergency Response Planning.Nrc Requests Space to Operate Federal Control Cell to Simulate State & Local Officials ML20151N2251988-04-26026 April 1988 Discusses Draft Control Plan & Request Review of Plan.If Agreement Reached,Plan Will Then Be Modified to Cover Seabrook Situation.Draft Control Plan Encl ML20205E9961987-11-0909 November 1987 Forwards Certified Index of Records in Listed Case ML20205E2041987-11-0505 November 1987 Forwards Respondent Motion to Dismiss Commonwealth of Ma in Listed Case ML20211D9811986-10-14014 October 1986 Requests Fr Publication of Encl 861014 Notice of Environ Assessment & Finding of No Significant Impact,Approving Exemptions from Apps a & J & GDC 13 & 17.Publication Requested as Soon as Possible So Licenses Can Be Issued ML20214M0371986-08-22022 August 1986 Requests That Liquid Samples Spiked w/Sr-89,Sr-90,H-3 & Fe-55 Be Sent to Listed Region II Licensees,Except Farley, Per NRC Confirmatory Measurements Program.Samples Should Be Sent within Approx 2 Wks of Ltr Receipt ML20195E9161986-06-0404 June 1986 Forwards DM Stahl,Counsel for Commonwealth Edison Co,860527 Ltr Addressing Allegations of Illinois Municipal Electric Agency Re Need for OL Antitrust Review.Related Correspondence ML20196L2131986-05-13013 May 1986 Provides Comments Re Draft Evaluation Rept for Plant 860403 Emergency Exercise.No Concerns Observed Which Could Adversely Impact Public Health & Safety ML20198G7221985-12-18018 December 1985 Forwards Util Request for Exemption Re Plume Exposure Pathway Emergency Planning Zone.Nrc Reviewing Request. W/O Encl ML20235A7441985-12-17017 December 1985 Forwards Rept TEI-837, Geologic & Seismic Investigations of Proposed Nuclear Power Plant Site on Bodega Head,Sonoma County,Ca. W/O Rept ML20214F5951985-09-19019 September 1985 Forwards Std Order for DOE Work, Review of PRA for Seabrook Nuclear Power Plant, Authorizing Extension of Period of Performance from 850930 to 860930 Due to NRC Request to Meet W/Applicant Prior to Issuance of Final Rept ML20214F6031985-08-30030 August 1985 Forwards Std Order for DOE Work for FIN A-3778, Review of PRA for Seabrook Nuclear Power Plant, Authorizing Funds for Encl Statement of Work Mod ML20133N1721985-08-0707 August 1985 Requests Info Re Federal Response Ctr Locations for Incorporation Into Region I Incident Response Plan.Fema Region I Will Be Informed by Phone Upon Activation of Incident Response Ctr ML20133M9161985-08-0707 August 1985 Requests Federal Emergency Response Ctr Locations Proposed by FEMA Region II for Nuclear Power Stations on Encl List. Initial Contact Message That Will Be Used to Notify Region Upon Activation of Incident Response Ctr Encl ML20209D3421984-09-27027 September 1984 Forwards Project Identification Summary Sheets Outlining Two Addl Tasks for Review of Seismic Design Licensing Condition. Response Re Adequacy of Funding Requested.Meeting W/Usgs in Early Oct Suggested.Tasks Should Be in Place by 850101 ML20138C1471984-09-13013 September 1984 Forwards,For Concurrence,Std Order for DOE Work, Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819.INEL Proposal Dtd Sept 1984 Acceptable.Lp Leach 850905 & 20 Ltrs to DOE Encl ML20138C1171984-08-24024 August 1984 Forwards,For Concurrence,Std Order for DOE Work,Changing Statement of Work for Evaluation of Selected NRC Open Items Before Plant Fuel Load, (FIN A-6819,Project 2) ML20244D0241984-08-0707 August 1984 Requests That USGS Send Representatives as Observers to 840823 Meeting to Respond to Questions in Seismology & Geology.Related Documents Encl ML20138C1701984-07-31031 July 1984 Approves DG Bowers & H Margulies as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per Inel 840727 Request.Related Documentation Encl IA-84-751, Approves DG Bowers & H Margulies as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per