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Category:NRC TECHNICAL REPORT
MONTHYEARML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20059J5351993-06-30030 June 1993 Review of 2.206 Petition Process:Background Discussion Paper ML20035F4141993-04-30030 April 1993 Unauthorized Forced Entry Into the Protected Area at Three Mile Island Unit 1 on February 7, 1993 ML19325C5301989-10-0606 October 1989 Evaluation Re Safety & Performance Improvement Program Programmatic Audit ML20246P9191989-03-31031 March 1989 The Status of Recommendations of the Presidents Commission on the Accident at Three Mile Island.A Ten-Year Review ML20235M5291989-01-11011 January 1989 TMI-2 Cleanup Program Status Update ML20148D0671988-03-17017 March 1988 Headquarters Daily Rept for 880317 ML20147E3211988-01-0606 January 1988 Rept of Interview W/Rg Lagrange to Discuss Gpu 830520 & s Re Environ Qualification equipment.Marked-up 850409 Statement from H Hukill Also Encl ML20133J5421985-02-14014 February 1985 Summary of Order Before Commission for Affirmation (SECY-84-475A) ML20088A7451984-03-31031 March 1984 Answers to Frequently Asked Questions About Cleanup Activities at Three Mile Island,Unit 2 ML20087P9481984-03-31031 March 1984 NRC Plan for Cleanup Operations at Three Mile Island Unit 2 ML20024C6951983-07-11011 July 1983 Portions of Chapter 1 to 10CFR50,Title 10, Emergency ML20024B9001982-05-10010 May 1982 Vol 2,Part 1 of TMI Rept to Commissioners & to Public ML20024B9191982-05-10010 May 1982 Tmi,Rept to Commissioners & to Public, Vol Ii,Part 1. Pp 109-111 Only ML20027C0931982-03-31031 March 1982 Recently Evaluated Preoperational Test Precursor of TMI-2 Accident, for Presentation at ANS 1982 Power Div Topical Meeting in Charleston,SC,820328-31 ML20054A5781982-03-16016 March 1982 NRC Plan for Cleanup Operations at Three Mile Island Unit 2 ML20023A5161982-03-11011 March 1982 Bevil Rept Input Re Ginna 820125 Steam Generator Tube Rupture Event.Nrc 16th Monthly Status Rept to Congress Re TMI-1 Restart Encl ML20054A6331982-02-28028 February 1982 NRC Plan for Cleanup Operations at Three Mile Island Unit 2: Revision 1 ML19352A8741981-05-29029 May 1981 Emergency Preparedness Evaluation for TMI-1 ML20003G7101981-04-30030 April 1981 TMI-1 Restart.Evaluation of Licensees Compliance with the Short and Long-Term Items of Section II of the NRC Order Dated August 9,1979.(Met Ed Et Al,Three Mile Island Nuclear Station,Unit 1,Docket No. 50-289) ML20003G7071981-03-31031 March 1981 Impact of the 1979 Accident at Three Mile Island Nuclear Station on Recreational Fishing in the Susquehanna River ML19350B7721981-03-31031 March 1981 TMI-1 Restart.Evaluation of Licensees Compliance W/Short & Long Term Items of Section II of NRC Order Dated August 9, 1979.(Met Ed Et Al,Three Mile Island Nuclear Station,Unit 1, Docket 50-289) ML20008F3211981-03-0505 March 1981 Evaluation of Radiation Protection Plan ML20148T0941981-01-31031 January 1981 Investigation Into Information Flow During the Accident at Three Mile Island ML19340E9031981-01-14014 January 1981 Rept on Saint Lucie 1 Natural Circulation Cooldown on 800611. Certificate of Svc Encl ML19347C6661980-12-31031 December 1980 Control Room Design Review Rept for TMI-1 ML19351F0731980-12-31031 December 1980 Emergency Preparedness Evaluation for TMI-1 ML20002D4031980-12-31031 December 1980 The Public Whole Body Counting Program Following the Three Mile Island Accident ML20148P6001980-12-24024 December 1980 Discusses Followup Study Re Degradation of Internal Appurtenances in LWR Piping During Normal Plant Operation & Potential Effects When Degraded Appurtenances Are Subj to Accident Loads.Recommends Review of Recurrent Problems ML19345D1411980-11-30030 November 1980 The Potential Impact of Licensee Default on the Cleanup of TMI-2 ML20008E0081980-09-30030 September 1980 Answers to Frequently Asked Questions About Cleanup Activities at TMI-2 ML19344A9881980-07-10010 July 1980 Status of NRC Activities & Plans as Related to Recommendations in Resolutions 207-211 by House of Representatives of Commonwealth of Pa ML19312E2781980-06-0202 June 1980 TMI-1 Potential Core Damage Accident Sequences & Preventive & Mitigative Measures ML19318B8541980-05-31031 May 1980 Environ Assessment of Radiological Effluents from Data Gathering & Maint Operation on TMI Unit 2 ML19331D4441980-05-31031 May 1980 Final Environ Assessment for Decontamination of TMI Unit 2 Reactor Bldg Atmosphere, Vol 1 of Final NRC Staff Report ML20155J7451980-04-28028 April 1980 Rept of Interview W/J Blessing as Recorded by Rk Christopher,Investigator,Us Nrc ML19323A6871980-04-25025 April 1980 Accident at TMI-2 & Ensuing Actions by Nrc ML20155J7781980-04-11011 April 1980 Rept of Interview W/Ms Coleman by IE & Ofc of Inspector & Auditor on 800410 ML19323A7231980-04-0505 April 1980 Tmi,Rept to Commissioners & to Public, Vol 2,Part 3. Final Version ML19323A7201980-04-0505 April 1980 Tmi,Rept to Commissioners & to Public, Vol 2,Part 1. Final Version ML19323A7221980-04-0505 April 1980 Tmi,Rept to Commissioners & to Public, Vol 2,Part 2. Final Version