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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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REPORT OF THE THIRD PARTY REVIEW OF THREE MILE ISLAND, UNIT 1, STEAM GENERATOR REPAIR SUPPLEMENT 2
' y To R. F. Wilson - Vice President, Technical Functions l - GPU Nuclear, t Prepared by
. THIRD PARTY-' REVIEW GROUP:
Stephen D.-Brown Stanley A. Holland Arturs Kalnins William H.' Layman David J. Morgan Richard W.-Weeks Edwin J. Wagner - Chairman I
i Submitted for the Review Group By:
401090315 B40103 . Wagn6#
DR ADOCK 05000
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Date: ' 3's 3 / 8 I
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PURPOSE This report is Supplement 2 of the report of the Third Party Review of the TMI-l steam generator repair dated February 18, 1983. It evaluates a revision to the Safety Evaluation Repor;t (SER) mado cince the Review Group issuc,d.its conclusions in-Sup-plement 1 of May 16, 1983.
BACKGROUND The establishment and operation of-the Third Party Review Group of the TMI-l steam generator repair was previously dis-cussed in the Review Group's Report of-February 18, 1983. The report contained a conclusion concerning the adequacy of the steam generator repairs for safe operation of the TMI plant and findings, comments, and recommendations about the steam genera-tor repair and return of the plant to operation.
In Supplement 1, of May 16, 1983, the Review Group evalu-ated the GPU Nuclear responses to the Review Group's Report and concluded that
"...upon satisfactory completion of the entire program as defined in the safety evaluations and as augmented by GPU Nuclear comments during and subse-quent to the April 12 and 13 neeting, the TMI-l -
plant can be operated safely with the repaired steam generators." .
GPU Nuclear subsequently revised their SER and issued " Assess-ment of TMI-l Plant Safety for Return to Service After Steam Gen-erator Repair, Topical Report 008, Revision 3, August 19, 1983."
The Review Group was requested by GPU Nuclear letters of August 22 and September 9, 1983, to review the revised SER. The GPU Nuclear letters are attached as Appendix A and B to provide explicit identity to those documents supplied for review.
- Revision 3 of the SER and related documents were distributed to the specialist members of the Review Group who_had~ interest in design analysis, which was the principal content of the revision.
The reviewers were Mr. Layman, Mr. Kalnins, and Mr. Wagner. They performed the review and discussed the conclusion by telephone. .
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The conclusion was provided to Mr. Wetmore, of GPU Nuclear, by.the Chairman on October 6, 1983. This supplement 2 reports the Review Group's conclusion.
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CONCLUSION
'The1 Review Group reiterates.the conclusion of our Supplement-1 :as : quoted; above. - Revision 3-of the SER included actions to
. resolve prior Review Group-comments as GPU Nuclear ~ indicated
,p would be.taken. - No new or opon safety! questions were found in
,']our review of3the revisions of the SER.
COMMENTS
, [ ' The: Review Group was specifically interested in the revised 77y0 actions'taken by GPU-Nuclear.on topics upon which the Review n : Group commented-inLSupplement.l. Those topics follow and are C.,..<> -
.. referred:to the same numbered section of Supplement 1.
,+y j{7,. :E. Stiress ' Analysis of Steam Generators,
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gp: The' Review Group:had-commented:
"For this' reason, the-Review' Group recom-i .a mended that a detailed ctress analysis of the transition zone be made including the loading of- the main steam line break.
+- Subsequent to-the Review Group meeting, e~- s~; 'GPU Nuclear l advised that they-had completed the stress analysis of the' transition zone, and the' revising the'-stress report to include
+
this. analysis and that~the analysis shows an o s , acceptable.: stress condition. This resolves
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the' Review' Group's comment."
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-[? The. Review Group;found Revision 3 of the SER to reflect
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- the revised stress analysis of the transition and that the
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'P.f:' Steam. Generator-Leak Tightness After Repair p
The Review Group had commented:
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..~Because of these uncertainties in the
. analyses, the' Review Group questioned whether
- the results'of the GPU Nuclear analysis of~
leak before break had sufficient margin for 4
the-limiting ~ case ofja main steam line break.
g . Subsequent-to the meeting GPU Nuclear has
" ' pursued.thiscissue and advised they have come A to the following conclusions:
-o '- The GPU Naclear study'on crack preparation
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- their interpretation of the draft analy-L / @r' ' .a y sis done by others' suggests that cracks will
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not grow or not grow rapidly as a result of flow induced vibration. Although growth rate is a function of the assumed threshold stress intensity, even the extreme case of no thres-hold revealed long time periods for crack growth to a critical size and therefore ample
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time for operator action to shut down the re-actor prior to a tube failure either at power or during shutdown.