Inel 840727 Request.Related Documentation Encl1984-07-31031 July 1984 Approves DG Bowers & H Margulies as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per Inel 840727 Request.Related Documentation Encl ML20138C0191984-07-18018 July 1984 Approves CM Rice & W Stratton as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per LP Leach 840717 Request ML20138C0051984-07-0202 July 1984 Forwards Std Order for DOE Work,Supporting Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2.Proposal Requested within 14 Days ML20126E0591984-05-0303 May 1984 Forwards Std Order for DOE Work: Resolution of Waterford Unit 3 QA, Approved as Modified ML20127M9671983-10-20020 October 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion, Providing Addl Funding to Complete Work in Oct 1983 ML20128M7391983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20127M7991983-09-0202 September 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion, Providing Funds for Work During Oct 1983 ML20127A8241983-08-0404 August 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core- Melt Accidents;Operating Reactor Reviews for Indian Point & Zion ML20244C3751983-07-0606 July 1983 Requests Info on Presence of Plant & Animal Species Listed or Proposed as Threatened or Endangered,In Vicinity of Site as Shown on Encl Maps ML20244C1641983-03-30030 March 1983 Confirms 830328 Telcon Re Postponement of 830330 Meeting on Questions for Util to 830414 in Bethesda,Md.New Date for Submittal of Final Questions to Div of Licensing Is 830419 ML20155C0101983-02-11011 February 1983 Forwards Std Form 83,supporting Statement Covering Info Collection Requirement Re Licensee Analyses of Significant Hazards Issues in Amend Requests & SECY-83-16 & SECY-83-16A. Approval Requested by 830213.W/o Secy Papers ML20127A4361983-01-24024 January 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core- Melt Accidents:Gessar - Fda,Limerick - Ol,Fnp - Ml ML20127A4471983-01-24024 January 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core Melt Accidents:Indian Point-OR & Zion-OR, Providing Addl Funding for FY83 ML20127A4151983-01-0404 January 1983 Requests Proposal from BNL to Provide Technical Assistance to Div of Sys Integration Through FY85 Re Safety Evaluation of Core Melt Accidents:Cessar - Final Design Approval; Westinghouse Std Plant - Final Design Approval ML20101C7221983-01-0404 January 1983 Requests Proposal from BNL to Provide Technical Assistance Through FY85 for Safety Evaluation of Core-Melt Accidents: CESSAR-FDS,Westinghouse Std Plant - Fda. Statement of Work Encl ML20127E4571982-12-30030 December 1982 Forwards Unexecuted Std Order for DOE Work for Safety Evaluation of Core Melt Accidents:GESSAR-FDA,Limerick-OL & FNP-ML ML20127M2961982-12-30030 December 1982 Forwards Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Accepting BNL 821203 Proposal & Providing Funds to Begin Work ML20244B5911981-09-0303 September 1981 Extends Appreciation for Participation & Assistance in Hearing.Knowledgeable Presentation at Hearing & Invaluable Guidance Before & During Hearing Contributed to Effective NRC Staff Presentation ML20244B5791981-09-0303 September 1981 Extends Appreciation for Participation & Assistance in Hearing.Knowledgeable Presentation at Hearing & Invaluable Guidance Before & During Hearing Contributed to Effective NRC Staff Presentation ML20244B5751981-09-0303 September 1981 Commends Hg Greene Participation in NRC Hearing,Which Contributed to Development of Sound & Complete Record on Complex Issue in Proceeding.Appearance Was Articulate & Presented in Forthright & Knowledgeable Fashion ML20083L3681981-01-21021 January 1981 Forwards Short & long-term OL & CP Review Schedules,In Response to 801216 Meeting W/Usgs.List of OL Plant Reviews