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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 VENDOR/MANUFACTURER
MONTHYEARML20140F3691986-01-14014 January 1986 Further Response to FOIA Request for Several Categories of Documents Re Pressure Suppression Containment.Fsar & SER for Limerick Only Documentation Re 4x4 Tests.Encl Apps D-G Documents Responsive to Item 4 Also Available in PDR ML20204G6881984-06-27027 June 1984 Accepts GE Proposed post-irradiation Fuel Surveillance Program.Basis for Acceptance Is Concern for Assuring Adequate Verification of Safe Fuel Performance & Maintaining Efficient Use of Industry Resources 1986-01-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20206Q5871999-05-14014 May 1999 Advises That Info Contained in ,Which Submitted Revised Procedures for Plant EP Response Procedures Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R3031999-05-11011 May 1999 Informs That on 990407,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Forwards Copies of Both Forms of Exam,Including Answer Keys & Grading Results of Facility ML20206N1111999-05-0707 May 1999 Forwards Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206H2651999-05-0606 May 1999 Informs That on 990112 Licensee Submitted to NRC Core Shroud Insp Plan for Plant,Unit 2,in Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors ML20206G5131999-05-0303 May 1999 Approves Change of Completion Date for Implementation of Thermo-Lag Fire Barrier Corrective Actions at Plant from End of April 1999 Limerick Unit 2 RFO to 990930 ML20206H8301999-04-30030 April 1999 Forwards Exam Repts 50-352/99-301 & 50-353/99-301 on 990312-19 (Administration) & 22-26 (Grading).Four of Five RO Applicants & Three of Four SRO Applicants Passed All Portions of Exams ML20206E6951999-04-30030 April 1999 Advises That Plant,Unit 2 Cycle 6 Safety Limit Mcpr, ,contained in PECO Energy Co 990311 Application & 990204 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20206F4221999-04-27027 April 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990312 & 990315-19 at Facility.Completed ES-501-2,power Plant Licensing Exam Results Summary & Summary of Overall Exam Results Encl.Without Encl ML20205N2291999-04-0909 April 1999 Discusses Limerick Generating Station Plant Performance Review Conducted for Period April 1998 Through 990115 & Informs of NRC Planned Insp Effort Resulting from Review. Historial Listing of Plant Issues,Encl IR 05000352/19980091999-03-30030 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-09 & 50-353/98-09 Issued on 990106.Actions Will Be Examined During Future Insp of Licensed Program ML20205C2711999-03-26026 March 1999 Forwards Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301.One Violation Noted & Being Treated as Non-Cited Violation.Staff Conduct of Activities During Insp Generally Characterized by Safe & Conservative Decision Making ML20205G7651999-03-22022 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 90 Days of Receipt of Ltr ML20204G9721999-03-11011 March 1999 Informs of Completion of Review of Changes Proposed by PECO Energy Co to Lgs,Units 1 & 2,EALs.Proposed EALs Incorporate Guidance in NUMARC/NESP-007,Rev 2.Forwards Safety Evaluation Supporting Proposed Changes ML20204H8171999-03-10010 March 1999 Discusses Request That NEDC-32645P, Limerick Generating Station,Units 1 & 2,SRV Setpoint Tolerance Relaxation Licensing Rept, Rev 2,dtd Dec 1998,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20207J0611999-03-0808 March 1999 Provides Authorization to Administer Initial Written Exams to Listed Applicants on 990312.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 990315-19 at Limerick Generating Station ML20203G6721999-02-17017 February 1999 Second Partial Response to FOIA Request for Documents. Records in App D Encl & Being Made Available in Pdr.App E Records Being Withheld in Part (Ref FOIA Exemption 5) & App F Records Completely Withheld (Ref FOIA Exemptions 6 & 7) ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J0261999-02-0303 February 1999 Informs of Completion of Licensing Action for NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors ML20203A6111999-01-22022 January 1999 Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705 ML20199F9251999-01-11011 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-05 & 50-353/98-05 ML20199C6501999-01-0606 January 