ML19323B5401980-04-0404 April 1980 Further Evaluation of Risk of Recriticality at TMI-2 ML19323A6441980-03-31031 March 1980 TMI Weekly Status Rept for 800322-28,providing Facility Status,Environ & Effluent Info,Major Activities,Future Evolutions & Public Affairs Info ML19308E1461980-03-0505 March 1980 NRC Action Plans Developed as Result of TMI-2 Accident, Draft 3 ML19322D8311980-02-13013 February 1980 Safety Evaluation & Environ Assessment Supporting Encl Tech Specs.Facility Will Remain in Safe & Stable Posture During Recovery Mode ML19345B9451980-02-0707 February 1980 Analysis of Feedwater Transient Sequences in B&W Nsss ML19257C1151980-01-24024 January 1980 Draft Tmi,Rept to Commissioners & to Public, Vol 2,Part 3 ML19257C1131980-01-24024 January 1980 Draft Tmi,Rept to Commissioners & to Public, Vol 2,Part 1 ML19257C1141980-01-24024 January 1980 Draft Tmi,Rept to Commissioners & to Public, Vol 2,Part 2 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1001999-10-14014 October 1999 Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20216F9231999-09-22022 September 1999 Safety Evaluation Supporting Amend 216 to License DPR-50 05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
- on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.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 ML20211E8731999-08-24024 August 1999 Safety Evaluation Supporting Amend 215 to License DPR-50 ML20211B1931999-08-19019 August 1999 Safety Evaluation Supporting Amend 214 to License DPR-50 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 05000289/LER-1999-009, :on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced1999-07-22022 July 1999
- on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced
ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 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 ML20212H9101999-06-21021 June 1999 Safety Evaluation Supporting Amend 212 to License DPR-50 05000289/LER-1999-007, :on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed1999-06-18018 June 1999
- on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed
ML20195J9401999-06-15015 June 1999 Safety Evaluation Supporting Amend 211 to License DPR-50 05000289/LER-1999-005, :on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With1999-06-14014 June 1999
- on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.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 05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open1999-05-0707 May 1999
- on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
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 ML20205Q6111999-04-15015 April 1999 Safety Evaluation Supporting Amend 210 to License DPR-50 ML20205Q5981999-04-13013 April 1999 Safety Evaluation Supporting Amend 209 to License DPR-50 ML20206P2841999-04-12012 April 1999 SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90 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 05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With1999-03-14014 March 1999
- on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.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 05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys1999-02-19019 February 1999
- on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
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 05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With1999-01-11011 January 1999
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 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 05000289/LER-1998-013, :on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance1998-10-15015 October 1998
- on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance
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 05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued1998-10-0909 October 1998
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With 05000289/LER-1998-011, :on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge1998-09-23023 September 1998
- on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge
1999-09-30
[Table view] |
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3/15/7 6 Extended outage to remove damaged Three Mile Island Unit 2 surveillance specimen holder tubes.
The PRC issued an operating license for TMI-2 Duraton,720 hours.
on February 8,1978. The license identrfied a 5/27/76 Reactor tnp due to operator error.
number of preoperatonal tests, startuo tests and Duraten,7 hours.
other items to be completed by Met Ed within spoo 11/ 5 / 7 6 Manual shutdown for scheduled repair of w
f As a w d a mechancal failure decay heat valve and pipe in nverwater in one of the reactor coolant pumps, the irutial test-system. Duraten 683 hours.
ng prp was pwformed with one pump out of savice for the penod March M through May 17 m t 977 Through December 37,1977 1978. The techncal specifications permitted three pumo operation, however, ard the inibal entcality The second refueling and maintenance outage was achieved on March 28,1978, approxrnately 2 took piace dunng 2 months bev-Esi March 18, montts sooner than if four pumps t.ed been used.
