ML20196G840

Monthly Operating Rept for June 1997 for TMI-1

ML20196G840
Person / Time
Site:	Three Mile Island
Issue date:	06/30/1997
From:	Heysek W, Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2280, GL-97-02, GL-97-2, NUDOCS 9707230138
Download: ML20196G840 (3)

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GPU Nuclear,Inc.

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Route 441 South NUCLEAR Post ofsce ac< 480 Middletown, PA 17057-0480 Tel 717 944-7621 6710-97-2280 July 15, 1997 U. S. Nuclear Regulatory Commission Attn: Document Control Desk ~

Washington, D.C. 20555 Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for June 1997 Enclosed are two copies of the June 1997 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1. The content and format ofinformation submitted in this report is in accordance with the guidance provided by Generic Letter 97-02.

Sincerely, htJL L

J. h. Langenbach Vice President and Direc(t r, TMl WGH cc: Administrator, Region I b

TMI Senior Resident Inspector 97001 1

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.i 9707230138 970630 PDR ADOCK 05000289 R

PDR L-.

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x APPENDIX A OPERATINO DATA REPORT DOCKET NO 50 289 DATE July 15,1997 COMPLETED BY W. HEYSEK TIEEPHONE (717)948-8191 REPORTING PERIOD:. JUNE 1997 YEAR TO MONTH DATE CUMULATIVE 1.

~ DESIGN ELECTRICAL RATING (MWe NET).

.819.0 The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.

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MAXIMUM DEPENDABLE CAPACITY (MWeNET).

786.0 The gross electrical output as measured at the output terminals of the turbine generator during the most restrictive seasonal conditions minus the normal station senice loads.

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NUMBER OF HOURS REACTOR WAS CRITICAL.

543.3 4166.3 122,493.4 The total number of hours during the gross hours of the reporting period that the reactor was critical.

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HOURS GENERATOR ON LINE.

538.2 4161.2 121,326.5

. (Service llours) ne total number of hours during the gross hours of the reporting period that the unit operated with the breakers closed to the station bus. The sum of the hours that the generator was on line plus the total outage hours in the reporting period..

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UNIT RESERVE SHUTDOWN HOURS.

0.0 0.0 0.0 1

ne total number of hours during the gross hours of the

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reporting period that the unit was removed from service for economic or similar reasons but was available for operation.

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NET ELECTRICAL ENERGY (MWH).

417,620.0 3,382,116.0 94,525,780.1

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The gross electrical output of the unit measured at the output j

terminals of the turbine generator minus the normal station t

service loads during the gross hours of the reporting period..

. 1 expressed in magawatt hours. Negative quantities should not l

M used.

• Design values have no " Year to Date" or " Cumulative" significance.

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-6 APPENDIX B UNIT SHUTDOWNS e

DOCKET NO. 50-289 DATE July 15,1997 COMPLETED BY W. HEYSEK TELEPHONE (717)9480 M REPORTING PERIOD: JUNE 1997 weemd or cau acormw D

pn,,en,1 one Type' ouratwn Remon' (Him)

Reactort 97-01 06/21/97 F

205.8 A

3 On 6:21/97 at 1214 hours0.0141 days <br />0.337 hours <br />0.00201 weeks <br />4.61927e-4 months <br />, the plant tripped on a Loss Of OtTsite Power (LOOP). It had been operating at 100*4 power. The plant trip was caused by the catastrophic failure of generator breaker GB-1-02 in the plant 230KV switch-yard. A fault in the "B" phase of the breaker caused severe overheating and ejection of the bushing and conductor from the breaker. He fault was detected on the #4 bus (230KV) which resulted in the opening of the parallel breaker which sufTered a re-strike and caused a fault on the alternate #8 bus. The two faults resulted in breaker action which isolated power to the station and resulted in the LOOP. He LOOP resulted in immediate reactor and turbine trips. Both emergency diesel generators started and loaded on to their respective safeguards buses as designed. Without balance of plant power, the condensate, feed, circulating water and main condenser vacuum pumps were not operable. De once through steam generators were fed through the Emergency Feedwater System via two electric pumps powered by the engineering safeguards busses and a steam driven g

punp. Heat was removed via the steam generator atmospheric dump valves. Loss of station power also deenergized the reactor coolant pumps which fo. red the plant into a natural circulation mode. Natural circulation flow was achieved within 19 minutes of the trip. Offsite power was restored within 90 minutes. Systems were restored to enable cooling via the main cond mr and subsequent restart of the reactor coolant pumps. The failed breakers were replaced with new ABB model 242 PMG 3000 amp breakers. He plant was back on line at 0202 on June 29,1997.

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F Fewed Reasa Method 5 Sctuduled A-Eqimpment FadureIExplums I-Mmmal B-Mamannce or Test 2-Munual Scram C.Refuelmg FAuhinanc scram D-Regulatory Resmenon 40ther (Explam)

Eoperstar Trammg & Lacensmg Exammanon F.Adneustraeve c.cm,n.i nrmtxpin.)

Hothes (Explam)

SUMMARY

The plant entered the month operating at 100% power and remained at that power level until the plant trip at 1214 on June 21 described above. The plant returned to power operation at 0202 on June 29,1997. The plant is scheduled to shutdown on September 5,1997 for refueling.

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