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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
[Table view] |
Text
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THREE MILE ISLANt UNIT 1 SURVEILLANCE HOLDER TU. REPORT INTRODUCTION Metropolitan Edison has discovered during the current refueling outage at TMI-1, damage to the reactor vessel surveillance holder tubes. As a result of this da= age, TMI-l must be operated during Cycle 2 with the surveillance specimen .
capsules and holder tubes recoved. This report demonstrates the acceptability of these actions.
SURVEILLANCE CAPSULE HOLDER ARRANGE?S T The design 9f BAW-10006A.ll)the The surveillance surveillancecapsule holder capsules tube is described are attached in B&Wwithin to and secured Topical theReport holder tube by a spring-loaded push rod asse=bly as shown in Figure 2-8 of Reference
- 2. The plenum flange compresses the push' rod assembly spring as the plenum is lowered into the core suppcrt shield. The spring-loaded push rod assembly has fcur spacers mounted along its axisl length to provide lateral positioning of the push rod. The top one of these 3-piece spacers, is shown in Figure 2-10 of Reference 2. Both upper spacers are located in the portion of the holder tube which is within the shroud tube.
The third spacer is axially located in a portion of the holder tube with a thicker vall and within a journal bearing counted to the core support shield. The fourth spacer is approximately in the center of the ogee bend in the holder tube.
A female fitting on the lover end of the push rod mates with the top end fitting of the upper surveillance capsule in a manner similar to the between capsule coupling shown in figure 2-6 of Reference 2. The bottom end fitting of the lever surveillance capsule mates with a special fitting in the base of the holder tube which prevents capsule rotatien.
SURVEILLANCE TUBE INSPECTION During specimen capsule removal, two of the three holder tubes were found to be severed at the axial location of the second push rod spacer from the top, thus separating the top approxicately six feet of the holder tube. One of these two tubes was also severely worn at the axial locatien of the first push rod spacer and became separated at that location during capsule removal. The third holder tube was intact following capsule removal.
Remote video techniques were used to inspect for further evidence of wear on the internal surfaces of two of the holder tubes, (the intact tube and one severed tube).
In general, the results of these inspections showed evidence of wear at each of the axial locatiens of the push rod spacer, at the axial location of the holddown spring, and at the axial locations of the surveillance capsule rinEs-The year sites on the holder tube are attributed to contacc and relative motion between the push rod spacers, the holddown spring, and the surveillance capsules and the holder tube.
CORRECTIVE ACTION B&W has concluded that the most likely cause of the observed tube vear is flow-induced relative motion between the surveillance capsule train and the holder tube.
To prevent the possibility of loose parts occurring during C3 r .e 2, the curveillance capsules and holder tubes vill be removed Prior to Cycle 2 operation.
7a10300 :4 3
CORRECTIVE ACTION con't Engineering of the holder tube and push rod assembly design modifications and material procurement will be conpleted during Cycle 2 to allow installation of the revised design prior to the start of Cycle 3 Removal of the specimens from the reactor ,
vessel for one cycle vill not adversely affect the results of future testing of these specimens or the overall results of the surveillance program.
SAFETY EVALUATION The TMI-l Technical Specifications provide the operating pressure and temperature limitations applicable up to the end of two EFPY of operation. One specimen capsule was removed at the end of Cycle 1 and those specimens vill be tested during Cycle 2.
Cycle 1 has accumulated approximately 13 EFPY of actual exposure to the reactor vessel vall at 1/4 vall thickness (1/ht).
The neutron fluence at the center of the surveillance specimens is reported in Reference 1 to be approximately 17 times the maximum fluence at the reactor vessel vall. A more recent calculation using improved methods reported in Reference 2 for the Oconee class reactors indicates that the neutron flux (E > 1Mev) is 2.4 times greater at the specimen ;1otsticn than the reacter vessel 1/ht location. Thus, the capsules in TMI-3 have received the equivalent irradiation in excess of the first three cycles of operation.
Cycle 2 is planned for 296 EFPD (0.8 EFPY) and Cycles 3 and h are each planned for 270 EFPD (0.75 EFPY) of operation. A revision to the technical specification limits vill be requested prior to the beginnin6 of Cycle 3 and vill be based on the results of testing of the specimens from the surveillance capsule withdrawn at the end of Cycle 1. This revisioa vill be applicable up through the end of at least the first 5 EFPY* of operation and vill provide additional assurance that adequate fracture toughness properties are retained through the period of the next surveillance capsule withdrawal and testing.
A revised surveillance capsule withdrawal schedule based on the results of the specimen testing planned during Cycle 2 vill be submitted for NRC approval in accordance with Appendix H to 10 CFR 50.
- 5 EFPY Reactor Vessel Exposure CONCLUSION It is concluded that operation of TMI-l with the surveillance specimen capsules and thu surveillance specimen capsule holder tubes removed is acceptable during Cycle 2.
This change vill not result in:
- 1. An increased probability of occurrence of any accident previously analyzed, or
- 2. An increase in the consequences of any accident previously analyzed, or 3 An increased probability of malfunction of any equipment important to safety previcusly analyzed, or
- k. An increase in the consequences of the malfunction of any equipment important to safety previously analyzed, or 1488 084
5 The creation of the possibility of an accident of a different type than previously analyzed, or 6.
The creation of the possibility of a =alfunction of a different type than previously analyzed, or 7
A reduction in the margin of safety in the jasis of any technical specification.
REFTRE:'CES 1.
Reactor Vessel Material Surveillance Program, BAW-10006A, Revision 3, Babcock
& Wilcox, January 1975 2.
Reactor Vessel Material Surveillance Prceram - Comoliance with 10 CFR 50, Aprendix H, for Oconee Class Reactors, BAW-10100A, Babcock & Wilcox, February 1975 1488 085