1977. Because the urut operated unctorrupted for 0 Frorn February 1978 to March 1979, TMI-2 ex-months, the urut availability factor increased to ponenced al least 20 reactor trips, approximately 80.9% and capacity factor increased to 76.2%.
one-tlurd of which ongmated in the conder: sate and Date Event feedwater system. Ir, additen, four trar,sents 2/g/77 Power reducten to repair turb.no test ed in the actm of the ECCS nigh pressure tubing. Duraten 7 hours.
injecten system. Table I-6 contains a chronology of 3/18/77 Refueling and mantenance Duraten, the TMi-2 operating history.
1,394 hours.
The major outage for TMI-2 was necessary in 9/16/7 7 Irutal outage was by manual shutdown order to replace all of the main steam safety valves.
to correct problems in the dommeralizer These valves were the first of a kind design and in order to reduce conductivity in the failed to reset after lifting. This outage lasted about 5 c.cE4.iy fluid systen. The outage 5 months, bogenmg in April 1978. The second was extended to repair reactor coolant longest outage resulted from rupture of the atmos-pump motor and generator ground. To-phenc dump valve bellows and lasted approximately tal outage,261 nours.
2 weeks dunng January 1979.
11/M/77 Reactor tnp due to falure of integrated control system.
Compensons to Other Plants Table W presents a cornpenson 2 ome January 7,1978 Through December Ji,1978 plants by number of bconsee Event Reports (LERs)
The tturd refueling and maintenance outage for flied with the PRC for the year of operation after the TMI-1 began March 18,1978, and lasted 2 months.
license was issued. The table provides some cuali-The year reflected a good operating hetory, com-tatrve correlations between TMI-2 and other B&W pared to the prevous year, and resulted in slight in-plants and other two unit sites using equipment suo-creases m the percentages of unit avalabeirty to plied by other pressunzod-water-reactor vendors.
85.1% and capacity to 79.1%.
h additen, a compenson of the LERs on PWRs nu-Date Event clear steam suppiers for 1975 through 1978 is pro-l l
3/8/78 Refueling. Duration,1,OS6 hours.
vided in Table I-7. The compensons, although not 9/22/78 Manual shutdown to repair seal fracture definstrve with respect to undertying causes. indicate on reactor coolant pump. Duraton,2M that the p.4.nirers for TMI-2 and other B&W hours.
plants is average for PWR vendors. The director of 1t/15/78 Power reducten to correct electncal E Regen i office consdered Met Ed's performance problems on turbme control system.
as average w.T.;we with other licensees in he re-Duraton, M hours.
gion 3 Dunng its year of operaten, TMI-2 had four events which resulted in actuation of the emwgency January f,1979 Thrcugh February 17,1979 core coolmg high pressure injecton system and the Full power operation was mamtamed until shut-injection of borated water into the pnmary coolant down for refueleg on February 17,1979. TMI-1 was system. The ACRS task force evaluatmg Ocensee on hot shutdown status at the time of the TMI-2 ac-Event Reports
- reported 40 inadvertent ECCS ac-tuatens in PWRs frc+n 1976 through 1978. Actua-cdont.
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y TABLE l.6. Chronology of TMI.2 operating esperience Date Event j
2/8/78 Operatmg License issued.
3/14/78 Began three-pump operations. Lost one pump due to mechanical failure.
f 3/28/78 initial criticality.
i 3/29/78 Reactor trip. Pressurizer rehof vaive open. ECCS actuation. Shutdown tzero power) dura.
tion. 57.8 hours.
I U1/78 Reactor tno cue to instrument fatture moscating loss of second pump m coolant loop Duration.182.9 hours.
4/18/78 Reactor trip due to noise soike. Duration. 7.8 hours.
4/19/78 Reactor trio due to foss of feedwater due to personate' error oe* forming mantenance on isedwater pumps. Duration. 7.9 hours.
4/20/78 Reactor trip due to spurious high fium spike. Duration. 6.0 tiours.
4/23/78 Reactor trip caused by soi.rious signal. Five mair. steamline safety valves fail to clore.
and the ECCS was actuated. Design error of the vatves necessifa'ed reosacement of all steamune safety valves. reouinng shutdown until Septemmer 17.1978 Metropolitan Ed:-
son removed orifice rods and installed retainers on burnacle poison rods during this outage 9/18/78 TMI.2 generated power for the first time.
