ML20195C880

Monthly Operating Rept for May 1988 for TMI-1

ML20195C880
Person / Time
Site:	Crane
Issue date:	05/31/1988
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
C311-88-2080, NUDOCS 8806220308
Download: ML20195C880 (6)

Text

_ _______

OPERATIONS

SUMMARY

MAY 1988 The unit entered May at 100% power.

The plant continued 100% power operation for the entire month.

]

MAJOR SAFETY RELATED MAINTENANCE l

During the month of May, i.4I Unit 1 performed the following major maintenance activities on safety-related equipment:

Liquid Waste Disposal-Neutralizer Tank WDL-T Repairs to WDL-T-8 were performed in May. A pin hole leak was identified in the bottom of the tank and the tank was drained and ultrasonic testing performed.

The tests showed no significant thinning or degradation of the tank walls.

The pin hole was repaired using Belzona compound.

The tank manway was opened and the tank interior was inspected which revealed rusting of the tank interior and the mixer blades were found on the tank bottom.

The tank manway was reinstalled.

Any remaining work will be performed af ter the 7R refueling outage.

Nuclear Service River Water Pump NR-P-lC - River water pump NR-P-lc was removed from service to replace a worn upper shaf t.

The motor was removed and the pump pulled and disassembled. A new shaf t was installed and the pump was reassembled and installed.

The motor was reinstalled, aligned and coupled.

The pump was tested and returned to service.

Spent Fuel Bridge - FH-A Repairs to the Spent Fuel Bridge were performed in May. A Stearns representative was on-site to direct removal and repair of the Control Rod Mast. Troubleshooting was performed on the mast prior to disassenbly. The mast was removed and additional troubleshooting was performed by the Stearns representative. As a result, limit switches, electrical cables, and valves were replaced.

The mast was tested and reinstalled in the bridge and the bridge was returned to service.

Some additional adjustments may be necessary at a later date.

Instrument Air Compressor - IA-P-1 A - Instrument Air Compressor IA-P-1 A was removed from service to correct unloader leakage.

The problem was corrected and the compressor was returned to service.

f 8806220308 880531

{DR ADOCK 05000289 DQ@

l OPERATING DATA REPORT l

DOCKET NO.

50-289 DATE 05-31-88 COMPLETED BY C.W. Smyth TELEPHONE (717)948-Q1 OPERATING STATUS NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

MAY

,1988.

3. LICENSED THERMAL POWER (;MWT) :

2535.

4. NAMEPLATE RATING (GROSS MWE) :

871.

5. DESIGN ELECTRICAL RATING (NET MWE) :

819.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

776.

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 744.

3647.

120504.

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744,0 3585.4 50105.9

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 61.6 1947.7

14. HOURS GENERATOR ON-LINE 744.0 3583.4 49183.2

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED

(. WH) 1881781.

9042649.

119530349, M

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 641626.

3108846.

39977067.

18. NET ELECTRICAL ENERGY GENERATED (MWH) 606588.

2936683.

37440965.

19. UNIT SERVICE FACTOR 100.0 98.3 40.8

20. UNIT AVAILABILITY FACTOR 100.0 98.3 40.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 105.1 103.8 39.8

22. UNIT CAPACITY FACTOR (USING DER NET) 99.5 98.3 37.9

23. UNIT FORCED OUTAGE RATE 0.0 1.7 54.8

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH Refuelinet Shutdown, June 17.1983 for 64 days

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF P,TARTUP:

AVERAGE DAZLY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE 05-31-.88 COMPLETED BY C.W. Smyth TELEPl!ONE (717) 948-8551 1

MONTH:

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

(MWE-NET) 1 824.

17 812.

2 826.

18

812, 3

826.

19 814.

4 825.

20 815.

5 821.

21 813.

6 818.

22 809.

7 816.

23 806.

8 822.

24 806.

9 823.

25 818.

10 818.

26 821.

11 815.

27 815.

12 820.

28 811.

13 812.

29 806.

14 817.

30 803.

15 81".

31 797.

16 815.

50-289 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME DATE 05-31-R8 COMPLETED BY C.W. Smyth REPORT MONni MAY TELEPHONE (/1/) 948-8551 e

e E

4

~4 Licensee gn, je, Cause & Corrective

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'h j ~E ~

No.

Date

~g i

2 Event g7 g3 Action to Repint =

mV o'

Prevent Recurrence y5 5

3 ;p3 H

c t

u 6

- NONE -

1 2

3 4

4 f: Forced Reason:

Methots:

Edibit G -Instructmns S: Siheduled A-fquipment Failure (Explain) 1 -Manual for Preparation of Data B Maintenance of Test 2-Manu.il Scram.

Entry Sheets for Lxenser C-Refueling 3 Autonutie Siram.

Event Report (LE R) Fde (NUREG-D-Regulatory Restriction 4-Other (I splain) 0161l 1 Operator Training & licenw I xamm.ition 5

F Adnunistraine Estubit I Same Source onal Ee ror (l:splam n G Operat}Explaint ll Other (

6 Actually used Exhibits F & 11 NUREC 0161

-l

., e '

REFUELING INFORMATION RE00EST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

June 17,1988 (7R) 3.

Scheduled date for restart following refueling:

August 19, 1988 4

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

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

Basic Refueling Report.

If answer is no, has the reload fuel design cnd 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)?

If no such review has taken place, when is it scheduled?

To be determined.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: April 5,1988 (TSCR 182 Cycle 7 Reload).

6.

Inportant licensing c nsiderations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

None 7

The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 177 (b) 284 8.

increase in licensed storage capacity that has been requested planned, in number of fuel asser611es:

The present licensed capacity is 752.

There are no planned increases at this time.

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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GPU Nuclear Corporation Gi U Nuclear

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

June 14,1988 C311 2080 U. S. Nuclear Regulatory Commission Attn:

Docunent Control Desk Washington, D.C.

20555

Dear Sir:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report May 1988 Enclosed please find two (2) copies of the May 1988 Monthly Operating Report for Three Mile Island Nuclear Station, Urit 1.

Sincerely, b.D.Huill Vice President & Director, TMI-1 HDH/SMO:spb cc:

W. Russell, USNRC R. Conte, USNRC Attachments 0015C t

GPU Nuclear Corporation is a subsidiary of the Genera! Public Utilities Corporation