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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20210P4461997-08-31031 August 1997 Update 2 to TMI-2 Post-Defueling Monitored Storage Sar ML20210T3411997-08-31031 August 1997 Rev 0 to TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20199E5841997-08-18018 August 1997 Limited Liability Company Agreement of Amergen Energy Co, LLC Among PECO Energy Co,British Energy PLC & British Energy,Inc ML20133D8771996-12-23023 December 1996 Rev 2 to TMI-1 Evaluation of Thermo-Lag Fire Barriers ML20137F1301996-08-27027 August 1996 Rev 0 to Auxiliary Bldg Sump Sludge Prevention (Regulatory Required) ML20117H6621996-07-20020 July 1996 Rev 1 to TR 094 TMI-1 Evaluation of Thermo-Lag Fire Barriers ML20129G9291996-06-17017 June 1996 TMI-1 Reload Design & Setpoint Methodology ML20148F0831996-04-0202 April 1996 Rev 0 to EDG 1B Air Start 2 Reservoir Tank ML20148F0611996-04-0202 April 1996 Rev 0 to SQ-TI-EG-T-0001B-1, EDG 1B Air Start 1 Reservior ML20098B1291995-09-19019 September 1995 Rev 1 to Pages 3 & 30 of TMI-1 USI A-46 Seismic Evaluation Rept ML20100L6581995-05-25025 May 1995 Div 1/2 Mod Design Description for New TMI-1 Radwaste Demineralizer Sys Three Mile Island Unit 1,Nuclear Generating Station, Rev 2 ML20087J5281995-05-11011 May 1995 Nonproprietary Page 2 of TMI Unit 1 USI A-46 Seismic Evaluation Rept ML20082G4191995-03-22022 March 1995 Rev 0 to Topical Rept 093, TMI-1 Reactor Bldg Twenty Yr Tendon Surveillance (Insp Period 6) ML20082Q8051995-03-10010 March 1995 TMI-1 Core Thermal-Hydraulic Methodology Using VIPRE-01 Computer Code ML20082G4441995-02-22022 February 1995 Vols I & II 20th Yr Physical Surveillance of TMI-1 Containment Bldg ML20100L6321994-08-0303 August 1994 Shipment of Miscellaneous Waste Evaporator Concentrates ML20059M2181993-11-30030 November 1993 Amend 19 to Pdms Sar ML20148F0931993-10-28028 October 1993 Rev 0 to Air Accumulator for FW-V-16A ML20148F1011993-10-28028 October 1993 Rev 0 to Air Accumulator for FW-V-16B ML20059F0471993-08-31031 August 1993 Amend 18 to Post-Defueling Monitored Storage (Pdms) Sar. W/Rev 2 to List of Pdms Requirements & Commitments ML20056E5921993-07-31031 July 1993 Conservative Design In-Structure Response Spectra for Resolution of USI A-46 for Tmi,Unit 1 ML20059D7351993-02-0707 February 1993 Review of Offsite Response to Site Area Emergency Incident at Three Mile Island Nuclear Station ML20126D2831992-12-18018 December 1992 Criticality SAR for TMI-2 Reactor Vessel ML20114B9631992-08-0808 August 1992 Rev 3 to Criticality Safety Evaluation of TMI Fuel Storage Facilities W/Fuel of 5% Enrichment ML20058F6561992-07-31031 July 1992 Companion Sample Exams ML20058F6481992-01-31031 January 1992 Metallographic & Hardness Exams of TMI-2 Lower Pressure Vessel Head Samples ML20066K3591991-01-31031 January 1991 Rev 0 to Rept on 1990 Eddy Current Exams of TMI-1 OTSG Tubing ML20216K1251990-10-31031 October 1990 Amend 9 to Post-Defueling Monitored Storage Sar ML20217A4251990-09-11011 September 1990 Rev 3 to Licensing Rept for Spent Fuel Pool Mod of Pool a: TMI Unit I ML20058M7251990-08-0101 August 1990 Rev 2 to Div Technical Evaluation Rept for Processed Water Disposal Sys ML20056A0091990-07-26026 July 1990 TMI-1 Trust Agreements ML20043A2341990-05-0202 May 1990 Rev 0 to TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5). ML20055C9461990-03-31031 March 1990 Final Rept, TMI - Unit 2 Safety Advisory Board, for Mar 1981 - Dec 1989 ML20247R6371989-09-12012 September 1989 Submerged Demineralizer Sys ML20246H9401989-08-25025 August 1989 Corrected Pages 5-10 Through 5-18 & 5-26 to Rev 1 to Defueling Completion Rept,Second Submittal ML20246E1021989-08-18018 August 1989 Portion of Rev 1 to, Defueling Completion Rept ML20246G1161989-08-15015 August 1989 Rev 0 to SER for Removal of Metallurgical Samples