ML20082C006

Monthly Operating Rept for June 1991 for TMI-1

ML20082C006
Person / Time
Site:	Crane
Issue date:	06/30/1991
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2073, NUDOCS 9107170261
Download: ML20082C006 (6)

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GPU Nuclear Corporation a Nuclear

"4rs:r8o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8005 July 12, 1991 C311-91-2073 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 June 1991 Enclosed are two copies of the June, 1991 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, i

T. G.

Droug on Vice President and Director, TMI-l WGH Attachments cc Administrator, Region I THI Senior Resident Inspector 9h[/i^7851.1 910630 PDR ADOCK 03000289 g

PDR p

o g GPU Nuclear Corporation is a subsid

ary of General Pubhc Utihties Corporation

OPERATIONS

SUMMARY

JUNE 1991 TMI Unit 1 entered the month of June operating at ~92.5% power producing

~765 MWe gross electrical generacion.

RC-P-1A #1 Seal Leakoff was ~9.7 to 10 GPM and was authorized to increase to a maximum of 12 GPM.

The rate of increase of RC-P-1A/C #1 Seal Leakoff appears to be reduced following the installation of a finer filter in the seal injection system in May.

The longest continuous period of operation of 439 days for a B&W plant was exceeded by TMI-1 on June 13th. The unit completed the month operating at 92.5% power producing 760 MWe.

Power production continues to be limited by high downcomer levels in the "B"

OTSG.

MAJOR SAFETY RELATED MAINTENANCE During June, the following major Safety Related maintenance items were completed:

Nuclear Service River Water Strainer NR-S-1B Nuclear Service River Water Strainer NR-5-1B was removed from " Emergency Use only* status in June.

The strainer was placed in that status in March when a crack was discovered in the motor pinion gear and no replacement spare part was available. A replacement gear was installed upon receipt and post maintenance testing was completed after reassembly of the strainer unit.

The test results were satisfactory and NS-R-1B was returned to service.

Nuclear Service River Water Cooler NR-C-1,A Nuclear Service River Water Cooler NR-C-1A was removed from service for a maintenance inspection for Asiatic Clams and other tubesheet debris. Nothing of significance was found and the cooler was returned to service.

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OPERATING DATA REPORT DOCKET NO.

50-289 i

DATE

.7ulv 12, 1991 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191 i

-1. UFIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

2. REPORTING PERIOD:

JUNE 1991

3. LICENSED THERMAL POWER:

2568

4. NAMEPLATE RATING (GROSS MWe):

871

5. DESIGN ELECTRICAL RATING (NET MWe):

819

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

856

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

808 l

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

9. POWER' LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 720.0 4343.0 147504.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 720.0 4343.0 73507.2

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2245.6

14. HOURS GFNERATOR ON-LINE (HRS) 720.0 4343.0 72462.7

15. UNIT RESERVE-SHUTDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1113074 9733542 176203873

.17. GROSS ELECTRICAL ENERGY ~ GENERATED (MWH) 551294 3453947 59414851

18. NET ELECTRICAL ENERGY GENERATED.

(MWH) 518051 3249370 b5738790

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 49.1 20.' UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 49.1

21. UNIT CAPACITY FACTOR (USING MDC NET) 89.0 92.6 48.1

22. UNIT CAPACITY FACTOR (USING DER NET) 87.9 91.4 46.1

23. UNIT. FORCED OUTAGE RATE

(%)

0.0 0.0 45.5

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

Cycle 9 Refueling Outage, scheduled to begin 9/27/91. with a nominal 7 to l'0 week duration.

25.'IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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AVERAGE DAILY UNIT POWER LEVEL DOCKET No.

50-289 l

UNIT THI-1 q

DATE July 17, 1941 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH' JUNE DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWo-NET) 1 721 17 723 2

729 18 734 3

729 19 736 4

732 20 729 5

741 21 726 6

742 22 726 7

701 23 737 8

570 24 739 9

586 25 731 10 733 26 737 11 729 27 731 12 732 28 723 13 741 29 719

'14 739 30 719 15 729 31 NA 16 720 t

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UNIT SHUTDOWNS AND POWER REDUCTIO 43 DOCKET NO.

50-289

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i UNIT NAME TMI-1 REPORT MONTH June 1991 DATE July 12,1Q91 sXM(PLETED BY W. G. Heysek-TELEPHONE (717) 948-8191 l

Method of Licensee System Conponent Catre & Corrective I

2 No.

Date Type Duration Reason shutti Event Code Code Action to (Hours)

Down Report #

Prevent Recurrence 3

4 6 5 6 Reactor g

f 91- 06/07/91-F 52.3 A

4 Power reduction to 76% power due to repair of 01 06/09/91 j

Feedwater Heater 10% tube leak.

38 tubes were plugged.

91-06/25/91 F

2.3 A

4 Power reduction to BM po rer due to f ailure 02 of ICS module for Main 'curbine Header Pres-sure.

Module was replaced.

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4 F Forced Reason Method Exhibit G - Instructions for S Scheduled A-Equipment Failure (Earstain) 1-Manual preparation of Data Entry Sheets B-Maintenstwe or Test 2-Manual scram f or Licensee Event Report (LER)

C-Refuetitu 3-Automstic Scram File (NUREG-0161)

D-Regulatory Restriction 4-Other (Esplain)

E-Cperator Training & Licensing Examination 5 Exhibit 1 same source F-Adninistrative G-Operational Error (Explain) 6 Actuatty used exhibits F & 11 NUREG C161 H-Other (Explain) 5

4 Brign1RQ_INFORMATION REQUI;Et 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

September 27, 1991 (9R) 3.

Scheduled date for restart following current refueling NA 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, han 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 CFn section $0.59)?

No.

If no such review has taken place, when is it scheduled? 7/91.

5.

Scheduled date(s) for submitting proposed licensing action and support-ing informations j

None planned.

6.

Important licensing considerations associated with refueling, w.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant chinges in fuel design, new operating procedures OPU Nuclear plans to install four Westinghouse Lead Test Assen-biles during the reload of the THI-1 core for cycle 9 operation.

Westinghouse /uel technology will be utilised to the extent possible.

i 7.

The number of fuel assemblies (a) in the ccre, and (b) in the spent fuel storage pools (a) 177 (b) 441 8.

The present licensed spent fuel pool storage capacity and thw cito of any increase in licensed storago capacity that has been requested or is planned, in number of fuel assemblies:

The present licensed capacity is 752.

Planning to increase licensed capacity through fuel pool raracking is in progress.

9.

The projected i.

f the list refueling that can be discharged to the spent fuel poo)

'ng the present licensed capacity:

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

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