for Which NRC Tentatively Plans to Seek USGS Assistance Is Provided ML20235X6731979-12-10010 December 1979 Forwards B Slemmons 791125 Comments & Questions & J Davis 791004 Questions Re Facility Review ML20235X6611979-09-20020 September 1979 Forwards Three Listed Repts Re Seismological Studies Due to USGS Involvement in Review of Facility.W/O Encls ML20235X6291979-02-14014 February 1979 Requests Confirmation of Availability to Perform Review of FSAR Amend Re Seismology.Rept Delayed Until 790331 ML20235X6251979-02-0202 February 1979 Confirms 790119 & 26 Telcons Requesting USGS Consider Undertaking Review of FSAR Amend,Including Approach for Determining Max Earthquake Magnitude on Offshore Fault Zone That Differs from Fault Length Vs Magnitude Approach ML20204C9001978-11-24024 November 1978 Forwards Statement to Congress on NRC Actions Being Taken Re Gao Recommendation on Floating Nuc Pwr Plants ML20235X5011974-09-27027 September 1974 Forwards Preliminary Rept on Recently Observed Geologic Features for Info.W/O Encl ML20235X4801974-07-11011 July 1974 Advises That Analysis of Geologic Features at Facility Being Transmitted Under Separate Cover,For Info ML20235X4691974-01-0707 January 1974 Forwards Background Matl Developed Re Tsunamis for Sites as Listed ML20126D8711973-03-12012 March 1973 Requests Assistance in Site Geologic Evaluation of Vogtle & Catawba Sites.Schedule for Input Dates Listed.Requests AEC & Schedule Dates Be Disregarded 1989-03-23
[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
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SBoyd Brookhaven Area Office DDandois
.U. S. Department of Energy DCorley
'Upton, tiew York 11973 ZRosztoczy
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Dear Mr. Ogeka:
1 3
SUBJECT:
DHL TECHilICAL ASSISTAilCE TO THE DIVISION OF SYSTEMS IllTEGRATION, i;RR,tiRC
" SAFETY EVALUATI0tl 0F CORE MELT ACCIDEUTS:
v LIMERICK-OL,FHP-ML(Fill #A-3711)
GESSAR-FDA,
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~ The enclosed tiRC Fom 173, Standard Order for CCE tlork, is hereby submitted in
'f accord 5nce with Cection III.B.2 of the DOE /HRC Memorandum of Understanding, dated February 24.' ~ 1978.
'x, lie have reviewed'the BUL proposal for this project, dated DecerL9r 10,1982, and find it acceptable. The enclosed order provides funding authorizatton in the amount of $80,000 to imediately begin work.
The balance of the
' funds for completion of the project will be provided incrementally at a later date.
If a portion of the work is to ce subcontracted, it is required that Ei1 have a professional assigr,ed to the contract who is cualified to defend the results. Also, prior approval by me in writing is required before initia-tion of any subcontract effort.
If you have any questions concerning the acceptance of this order, please contact Mrs. Sybil Coyd on FTS 492-7685.
Sincerely.
OrrWalsigned by RogerJ.Mattson 850S200084 840920 PDR FOIA Roger J. Mattson, Director SHOLLYB4-243 PDR Division of Systems Integration y
Office of ?!uclear Reactor Regulation
Enclosure:
MRC Forin 173
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cc: R.'Bari, BUL T. ilomano, Bill ll. Kato, CUL
- 11. T. Pratt, Bl3.
1 H. Grahn, C!il PPA (RRQ R. Dauer,00E/CH A'
R. Barber, 00E-HQ BLG et
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JMeyer-
. b ry J. Ogeka. Chief Administrative Branc Brookhaven Area Office U. S. Department of En Upton. New York 11973
Dear Mr. Ogeka:
SLBJECT:
BNL TEQiNICAL ASSISTANCE TO THE DIVIS ON OF SYSTEMS INTEGRATION.
NRR. NRC
" SAFETY EVALUATION OF MELT ACCIDENTS: GESSAR-FDA.
LIERICK-OL, FNP-ML"- (FIPMA-371 The. enclosed-NRC Fem-173 Standard-Ord DOE Work is hereby submitted in accordance with Section III.B.2 of the
. NRC Menorandum of Understanding, i
dated February 24. 1978.
