ML20072T182

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Monthly Operating Rept for Mar 1991 for TMI-1
ML20072T182
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 03/31/1991
From: Broughton T, Heysek W
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2038, NUDOCS 9104180001
Download: ML20072T182 (6)


Text

OPU Nuclear Corporation Nuclear

,o " n m a 4

Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX B4 2366 Writer's Direct Dial Number; (717) 940-8005 April 14, 1991 C311-91-2038 4

U. S. Nuclear Regulatory Commiselon Attna Document Control Desk Washington, D.C.

20555 centlement Subject Three Mile Island Nuclear Station, Unit I (TMI-1)

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

Sincerely, M

T. G.

Brou hton Vice President & Director, THI-1 WGH Attachments cci Administrator, Region I THI Senior Resident Inspector 9104180001 91o333 PDR ADOCK 05000289 R

PLR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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OPERATIONS

SUMMARY

MAkCH 1991 The unit entered the month operating at -92% power producing ~000 MWe gross electrical generation.

The A and c Reactor coolant Pump Seal Leakoff flows continued to remain within the vendor established limite.

On March 1, 1991 the unit generated electricity for greater than 335 days exceeding the previous record for continuous electrical generation.

The twelfth anniversary of tha TMI Unit 2 accident on March 28, was observed by three protestors at the site's North Gate.

The protestors left the setne upon arrival of the State Police.

The unit completed the month operating at ~93% power producing

-B10 MWo gross electrical generation.

Power production continues to be limited by high OTSO level on the "B" eide.

MAJOR SAFETX MMTIQ_ MAINTENANCE The Nuclear Service River Wator Strainer NR-S-1B was removed from service in March to repair oil leaks in the strainer drive unit.

The drive unit and motor were removed from the strainer, disassembled and inspected.

The motor pinion gear was found cracked at the setscrew hole and the motor shaft was damaged. New gaskets, oil seal, an oil sightglass with a vented cap and motor l

were used during he reassembly. The cracked pinion gear wan evaluated by l

Plant Engineering and found acceptable for reinstallation until a apare can be procured.

The strainer drive unit was reinstalled on the otrainer, filled with oil and placed in an " Emergency Use only" status until a new motor pinion gear 10 obtained and installed.

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OPERATING DATA REPORT DOCKET NO.

50-209 DATE April 14, 1991 COMPLFTED BY

_W. G. Hryuk_

TELEPHONE (7171 94n.n191 OPERATING STATUS I NOTES 1

1. UNIT NAMEt THREE MILE ISLAND UNIT I I I
2. REPORTING PERIOD:

MARCH 1991. I I

3. LICENSED THERMAL POWER (MWT):

2560. I i

4 NAMEPLATE RATING (GROSS MWE):

971. I I

5. DESIGN ELECTRICAL RATING (NET MWE):

019. I I

O. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

056. 1 I

7. MAXIMUM DEPENDABLE CAPACITY (NET MUC):

G00. I I

I I

C. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

O. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATC CUMMULATIVE

!!. HOURS IN REPORTING PERIOD 744.

2160.

145321.

12. NUMDER OF HOURS REACTOR WAS CRITICAL 744.0 2160.0 71324.2
13. REACTOR RESERVE SHUTDOWN HOURS O.0 0.0 2245.6
14. HOURS GENERATOR ON-LINE 744.0 2160.0 70279.7
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
13. GROSS THERMAL ENERGY GENERATED (MWH) 1764524.

5135170.

17160$951.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 597740.

1747458.

57708362.

10. NET ELECTRICAL ENERGY GENERATED (MWH) 562420.

1644597.

54134017.

10. UNIT SERVICE FACTOR 100.0 100.0 40.4
20. UNIT AVAILABILITY FACTOR 100.0 100.0 40.4
21. UNIT CAPACITY FACTOR (USING MDC NET) 93.6 94.2 47.4
22. UNIT CAPACITY FACTOR (USING DER NET) 92.3 93.0 45.5
23. UNIT FORCED OUTAGE RATE O.0 0.0 46.3
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
25. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-209 UNIT THI-!

DATE April 14. 1991 COMPLETED BY u n Hnyut TELEPHONE (7171 948 8191 NONTH:

MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

( r1WE-NET )

1 758.

I7

'761.

2-748.

10 761.

3 747.

19 761.

4 750.

20 764.

5 754.

21 765.

6 749.

22 7G4.

7, 746.

23 764.

B 750.

24 760.

9 753.

25 761.

10 746.

26 762.

747.

27 759.

12 740.-

28 750.13-747.

29 759.

14 762.

30 765.

15 761.

31 759.

16 762.

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REPUELING INFORMATION REOUEST Three Mile Island Nuclear Station, Unit 1 1.

Name of Facility:

october 4, 1991 (9R)

Scheduled date for next refueling shutdowns 2.

Scheduled date for restart following current refueling:

NA 3.

Will refueling or resumption of operation thereafter require a technical 4.

No.

specification change or other license Amendment?

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 No.

core reload (Ref. 10 CFR Section 50.59)7 6/1/91 If no such review has taken place, when le it scheduled?

for submitting proposed licensing action and supporta Scheduled date(s) ing information None planned.

Important licensing considerations associated with refueling, e.g. now or different fuel design or supplier, unreviewed design or performance 6.

analysis methods, significant changes in fuel design, new operating procedures GPU Nuclear plans to install four Nestinghouse Lead Test Assem-blies during the reload of the THI-1 core for cycle 9 operation.

Westinghouse fuel technology will be utilised to the extent possible.

The number of fuel aseemblies (a) in the core, and (b) in the spent f uel 7.

storage pools (a) 177 (b) 441 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or le 8.

planned, in number of fuel assemblies:

Planning to increase The present licensed capacity is 752.

licensed capacity through fuel pool raracking is in progress.

The projected date of the last refueling that can be discharged to the 9.

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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