- The tube loads associated with the steam main line break case were calculated using a gener-ic analysis for B&W plants. The assumptions
- used in this analysis are very conservative with respect to the particular plant para-meters for TMI-l and results in calculated tube loads substantially greater than would
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actually. occur. When more-realistic tube loads are taken into account, the critical crack size is estimated to be significantly larger and the corresponding leak rate is in-creased by approximately a factor of two.
Thus GPU Nuclear concludes that because sig-
- nificant margin exists in the tube loading used-to determine critical crack size, no further conservatisms need be added in desig-nating administrative limits which take credit for leak before break...
In addition, in response to Review Group e suggestions, GPU Nuclear will record the conden-ser offgas activity data during cooldown and evaluate the feasibility of using this data for determining primary-to secondary leak rates dur-ing conditions of higher tube-to-shell dolta T.
GPU Nuclear also plans to use secondary-to-primary bubble testing tube as one technique for locating leaking tubes whenever the plant is shut down in response to an increase to a leak rate 0.1 gpm or more. The high sensitivity of this measurement technique provides additional assurance that flaws that could become unstable before the next eddy current inspection will be detected."
The Review Group found Revision 3 of the SER contains the following items which respond satisfactorily to our pre-vious comments:
a) The leak befcre break critical crack analysis was per-formed for the TMI-1 specific main steam line break in addition to the generic analysis. The leak before break analysis was also further supported by improved analysis of leakage rates through cracks.
l j
. r b) Monitoring primary-to-secondary leakage rate indications during operational cooldowns was included.
c) Secondary-to-primary bubble. testing for tube leak detec-tion was included whenever the plant is shutdown in response to an increase in leak rate of 6 gph (0.1 gpm) or more.
APPENDIX 1 - GPU Nuclear letter dated August 22, 1983 to Mr. Edward Wagner from Mr. J.S. Wetmore, Manager, PWR Licens-ing.
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-APPENDIX 2 - GPU Nuclear letter dated September 9, 1983 to I Mr. Edward Wagner from Mr. J.S. Wetmore, Manager, PWR Licensing.
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APPENDIX 1 GPU Nuclear Corporation UCIMr 100 lnterpace Parkway Parsippany New Jersey 07054 201 263 6500 TELEX 136-482 Writer's Direct Dial Number:
August 22, 1983 REcy;ygg ,,7,0 Mr. IMward Wagner ~ -
Cincinnati Gas & Electric %
Zirmer Nuclear Power Station RR$1 Box 2023 QI MO2. dim 3 U.S. Ibute 52 Moscow, 01 45153 g -
Dear Ed:
Per our telephone conversation today, I am forwarding the below listed documents for review by the Third Party Review Group for 'IMI-l OPSG Repair:
- 1. An SER entitled " Assessment of 'IMI-l Plant Safety for Return to Service After Steam Generator Repair,"
- 2. TDR-417 Rev.1 entitled "'IMI-l OPSG Tutn Axial Ioads and Leakage Bbntoring."
- 3. 'IDR-417 Rev. O entitled "OrSG Leakage and Operating Limits," and
- 4. Report entitled "The Residual Crack Opening Displacements in Tubes and Pipes."
Item 1 consists of changes made to Topical Report 008 (changes indicated by marginal change bars) to reflect results of OrSG cold testing and updated assessment of tube axial loads and their effects on leakage rate monitoring. Items 2 through 4 provide additional information to support the changes reflected in Item 1.
We expect to have further data to support the validity of estimates of residual crack opening displacements in the near future. A final revision to 'Ibpical Report 008 will be completed at that time.
Per your request, I have forwarded copies of the enclosed to A. Kalnins an.3 W. Layman.
Sincerel
. S. Wetmore Manager PWR Licensing dis:0079f Enclosures GPU Nuclear Corporatior;is a subsidiary of the General Pubhc Utihties Corporation /
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. . . . APPENDIX 2 .
l GPU Nuclear Corporation piUGE nep 100 Interpace Parkway s
l w Parsippany. New Jersey 07054 j
201 263-6500 1 TELEX 136-482 Writer's Direct Dial Number:
E&L: 5066 September 9,1983 arrn RECEIVED NOTED E.J. WAGNER Mr. Edward Wagner Cincinnati Gas S Electric Zimmer Nuclear Power Station E\' To-R.R. #1 Box 2023 U.S. Route 52 Moscow, 011. 45153
Dear Ed:
Enclosed for Third Party Review Group review is Revision 3 to spical Report 008, " Assessment of TMI-1 Plant Safety for Return to Serv' ice After Steam Generator Repair."
To minimize unnecessary delays, I have also forwarded copies directly to A. Kalnins and W. Layman.
Very tr 1 urs, i
J S. Wetmore anager, PWR Licensing 1r Enclosure GPU Nuclear Corporation is a subs diary of the General Public Utilities Corporation