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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 U.S. CONGRESS
MONTHYEARML20236G5871987-07-30030 July 1987 Responds to 870617 Request for Info Re GE Reed Rept on LER Sys.No Issues Raised in Reed Rept Support Need to Curtail Operation of GE BWRs ML20215F2291986-12-16016 December 1986 Responds to Re Constituent Concerns.Concerns Carefully Considered & Given Thorough Response Consistent W/ Commission Regulations & Adequate Protection of Public Health & Safety NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls1986-08-26026 August 1986 Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls ML20138R1581985-12-18018 December 1985 Responds to R Digiacomo 851023 Inquiry Re Recent Issuance of Facility OL & Effect on Costs of Electricity & on Water Conditions in Schuylkill River.No Significant Impact on Water Use or Conditions Expected ML20137U2691985-11-26026 November 1985 Submits Results of Investigation of Constituent R Dobson ,Per 851029 Request.Region I Combined Insp Repts 50-352/85-30 & 50-353/85-07 Re Water Spill Incident Encl ML20132B8341985-07-18018 July 1985 Forwards Quarterly Status Rept for Second Quarter CY85. Licensing Delay for Limerick 1 Projected to Be 5 Months. Delay Cannot Be Quantified for Shoreham Due to Litigation. Full Power OL Issued for Palo Verde 1 on 850601 ML20140H6701985-06-0303 June 1985 Forwards Press Release 85-78 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Unplanned Occupational Radiation Exposures & Failure to Control Contractor Work Forces ML20126B1491980-02-0707 February 1980 Forwards NRC 800130 Response to M Seidts Re Size of Facility Low Population Zone ML20125B6621979-10-12012 October 1979 Responds to Re Fr Romano 790723 Concern About Blasting at Rock Quarry Near Facilities.Request Being Treated Per 10CFR2.206.Effects of Blasting at Nearby Quarry Must Be Carefully Evaluated ML20235F1361971-12-15015 December 1971 Forwards Notice of Hearing to Be Held on Util Application Re Plant.Div of Reactor Licensing Safety Evaluation & Rept to ACRS Also Encl.W/O Encls 1987-07-30
[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] |
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. .. ? .
c9 o UNITED STATES g
8 e NUCLEAR REGULATORY COMMISSION g E WASH lNGTON, D. C. 20555 k .../
n MR.36 E The Honorable Lawrence Coughlin -
United States House of Representatives Washington, DC 20515
Dear Congressman Coughlin:
I am pleased to have the opportunity to respond to your June 17, 1987, request for information regarding the (1) 1975 General Electric Company (GE) study herein referred to as the " Reed Report" (named for its principal author, Dr. Charles E. Reed, a senior engineer at GE) and (2) an article in the Times Herald of Norristown, Pennsylvania, regarding the NRC's " licensee event report system."
It should be noted first and foremost that the NRC staff did review the Reed
-Report'on a number of occasions, as discussed below. On the basis of its review of each of the issues addressed in the report, the staff determined that the Reed Report did not identify significant new safety issues.
l Another thorough NRC staff review of the Reed Report has recently been completed. A copy of NUREG-1285 is attached for your information. Proprietary and predecisional documents will be made available for your review through our Office of Governmental and Public Affairs.
The Reed Report, prepared in 1975 at the request of the Chainnan of the Board of Directors for General Electric was intended to be an internal critical self-analysis of GE's Boiling Water Reactor (BWR) design for the purpose of product improvement. It addressed future reactor designs and considered steps l to enhance plant performance.
After Dr. Reed testified before the Joint Congressional Committee on Atomic Energy in February 1976, two senior members of the NRC staff reviewed the Reed Report in GE's Washington, DC office. In this review, the staff members did not identify any new safety concerns not already known to the NRC nor any evidence that GE had not met the requirements of Section 206 of the Energy Reorganization Act of 1974 in regard to the reporting to NRC of signi'icant safety concerns. A copy of the memorandum from the two NRC staff menaers to the Director, Office of Nuclear Reactor Regulation, was incorporated in e record of the Joint Committee on Atomic Energy's " Investigation of Charge!
Relating to Nuclear Reactor Safety," held February 18, 23, and 24 and March .
and4,1976(VolumeII,atPage1774).
Since this initial review, the staff has examined the Reed Report several other l
times.
1 g A e70eo40m e7ono pe -cm g l
C__________________._______ _ .________J
o a . . ,
In December 1977, Congressman John D. Dingell requested information on the Reed Report, which the Chairman provided in a letter dated February 9, 1978.
On March 6, 1978, the staff formally asked GE to provide a copy of the Reed Report or a list of the safety issues it raised. On March 22, 1978,.GE gave the NRC a list of 25 issues identified in the report as having some safety significance. On April 11, 1978, members of the NRC staff and a member of Congressman Dingell's staff met at the GE offices in Washington, DC and reviewed the Reed Report. On May 26, 1978, GE gave NRC the status and an evaluation of the 25 issues identified in the report. On November 9, 1978, the staff gave the Commission a draft letter response to Congressman Dingell discussing the staff review and stating the staff conclusion: "
...no substantive disagreement with the summary status provided by GE" (SECY-78-462A). The Chairman forwarded the staff's findings to Congressman Dingell in a letter dated December 27, 1978.