We have reviewed the BNL proposal for his pro 10, 1982 orderpro(ect,datedDecember and find it acceptable. The enclos
-in the amount of $80.000 to inueediately begin wor $ des funding authorization v,
k.
The balance of the funds for completion of the proj t will be provided incrementally at a later date.
If you have any questions concerning the acceptance ofsthis order, please contact Mrs. Sybil Boyd on FTS'492-7685.
\\
Sincerely.
Or! lrmr s'gned by *
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R e eJ k t'uon Roger J. Mattson. Director Division of Systans In tion. NRR c
Enclosure:
NRC Fom 73 cc:
R. Bari. BNL T. Romano. BNL W. Kato. BNt' W. T. Pratt. BNL i
H. Grahn.,5NL R. Bauer-
.R. Barber, DOE-CH
. DOE-HQ PPAS NRR BGrenier l l (Q
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BC FORM 318 (10-80) NRCM C240 OFFICI AL R ECO@@LCcXd@V
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f 4 NRC poRu 173 u 5. NUCLEAR racutArony coweissics onoan Nuusa m
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20-83-209.
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STANDARD ORDER FOR DOE WORK 0?C 3 01983 ISSUED TO: IDOE Offical ISSUED BY: (NRC Office)
ACCOUNTING CITATION Brookhaven Area Office.
Office of Nuclear Reactor
^"aoaa'^mN smsou Regulation, DSI J1X0200.203 St.R NUM SER PERFORMING QRGANIZATION AND LOCATION 20-19-40-41-3
.Brookhav'en National Laboratory FIN NUMBER e
Upton, fly A-3711-3 WORK PERIOD THIS ORCER FIN TITLE FIXED C
- ESTIMATED D Safety Evaluation of Core-Melt Accidents: BESSAR-FDA, FROM:
TO:
Limerick-OL, FNP-ML 1/14/83 1/15/84 08 LIGATION AVAi[ ABILITY PROVIDED BY:
A. THIS ORDER S-~
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'ufoYR TkUEiE AeeEiUiOr75vT8OL'F "E^
1,2'59,0d0 AN E 1RS FOUR IS F E
S esR NUMeER CITED asCvE.
C. TOTAL ORDERS TO DATE ITOTAL A & 81 8 1,339,000' 0 AMOUNT INCLUDED IN "C** APPLICARLE TO THE " FIN NUM8ER** CITED IN THIS ORDER.
S g
FINANCIAL FLEXistLITY:
Q FUNOS WILL NOT BE REPROGRAMMED 8ETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON 088,1GATI'ONS AU THORIZE D.
@ ON 08 LIGATIONS AUTHORIZED.1/
FUNDS MAY BE REPROGRAMMED NOT TO EXCEED 210*' OF FIN LEVEL UP TO $50K. LINE C CONSTITUTES d f.lMITA SEE BELOW STANDARD TERMS AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THIS ORDER l
UNLESS OTHERWISE NOTED.
ATTACHMENTS:
THE FOLLOWING ATTACHMENTS ARE HERE8Y SECURITY:
MADE A PART OF THIS ORCER:
Q WORK ON THIS ORDER 15 NOT CLASSIFIED.
d STATE *AENT OF WOR K Modification.
O WORK ON THl3 ORDER INVOLVES CLASSIFIED C ADDITIONALTERMS AND CONDITIONS INFORMATION. NRC FORM 187 IS ATTACHED.
O OTHER r.EMARKS (Reference the proposal by number and date. and indicate of the attached statement of work modofres the DOE proposaq:
This order provides incremental funds for initiation of work in accordance with the Bill-proposal dated December 10, 1982, as modified by the attached revised
-format for the monthly business letter report.
- After accep nce, please send to the NRC Office of Resource Management, ATTN: D. Dandois and, provide a copy to the Office of Nuclear Reactor Regulation, ATTN: D. Corley and S.Boyd ISSUING AUTHORITY ACCEPTING ORGANIZATION Roger J. Mattson, Director bfh 5tGNarung SIG N A T U R E
- r. rte v
vitte Division of Systems Integration I (ic/12-
~hangis on Utls withi)n.f-Reprogramming 1imited'to N:C FO n Is-ni
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the same B&R Number and the ame Appropriation Symbol.