1999 Forwards Insp Repts 50-352/98-09 & 50-353/98-09 on 981018- 1130 & Notice of Violation.Violation of Concern Because Technicians Exercised Poor Judgement & Deviated from Procedure in Attempt to Resolve Problem Without Mgt ML20198H4951998-12-18018 December 1998 Forwards Results of Audit of Licensee Year 2000 Program for Limerick Generating Station,Units 1 & 2 ML20198A3721998-12-10010 December 1998 Forwards Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20198B1751998-12-0808 December 1998 Advises of Planned Insp Effort Resulting from Limerick mid-year Insp Resource Planning Meeting Held on 981110. Historical Listing of Plant Issues & Details of Insp Plan for Next Six Months Encl IR 05000352/19980081998-11-23023 November 1998 Discusses licensee-identified Issue Involving Potential for Bypass of Suppression Pool as Documented in Insp Repts 50-352/98-08 & 50-353/98-08.NOV Will Not Be Issued & Civil Penalty Will Not Be Proposed ML20196C3311998-11-23023 November 1998 Forwards Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violation Identified.Security Program Insp Identified That Security Program Effectively Protects Public Health & Safety ML20195D1491998-11-13013 November 1998 Forwards RAI Re on-going Review of IPEEE Submittal Dtd 951014.Understands That Licensee Will Inform NRC in Writing, by 981130,on How Question Re Effects of New Probable Max Precipitation at Plant,Units 2 & 3 Will Be Addressed IR 05000352/19980061998-10-15015 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-06 & 50-353/98-06 on 980826.Finds C/As for Violation Involving Failure to Select Performance Measures to Be Acceptable ML20154F8191998-10-0101 October 1998 Forwards Notice of Withdrawal of 960503 & Suppl Application for Amend to Fols.Amend Would Have Modified Facility TSs Pertaining to Rev to Frequency of Testing Stand Gas Treatment Sys & Reactor Encl Recirculation Sys ML20154A3461998-09-25025 September 1998 Forwards Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Weaknesses Noted with Reactor Engineering Support to Rod Pattern Adjustment ML20153G4291998-09-24024 September 1998 Forwards Request for Addl Info Re Licensee Revised Emergency Action Level Guidelines for Limerick Generating Station, Units 1 & 2 & Peach Bottom Atomic Power Station,Units 2 & 3. Response Requested within 30 Days of Receipt of Ltr ML20153D0151998-09-21021 September 1998 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Plant, Units 1 & 2 ML20151X2421998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-04 & 50-353/98-04 on 980805 ML20151W9601998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Were Selected as SRAs for Region I ML20237D5421998-08-26026 August 1998 Ack Receipt of & Fee for $55,000 in Payment for Civil Penalty Proposed by NRC in .C/As Will Be Examined During Future Insps 1999-09-09
[Table view] |
Text
._. _ _ _ _ . _- _ ____
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m\ g UNITED STATES NUCLEAR REGULATORY COMMISSION
,, . gh' ,a WASHINGTON, D. C. 20555 i .8.EC Ely E D JUN 2 71984 . tin. - 21984 Mr. R. L. Gridley, Fuel and Services MFN-087 h l N.% EY.
Licensing Manager Nuclear Safety & Licensing Operation -
General Electric Company 175 Curtner Avenue San Jose, California 95125
Dear Mr. Gridley:
Subject:
Acceptance of GE Proposed Fuel Surveillance Program -
References:
(1) J. S. Charnley (GE) to C. H. Berlinger, (NRC), " Post-Irradiation Fuel Surveillance Program" November 23, 1983.
(2) L. S. Rubenstein (NRC) to R. L. Gridley (GE), " Post-Irradiation Fuel Surveillance", January 18, 1984.
(3) J. S. Charnley (GE) to L. S. Rubenstein (NRC), " Fuel Surveillance Program", February 29, 1984.
(4) J. S. Charnley (GE) to L. S. Rubenstein (NRC), " Additional Details Regarding Fuel Surveillance Program", May 25, 1984. .
Reference 1 contained a GE proposal for a program to satisfy the regJirenent for~ a post-irradiation surveillance program described in Section 4.2.II.D.3 of the Standard Review Plan. While the Standard Review Plan addresses guidelines and requirements for license applicants, we understand that GE .
- proposes to accept the responsibility for post-irradiation surveillance of GE. designed and manufactured fuel assemblies. This program would then be referencable by applicants proposing to use GE fuel as demonstrating satisfactory compliance with Section 4.2.II.D.3 of the Standard Review Plan.