from TMI-2 Reactor Vessel, Safety Analysis ML20247J2251989-07-31031 July 1989 Rev 7 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) ML20246E3481989-07-0505 July 1989 Rev 0 to TMI-2 Defueling Completion Rept ML20245K0151989-06-30030 June 1989 Amend 4 to Post-Defueling Monitored Storage Sar ML20246P8081989-05-31031 May 1989 Rev 12 to Defueling Water Cleanup Sys ML20244E3241989-04-30030 April 1989 Rev 7 to Technical Evaluation Rept 15737-2-G03-107, Waste Handling & Packaging Facility ML20235G5761989-02-0101 February 1989 Rev 0 to Criticality Safety Evaluation for Increasing TMI-2 Safe Fuel Mass Limit ML20155G5581988-10-10010 October 1988 Rev 0 to Technical Evaluation Rept for Processed Water Disposal Sys ML20154F6941988-09-0909 September 1988 Rev 0 to SER for Completion of Upper Core Support Assembly Defueling 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
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NUCLEAR SL ETY AND COMPLIANCE COMMITTEE REPORT NO. 2 to the GPU NUCLEAR BOARD OF DIRECTORS N April 15, 1985 APPROVED: '?
(' < .k &f R. V. Laney '
L. L. humphreys(/ V E I4 K. F. Witzig g ,
.g 8504300179 850424 PDR ADOCK 05000289 P PDR
I. SlM4ARY During the period of this repart, tne Nuclear Safety and Cbn-pliance Cbamittee met montnly with its Staff, twice witn Quirman John O' leary ard President Pnil Clark, aM once with the GPt3 03rporate '
Board. 'Ibe Qxmittee visited the Oyster Creek Station twi and D1I-l once. 'Ihe meetings with Mr. O' leary aM Mr. Clark were for the purpose of reporting observations made by the dSOC Staff in tne course of its evaluations which might be beneficial to management to improve operations but had no safety or c:xpliance significance.
'Ibe Staff's evaluations were concerned with a range of station activities that could affect the safe operation of T41-1 and Oyster Creek. 'Iheir purpose was to determine whether each activity is being performed safely ard in cmpliance with governing requirements and sourd operating practices. 'Ihe Staff developed its evaluations through direct observations at operating stations, interviews with various managers and supervisors, and review of relevant written policies, procedures, and reports.
At T4I-1, the Staff wrducted evaluations incitding operations, preventive and corrective maintenance, chemistry, records management, mcmitment tracking, radiological controls, special processes control, design change processirg, accreditation of training, procurement ard control of repair parts, and several specific events.
At Oyster Creek, the Staff conducted evaluations incitding training facilities ard prcgram, preventive maintenance ard surveil-lance, chemistry, radiological controls, control rocan audits, non-mntrol rocm shift operations, instructor training, mntrol of special processes, control of regulatory ccramitments, normal ard emergency operating procedures, procurement and control of parts, records management, and several specific events.
In general, tne Staff found safety attitudes ard practices to be satisfactory. Station operating personnel, supervisors, ard managers exhibit professionalism ard competence in the implementation of policies. Staff evaluation of two scrams which occurred durire Oyster Creek startup in late 1984 revealed a need for improved adherence to procedures and strengthened post-repair maintenance practices. NSCC notes that snagement's responses to these events were prcrapt ad appropriate.
Ma:u 15, 1984, (Clark, 4/gement's response to the NSCC's report of October 1/85) is roted by the NS NSCC enmurages the GPLI4 management to redum response time.
Significant observations are reported in the followire sections on 711-1 and Oyster Creek.
II. IMI-l OBSERVATICLE
.' Oparations - (bntrol roaa activities are conducted in a professiomi manner witn an appropriate degree of formality.