The Commission first received a copy of the Reed Report on January 5, 1979, when GE provided a copy to the Atomic Safety and Licensing Board in the Black Fox proceedings. TheBoardreceiv'dt.ndreviewedthereportincamera,andthe report was not made public. GE categorized the report as " proprietary" and claimed that, under the provisions of the Commission's regulations in 10 CFR I 2.790, the report was exempt from mandatory public disclosure. As part of its l agreement with GE, the Board issued a protective order relating to the inclusion of the Reed Report into evidence in the Black Fox proceedings.
The pertinent terms of the protective order were as follows: (1) the Reed Report was available to the Board in confidence; (2) vercatim extractions were available to counsel insofar as they related to the intervenor's contentions and Board questions; and (3) the Reed Report was available to the intervenor's i counsel to evaluate the faithfulness of the extractions. The parties also signed protective agreements that limited access to and use of the report.
As mentioned above, as a result of the recent renewed interest in the 1975 study, the NRC assembled a task force to restudy the Reed Report from the perspectives gained from the licensing and the operating experience of GE BWRs, including Limerick, Unit 1. The conclusions of the task force are (1) there are no issues raised in the Reed Rt-port that support a need to curtail the operation of any GE boiling water reactor (BWR); (2) there are no new safety issues raised in the Reed Report of which the staff was unaware; and (3) although certain issues addressed by the Reed Report are still being studied by the NRC and the industry, there is no basis for suspending licensing and operation of GE BWR plants while these issues are being resolved.
The other matter you mentioned involved a newspaper article in the Norristown Times Perald regarding the NRC's licensee event report system.
Commission regulations, as given in 10 CFR 50.73 require the holder of an operating license for a nuclear power plant to submit licensee event reports (LERs) on a broad range of events "...regardless of the plant mode or power level and regardless of the significance of the structure, system or component
.s 1
. l that initiated the event." As the article noted, the vast majurity of LERs do not involve significant threats to public safety. The article also quoted an NRC spokesman who stated that of the several thousand events reported each year, only a very few (e.g., nine in 1985) are determined to be significant from the standpoint of public safety; these are reported to Congress on a '
quarterly basis.
There are many purposes behind the NRC's LER system. One purpose is to ensure that licensees thoroughly investigate the cause of any incident and, where appropriate, institute corrective action to prevent a recurrence. The NRC staff evaluates each LER submitted and frequently conducts an independent investigation and assessment. In addition, the staff uses the information from LERs in many ways, such as evaluating whether there is a potential generic problem with an item of equipment. LERs are also used in the NRC's Systematic Assessment of Licensee Performance (SALP), in which we specifically review LERs in regard to type, common mode events, trends, and root-cause identification..
For Limerick, Unit 1, the number of LERs submitted in 1986 was comparatively high, but, as reported ir the recently issued SALP evaluation for Limerick,. j none of the events reported was of unusual safety significance, and no events ,
or problems specific to Limerick were considered significant. Nonetheless, l Philadelphia Electric Company is making a concerted effort to correct the causes of the events that occurred.
\
I hope this letter provides the information you are seeking. Please let me know if we can be of further assistance to you in this matter, i
Sincerely, j orJ ah mm g ,
Il n t cr ,h jag l
. Victor Stello,-Jr'.
Executive Director
. for Operations l En. closure:
As stated l
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i EDO PRINCIPAL-CORRESPONDENCE CONTROL [
_y FROM: DUE: 07/24/87 EDO CONTROL: 003008 DOC.DT: 06/17/87
' REP. ~ LAWRENCE COUGHLIN FINAL REPLY:
TO:
CHAIRMAN ZECH FOR SIGNATURE OF: ** GREEN ** SECY NO: 87-799 l
EXECUTIVE DIRECTOR l
L DESC: ROUTING:
REFERENCE NEWSPAPER ARTICLES CONCERNING POSSIBLE ' RUSSELL DANGERS OF CERTAIN GENERAL ELECTRIC NUCLEAR MURRAY REACTORS SUCH AS LIMERICK j i
DATE: 07/10/87 ASSIGNED TO: NRR CONTACT: MURLEY J
1 SPECIAL-INSTRUCTIONS OR REMARKS:
T) ae b A"% 7 af 1 .
NRR RECEIVED: JULY
{gj10c.198L, ACTION: VgGAgiyq)
.q NRR ROUTING: j MURLEY/SNIEZEK MIRGLIA 3 STAROSTECKI j BLAHA 1 FUNCHES MOSSBURG 4
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C.______. _....._l.__
-o, . ,
~
OFFICE OF THE SECRETARY
. CORRESPONDENCE CONTROL TICKET PAPER NUMBER: CRC-87-0799 LOGGING DATE: Jul 9 87 ACTION OFFICE: EDO AUTHOR: L. .Coughlin AFFILIATION:. U.S. HOUSE OF REPRESENTATIVES
! LETTER DATE: Jun 17 87 FILE CODE: ID&R-5 Limerick
SUBJECT:
Ref news articles concerning possible dangers of certain GE nuc reactors--such as Limerick.
ACTION: Direct Reply DISTRIBUTION: OCA to Ack, Docket SPECIAL HANDLING: None NOTES:
DATE DUE: Jul 23 87 SIGNATURE: . DATE SIGNED:
AFFILIATION:
Rec'd Cli. E00 y { D-O-l 9g, Time _.
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