ML20070K760

Monthly Operating Rept for Feb 1991 for TMI-1

ML20070K760
Person / Time
Site:	Crane
Issue date:	02/28/1991
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2028, NUDOCS 9103190143
Download: ML20070K760 (6)

Text

.

e OPU Nuclear Corporation U Nuclear

so"ra:e8o 4

Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2380 Writer's Direct Dial Number; (717) 948-800$

March 13. 1991 c311-91-2028 U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, D.C.

20$$5 Gentlemen:

Subject:

Three Mile Island Nuclear Station, U,.c I (THI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for February 1991 Enclosed are two copies of the February, 1991 Monthly Operhting Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, hh A

T. G. Broughton Vice Frosident & Director, THI-1 WGH:

Attachments cci Administrator, Region I TMI Senior Resident Inspector l

91C)3hb 1 910228 PDR ADOCK 05000289 R

PDR 76D'/

GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation

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OPERATIONS SUKMARY FEBRUARY 1991 The unit entered the month operating at -934 power producing -810 MWe gross electrical generation.

Reactor Coolant pumps A and C #1 Seal Leakoff flows were trending upward but remained within vendor established limits. The unit continued to operate at maximum achievable power until February 23,19P1 when an EHC transient occurred which resulted in a turbine control valve closure during performanco of en Operations Surveillance.

The valves reopened within approximately eight seconds with RCS pressure reaching a maximum of 2336 pelg, 15 pai below the Reactor Protection System high pressure trip setpoint. The operations on-duty shif t response was excellent.

The unit completed the month operating at -924 power producing -800 MWe gross electrical generation.

Power production continues to be limited by high 0T00 level on the "B" side.

Company administered requalification examinations were conducted during the week of February 4, 1991.

The combined pass rate for the NRC and company requalification examinations was ~074 (45 of 52).

With one excrttion, all candidates have requalified, The remaining unqualified candidate is complet-ing an extended upgrade program.

MAJOR SAFETY RELATED MAINTENANCE There were no major safety related maintenance activities performed during the month of February.

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OPERATING DATA REPORT l

1 DOCKET NO.

50-289 4

DATE March 13, 1991 CDf1PLETED PY D 7 0 SOE

(

TELEPHONE YIY N D I I

1 1

]

OPERATING STATUS

~

i l NOTES i

1.

UNIT NAt1E THREC title ISLAND UNIT I 1 I

2.

REPORTING PERIOD:

FCORUARY,1991. 1 I

+

i

3. LICCtGED THERNAL POlJER (t1W1 ):

2560. 1 I

l 4.

NAf1CPLATC RATING (GROSS f1WC ):

G71. I i

]

5.

DESIGN ELECTR3 CAL RATING (NCT t1WE)t ei9. i i

G.

t1AXIt1Uf1 DEPENDADLC CAPACITY (GROSS f1WI):

856. i I

7.

t1AXIMuti DCPCNDADLE CAPACITY (NET MWE):

809. I I

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l 8.

IF CHANGES OCCUR IN ( I TEt15 3+ 7 ) SINCE LAST REPORT. GIVE REASONS:

=

9.

POWER LEVEL TO WHICH PESTRICTED, IF ANY tNET MWE)

- 10. RE ASONS FOR RESTRICTIONS, IF ANY

=

s 1

^

THIS MONTH YR-TO-DATE cut 1MULATIVE

11. HOURS IN REPORTING PCRIPL G72.

1416.

141577.

! 12. Nut 1BER OF HOUR 3 RCAC%r< WAS CRITICAL 672.0 1416.0 70580.2

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 2249.0

14. HOURS GENERATOR ON-LINC 672.0 1416.0 69535.7 l 15. Ut41T PESERUC SHUTDOWN HOURS 0.0 0.0 0.0 l 16. -GROSS THERMAL ENERGY GENERATED (NWH) 1592571.

33706S4.

169041426.

j.17 GROSS ELECTRICAL ENERGY GENERATED (MWH) 541935.