Itintenan - Staff exhibits a professional attitude towards nuclear safety ard cxxpliance. Mministrative procedures are adegaate.
Gemistry - Department has staff, pro dures, and equipment to ensure adequate control. Qantinued management attention to calculational z:ethods for E oar and primary-to-secondarf leak rate is in order. The natural sulfate Mckground levels in cxandensate storage should continue to be examined.
Preventive Maintenance and Surveillance - Established programs are found satisfactory.
Fagulatorf Cbtrtitment Tracking - Tracking System in use is appropriate.
The percentage of past due items, however, exceeds corprate goals.
Radiological Cbntrols - Program is comprenensive and meets or exceeds all regulatory requirements for an operating plant. Improved com:aanications to personnel outside those in PNMIX4 is encouraged in the area of the Radiological Awareness Report system.
Soecial Processes Qantrol - 03ntrol of special processes is adequately administered. Efforts to c:xaplete the Cbrporate Welding Manual cn schedule are important.
Pro ssing of Design Gange Packages - This review, while nat yet ccraplete, shows adequate design configuration control. The area of welding procedures for certain materials is being further evaluated due to some inadequate welding results.
Accreditation of Training - NSCC notes that IMO accreditation was granted for five important operator, shift technical advisor, and radiological technician training programs.
Cbntrol Roczn Monitoring - IM extent of control rocIn monitoring sub-stantially exceeds regulatorf requirements; however, no adverse effects due to this monitoring on control rocra operations were observed.
Fbliowing startup, this should be ::enitored to assure there is na distraction of operators frcxn operatin3 functicns.
, III. OYSTER CRZEK OBSERVATICMS (bre Soray Injection, Oct. 29, 1964 - Difficulty in following an extensive cne-time temporary procedure change was the rmt cause of this event. Management attention to irgrove in this area is apparent.
Reactor Scrams, Oct. 31 aM Dec. 3,1984 'Ibe NSCC believes that these scrams were bath related to Oyster Creek's long maintenance outage aM the resulting lack of operating opportunity. In botn cases, operator and plant responses to the scrams were proper aM effective. Root causes have been determined and appropriate remedial steps taken.
Preventive Maintenan aM Surveillance 'Ihere is a need to strengthen the priority system to assure that important-to-safety equipnent is regularly assigned higher priority than other equipaent.
Drywell Ventilation Valve Modifications - A special NSCC investigation of modifications performed on four main drywell ventilation inlet and outlet valves found that the modifistion decision was pntlent and tnat it was effectively performed.
Q1emistry - Department has adequate tecnnical and administrative proce-dures to ensure safe operations of chemistry-related systems. Upgrade of laboratorf facilities, now in progress, extend the ability to detect chlorides and sulphates at very low concentraticns.
Cantrol Room Aalits - (batrol Room auditing activities are well planned and scheduled. Auditing reports reflect cxzpliance with check lists and QA plans.
Instructor Training and Qualification - Current instructors are quali-fied in acm rdan with appropriate regulations. 'Ihere is a potential snortage of Senior Reactor Operator li nsed instructors. Until addi-tional instructors are qualified, any significant increase in projected training schedules would be un rtain.
Remrds Management 'Ibe records management system is in order.
. Cbrrective Maintenan - Atninistrative controls are adequate.
Control of Smcial Processes (welding, brazing, heat treating, solder-ing, cutting, and burning) 'Ihe program in place is effective and meets the requirements of the OA plan and the intent of 10CER50 Appendix B.
Procurement and Cbntrol of Parts - The processes in use are acceptable.
The mnaept of shelf life vs assuran of materials being acceptable
. prior to use bears examination.
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Normal and Emrgency Operating Premdures - Megtate written guidance is providea to the operators for safe opration o2 plant eystems and
- components. 'Ihe mechanism for keeping operators informed of new or changed pro dures appears to be satisfactory.
Radiological Cbntrols - Mequate radiological controls exist. Improve-ments in following procedures and timely response to awareness ard deficiency reports can be made.
Ibn-Cantrol Foom Shift Operations 'Ihese operations were found to be in compliance. Trainee progress throtx3h the operator requalification program suggests the need for attention.
Regulatorf Cbctnitments - Ib safety or carapliance findings were roted.
'Ihe numoer of overdue items are being vicprously pursued to bring them in line with corporate goals.
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