In order for this reallocation to be effective this office mu otified within 5 days so that an appropriate NRC Form 173 can be issued alid counter-signebt be to c'nplete the action prior to' receipt of any bills.
. - -. - ~ - - - - - - -
Bus.fness Letter Report [
]
A monthly business letter r3 port will be submitted by the 15th of the month
- ~'to the Project Officer with copies provided to the Contracting ~ 0ff'icer, the Director, Division of Systems Integration, ATTN: Program Assistant, Branch Chief, - and B. L. Grenier, NRR.
These reports will identify the titl'e of the project, the FIN, the contract number, the Principal Investigator, the period of performance, and the reporting period and will contain 3 sections as follows:
Project Status Section 1.
A listing of the efforts completed during the period; milestones reached, or if missed, an. explanation provided.
2.
. Any problems or delays encountered or anticipated and recommendations for resolution. 3_/
3.
A summary o'f progress to date (this may be expressed in terms of percentage completion. for each task).
- 4.. Plans for the next reporting period.
Financial Status Section l'.
Provide the total cost (value) of the project as reflected.in the proposal contract and the total amount of funds obligated to date as follows:
Total Prior To FY* Funds Projected Projected FY*
FY*
Obligated FY
- Funding Project Cost Funding Level Carryover To Date Bal. Needed 2.
Provide the total amount of funds expended (costed) during the period and cumulative to date as follows:
a.
Direct 1 abor Project.
Cumulative
_b.
Indirect 1 abor c.
ADP Support d.
Travel e.
Subcontracts f.
Equipment & Materials g.
Overhead (G8A)
Total
( ")F identify fiscal year using, as appropriate, the applicable fiscal year; dollars
-=
in thousands.
- 1. / If the recommended resolution involves a contract modification, e.g., change in work requirements, level 6f effort (costs), or period of performance, a separate letter should be prepared and submitted to the Contracting Offic'er. DC, with copies provided to the Director, Division of Systems Integration, ATTN: Project Officer, and B. L. Grenier, NRR.
_2_, / Provide percentage against total funds obligated to date.
, r'
')
J5'Fe>RecoveryCostStatussection
-Pursuant to the provisions of HRC Regulations,10 CFR 170, provide the total amount of funds expended (costed) during the period and cumulative to date
-for each task in the followino format:
FIN:
B3711 TITLE:
Safety Evaluatica of Core-Melt Accidents: GESSAR-FDA, Limerick-OL, FNP-ML Period:
Task I:
Severe-Accident Progression Analysis: Reactor Systems / Containment Systems Loadings and Failure Modes Facility Docket #-
Period Cumulative
.GESSAR-238HI 50-447 Limerick 1 50-352
-FNPl-8 50-437 Task II:
Radionuclide Release Assessment l
Facili ty Docket #
Period
, Cumulative GESSAR-238NI 50-447 Limerick 1 50-352 FNPl-8 50-437.
Task III:
Consequence Analysis
. Facility Docket #
Period Cumulative GESSAR-238HI 53-447 Limerick 1 50-352 FPP1-8 50-437 Task IV:
Risk Assessment Summary Facility Docket #
Period Cumulative GESSAR-238NI 50-447 Limerick 1 50-352 FNPl-8 50-437 Note:
If there is any effort under any of these tasks that is generic in nature such -that the effort is required in order to perform the
- evaluation of any submittal., the cost for the generic effort should be prorated to each facility-to which it applies; for example during FY 1983, costs should be prorated equally to GESSAR and Limerick and in FY 1984 to FNP as appropriate.
9
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,p-NRR TECHNICAL. ASSISTANCE PROGRAM PPAS ACTION SU!7.ARY SHEET-DATE. RECEIVED BY PPAS:
1 30/P2
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'FI!(S): hh7/[
' TYPE OF ACTION:
O h
80t mmM PPAS ' REMARKS, COMMENTS, IDENTIFICATION OF DEFICIENCIES:
00CUME !T(S) MISSIiG FRC:4. FILE e
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1 1
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