1149718.:

57110622.

18; NET ELECTRICAL ENERGY GENERATED (11WH) 509099.

1082177.-

53571597.

19. UNIT SERVICC FACTOR 100.0 100.0 48.1

20. UNIT AVAILABILITY - FACTOR.

100.0 100.0 40.1

21. UNIT CAPACITY F ACTOR.(USING MDC NET )

93.9 94.G

-47.2

22. UNIT CAPACITY F ACTOR - (USING DER NET )

92.6.

93.3 45.2 4

23. UNIT FORCED OUTAGE RATE

-0.0 0.' O 46.6 i

) 24. SHUTDOWNS SCHEDULED OVER NEXT G f10NTHS ' ( TYPE, DATE, AND DURATION OF EACH

~"

25. IF SHUT DOWN AT END OF. REPORT PERIOD,_ ESTIMATED.DATE OF STARTUPt I

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AVERAGE DAILY UNIT POiJER LEVEL i

4 9

DOCKET NO.

50-209 i

UNIT

'I t11 ~ l DeTE fjgqLL3A,l_9_9]

i COMPLETED BY _WuG.f henek_.

1ELEPHONE J717) 948-8131-d l

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NONTH:

FEBRUARY DAY HUERAGE DA]LY POWER LEVEL DAY AUCRAGE DAILY Pour.R Ll's i

( T1WE - NE T ) -

01WC-NET) 1 765.

17 759.

2 762.

- IB 759.

1 3

756.

- !9 757.

4 756.

20 752.

i 4

5 755.

21 754 i

6

756, 22 751.

7 757.

23 764.

O 750.

24 764 9

759.

25 761.

1 10 759.

2G 762.

11 760.

27 761.

12 761.

20 761.

I3 760.

29 N/A l

14 757.

30 N/A 15 756.

3I.

N/A 16 761.

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o UNIT SHUTDOWMS AND POWER REDUCTIONS

~

DOCKET No.

% -289 UNIT NAME TMI-1 REPORT Mormt february 1991 DATE 3/13/91 COMPLETED BY W. G. Heysek TFT EPHONE (737) 948-8191 mw_

m thod of Licensee Syst m :ceponent Cause & Corrective e

2 "7-Date Type Duration Feeson Shutting Event Code Code Action to i

(Mours)

Down Raport8 Freve M Beeurrence I

6 l

Reactor 5 6 i

g i

h NONE l

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t l

i L'

1 2

3 4

F Forced Reeson Method Exhibit G - Instructions for S Scheduled A-Equipment Failure (Explain) 1-Manuet preperation of Data Entry Ms 8-maintenance or Test 2-manust Scram for Lice see Evem Raport (LER)

C-Refueling 3-Ai.tTomatic Scram file (4UREG-0161) 4 D-Regulatory Restriction 4-Other (Emptein)

E-Operator Training & Licensing Examination 5 Exhibit i same source i

F-Actuinistrative l

G-Operationet Error (Explain) 6 Actuelty used exhibits F & II NUEEG C161

{

N-Other (Esplain) i 5

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l REFUL1,1NO INFORMATION REGEET 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown October 4, 1991 (9R) 3.

Scheduled date for restart following current refueling: NA i

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

No.

If answer is yes, in general, what will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)7 No.

If no such review has taken place, when le it scheduled? 6/1/91.

5.

Scheduled date(s) for submitting proposed licensing action and support-ing information:

None planned.

6.

Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysie methods, significant changes in fuel design, now operating procedures OPU Nuclear plans to lusta11 four Westinghouse Lead Test Assem-blies during the reload of the THI-1 core for cycle 9 operation.

Westinghouse fuel technology will be utill ed to the extent possible.

7.

The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 171 (b) 441 1

8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or le planned, in number of fuel assemblies:

The present licensed capacity is 752.

planning to increase licensed capacity through fuel pool reracking is in progress.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

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