In Reference 2 we agreed to your proposal in principle but requested clari-fication of several points. Continuing discussion and clarifications are !
reflected in References 3 and 4. As a result of these clarifications we now find the GE proposal acceptable for post-irradiation fuel surveillance. It ,
4 is our understanding that this program consists of the following. 1
- 1. For new fuel designs, GE will conduct a general visual examination of the exterior surfaces of a statistically meaningful number of fuel bundles upon discharge. The examination will be conducted as described in the Attachment to Reference 1.
This examination will be conducted at two applications of the new design fran the first year in which the design is introduced, as described in Reference 4.
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ATTACllMENT 4 j! of 3 )
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~
' . . Mr. R. L. Gridley '
Oh % 7 gg
- 2. Lead Test Assemblies (LTAs) of new fuel designs will be utilized to-test
. new fuel features. These LTAs will be precharacterized and inspected '
after irradiation using the non-destructive testing techniques described in the Attactinent to Reference 1. -
l
- 3. GE's current fuel surveillance program for standard fuel designs will be -
continued at its present level of effort and the results of this program !
will be reported to the NRC in a yearly operating experience report.
As discussed with you earlier, we view this program as satisfying the Standard Review Plan requirenent for routine post-irradiation surveillance. If a problen were to arise with GE designed fuel for which increased surveillance would be useful, surveillance in addition to.that contained in this program inay ]
be required. !
In addition, this program in no way lessens our intent that licensees maintain 1 an effective on-line surveillance effort as described in Section 4.2.II.D.2 of the Standard Review Plan.
This program will apply only to GE designed. and manufactured fuel and will not necessarily change any commitments made by a licensee with respect to fuel l manufactured by other vendors which may be in the licensee's reactor.
Our basis for acceptance of your proposed program for post-irradiation fuel surveillance is twofold. First, we share your concern with attempting to i'
assure adequate verification of safe fuel performance while still maintaining efficient use of industry resources. We believe the program, as described above, does this. In addition, the industry's fuel surveillance programs have, in the past, been responsible for the discovery of the major fuels related probles without initial NRC involvenent. The test of this program will be the extent to which GE continues to discover any new anomalies in a timely and effective way.
Si cerel -
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. ,d t /i. u @ i M' L. S. Ru nstein, Assistant Director for Core and Plant Systems i Division of Systems Integration Office of Nuclear Reactor Regulation t
4
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Esgs 6 of 3 ATTACHMENT l.
General Electric Fuel Performance Verification Program The General Electric fuel performance verification program consists of inspection of lead test assemblies (LTA's) for new designs, and offgas monitoring of all designs throughout their lifetime.
For new fuel designs, GE will, in addition, agree to conduct a general visual examination of the exterior surfaces of a statistically significant
, number of fuel bundles (12 bundles).upon discharge from each of two early commercial applications of the new product. The visual examination will be made using binoculars, borescope, periscope, or TV and will be suffi-cient to meet the objectives presented in SRP 4.2 for visual inspections.
The schedule and scope of LTA inspections is contingent on both the .
availability of the fuel as influenced by plant operation and the expected value of the information to be obtained.
General Electric's LTA's are selectively inspected using one or more of the following techniques:
- 1) Leak detection tests, such as sipping.
- 2) Visual inspection with various aids such as binoculars, borescope, or periscope, with a photographic record of f
observations as appropriate. .,
- 3) Nondestructive testing of selected fuel rods by ultrasonic and eddy current test techniques.
- 4) Dimensional measurements of selected fuel rods.
l Unexpected conditions or abnormalities which may arise are analyzed, and
! examination of selected fuel rods in hot cell facilities may be undertaken
- when the expected value of the information to be obtained warrants this type of examination. Results of this surveillance program will be updated annually by a GE proprietary letter report.
The use of LTA's provides early verification of performance targets as well as early indication of potential performance anomalies.
Specific plant fuel failures are accurately detected by offgas surveil-lance. Offgas surveillance is performed for all operating plants, and leak detection tests such as sipping are performed by the utilities at the end of each cycle, if warranted (based on analysis af the offgas surveillance results). Offgas surveillance is a very sensitive measure of fuel performance, and General Electric fuel failure statistics include fuel failures estimated as a result of offgas measurements. These fuel failure statistics will be updated in the annual letter report.
If many fuel failures are detected, an analysis or investigation is initiated to determine the cause of the failures. In addition to review of operational parameters such as power history and water chemistry and of GE's current overall fuel experience base, the investigation may include site examinations, and when appropriate, searches of manufac-turing records, tests of manufactured spare rods if available, and hot cell examination of selected irradiated fuel rods.
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