9'/19/78 Manual reactor trip. During test procedure of shutdown outside controt room. feedwater vatve closed and reactor did not tnp when tureir's tnoped. Duration. 6 hours.
9/20/78 Reactor tno due to loss of one mam feedwater pump. Duration,9.2 hours.
9/21/78 Reactor trip due to controt prootems with feedwater pump Duration. 8 hours.
9/22/78 Manual reactor shutdown for scheduled testing of main steam safety valves. Duration. 92 hours.
10/5/78 Estended outage due to Conas connector proelems on steam generator. Duration.181 hours.
10/13/78 Hot standDy for 4 hours to repair turtine generator.
10/14/78 Two reactor tnps due to feedwater pump probtems. Duration.13.7 hours.
10/17/78 Reduced power for total of 7.7 hours due to proetems in the mam generator relay, which 10/20/78 prohibited synchronization with power gnd.
10/21/78 I
i 10/28/73 Manual reactor shutdown m order to repair turome. Duration 90.1 hours.
j 10/29/78 Durmg reactor shutdown a rachet tno of Group 5 controt rods occurred. After trip, three rods were stuck at th,e 5'. withdrawn positions.
11/3/73 Reactor trip due to lbss of feedwater. Personnel error resulted in loss of pJwer to con.
densate polishmg valve.
11/7/78 Reactor trip due to foss of ieedwater. Pressurizer level indicated below zero, and the ECCS was actuated. Feedwater system was found to be contammated with oil. Duration.
594.6 hours.
12/2/78 Reactor tnp due to foss of feedwater pump. Duration 1.7 hours.
110
g TABLE l 6. Chronology of TMI 2 operating esperience-Continued Event Cate 12/2((8 Reactor trip during recovery from foss of feedwater. Duration,4 8 hours.
Reactor trip due to personnel error resulting in excessive feedwater resulted in ECCS 12/2/78 actuation. Duration. 28.3 nours.
12/16/78 Reactor trip due to mechanical failure in feedwater pump. Duration 146 hours.
12/28/78 Manual reactor shutdown to repair a number of steam leaks.
Hot standDy for 3 hours to repair steam teak in tureine. Unit achieved 80*. power and 12/30/78 declared in commercial operation at 11:00 p m. Unit maintained 82* power af'er 6.30 a.m on Decemter 31,1978. i.ntil second heater drain pump could ce retumed to service 1/2/79 Tureine taken off line to repair hydraulic lean. Duration.11.5 hours.
1/5/79 Rod drops due to Otown fuse. Automatic power reduction and then power escalation.
Reactor manual shutdrwn to recair leaking pressunzer instrumentaticn esciation valves.
1/14/79 During startup. reactor (noped due to loss of power to pressurizer. Outage extended to 1/15/79 reoair atmoschenc.1 ump bellows and a nun. Der of pressurizer instrumentation valves.
Duration. 425 9 hours.
1/31/79 Un:t returned to service.
2/6/79 Feedwater pump tnos twice with automatic power runcack to 55*..
Reactor maintained at 13'. power cunng 13.2 hour outage to repair tureene leaks.
2/10/79 3/6/79 Turcine generator trip fottowed by reactor trip. Duratron.16.5 Pteurs.
3/7/79 Unit operated near 97*. power until foss of feedwater trro on March 28.1979.
~
tions reauired by depressunzacon and other tran-Aod Possfions-Rod Groups one through five were sients, wrnen were not riadvertent, were not ad-fully withdrawn, groups six and seven were 95%
dressed.
withdrawn, and group eight was 27% withdrawn.
A request to the PER for '1formabon anowing a s
compenson of the number of TMI-2's safety insec-Pressurizer-tion events to those of other operating plants re-229 h vealed that such informaton was not available and Spray 4 pray valve open that a two-man-month effort would be required to Heaters-Energized in manual control cetain such informaten. Consequent!y. no data Through one of the safety valves were provided, and the SIG was unable to make this p or RC-122) compenson. This lack of operatonal informaton is Header p190'F.
significant, demonstrating that a major ww.cf in l
NRC activities is the lack of a structured, systemanc The leakage noted above could have been and coordinated process for couecton, review, and through pressunzer relief valve. The temperature t
evaluation of operatonal data.s indication is on header from aR three valves.
l Phmary Cooient Systems-TMl-2 Plant Status on Maren 28,1979s Loop A ang h Pressure-2165 psig The piant status pnor to A00 a.m. on March 28.
Flow-68.484 MPF H (Minion Pounds 1979. was as fotows.
per Hour)
Temperature-Hot Leg--6067 Anwer Leve6-97.928% fut power (872 MWe).
Cold Leg-5587 111
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