ML20132F254

Monthly Operating Rept for June 1985

ML20132F254
Person / Time
Site:	Crane
Issue date:	06/30/1985
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
0015C, 15C, 5211-85-2126, NUDOCS 8507180362
Download: ML20132F254 (7)

Text

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OPERATIONS

SUMMARY

JUNE, 1985 The Unit was in cold shutdown until June 7,1985. Core cooling was being provided by the Decay Heat Removal System.

On June 8, 1985, the plant was taken to hot shutdown in preparation for startup on June 11, 1985. With the positive NRC vote and the following Court of Appeals stay, the plant was maintained hot to enable the operating crews to gain experience under these conditions.

On June 17, 1985, the main turbine was rolled to its rated speed, 1,800 rpm.

This test was performed with satisfactory results.

As the end of the month, the plant remains in hot shutdown awaiting the outcome of the Court of Appt cls hearing.

Major Safety Related Maintenance The following major work items were completed during the month:

Reactor Buildina Tendon Surveillance - The Tech. Spec. scheduled periodic surveillance was completed on June 10, 1985. Preliminary evaluation of data indicated satisfactory tendon system performance.

Air Handling System Purge Valves - Air Handling System Purge Valve repairs (leakage by the seats) on AH-V-10 and AH-V-10 were completed during June, 1985. The valve seats were readjusted and " snoop" tested. The valve repairs were tested satisfactorily.

Feedwater Valve FW-V-81B_ - Valve FW-V-81B was repaired (body to bonnet leak) in June, 1985.

The bonnet bolts were retorqued but no reduction in leakage was obtained. Duetoplantconditions(hotshutdown)thevalvebonnetwas injected with furmanite. There was no leakage at FW-V-818 after injection.

The valve will be repaired at a later date as plant conditions permit.

Feedwater Pump FW-P Feedwater Pump FW-P-1B (turbine steam chest flange leak) was repaired in June, 1985.

The flange bolts were retorqued with leakage reduction. One bolt area continued to leak after retorquing.

Because the plant was hot, the flange was injected with furmanite. There was no post injection leakage. The flange will be repaired at a later date.

Emergency Feedwater Pump EF-P-2A - Repairs to EF-P-2A (failed to start) were completed during June, 1985.

Repair work consisted of relay adjustment. The pump tested satisfactorily.

Chemical Addition System Valve CA-V Valve CA-V-13 (would not cycle) was repaired in June, 1985.

The operator was removed and the valve disassembled and inspected.

The valve stem was found damaged and was replaced.

The valve was reassembled, and the operator reinstalled.

The valve was IST and LLRT tested. The operator mounting flange required adjustment. All testing was satisfactory and all work is complete.

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2-l Waste Disposal Liquid System Filter WDL-F-1B - Precoat filter WDL-F-1B repairs f

(high D/P) were completed during June, 1985.

Valve WDL-V-276 was opened along

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with the flow orifice to facilitate fiber optic inspection of the flow path.

The inspection revealed no blockage. The filter housing dome was removed and the fourteen (14) elements were replaced. The filter was closed and tested l

satisfactorily.

Precoat filter WDL-F-1A will be opened during July,1985.

Emergency Diesel Generator EG-Y-1ALB - Emergency Diesel Generators EG-Y-1A/B generator damp (ening bars were removed in June, 1985 based on an NRC notification failure at Calvert Cliffs).

The dampening bars were removed and the generators were one-hour test run satisfactorily, i

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REFUELING INFORMATION REQUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 l

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Scheduled date for next refueling shutdown:

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Unknown 3.

Scheduled date for restart following refueling:

Unknown 4.

Will refueling or resumption of operation thereafter require a technical 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 Coc:sittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50 59)7 If no such review has taken place, when is it scheduled 7 i

Amendment No. 50, Cycle 5 reload, was approved on 3-16-79 5.

Scheduled date(s) for submittin'g preposed licensing action and supporting l

informations N/A 6.

Important licensing considerations associated with refueling, e.g. nov 1

or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures N/A 7.

The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 177 (b) 206 8.

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

The present licensed capneity 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 alleva full core off-load capacity (177 fuel assemblies).

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OPERATING DATA REPORT

)

DOCKET NO.

50-289 I

DATE 06/30/85 I

COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 i

i OPERATING STATUS I

j NOTES

1. UNIT NAME:

Ti!REE MILE ISLAND UNIT 1 i

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2. REPORTING PERIOD:

JUNE

,1985.

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3. LICENSED TilERMAL POWER (MWT) :

2535.

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4. NAMEPLATE RATING (GROSS MWE):

871.

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5. DESIGN ELECTRICAL RATING (NET MWE) :

819.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

776.

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

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9. POWER LEVEL TO WHICil RESTRICTED, IF ANY (NET MWE) 4

10. REASONS FOR RESTRICTIONS, IF ANY:

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TilIS MONTl!

YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD 720.

4343.

94920.

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12. NUMBER OF llOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8 i

13. REACTOR RESERVE S!!UTDOWN llOURS 0.0 0.0 838.5 l

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14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9

15. UNIT RESERVE SHUTDOWN llOURS 0.0 0.0 0.0 j

16. GROSS TilERMAL ENERGY GENERATED (MWil) 0.

O.

76531071.

17. GROSS ELECTRICAL ENERGY GENERATED (MWil) 0.

O.

25484330.

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18. NET ELECTRICAL ENERGY GENERATED (2MWil)

O.

O.

23840053.

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19. UNIT SERVICE FACTOR 0.0 0.0 32.8 i

20. UNIT AVAILABILITY FACTOR 0.0 0.0 32.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 32.1

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22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 30.7

23. UNIT FORCED OUTAGE RATE 100.0 100.0 64.4 I

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24. SilUTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACil l

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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE 06/30/85 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 MONTH:

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

(MWE-NET) 1 0,

17

-0.

2 0.

18 0.

3 0.

19 0.

4 0,

20 0.

5 0.

21 0.

6 0.

22 0.

7 0.

23 0.

8 0.

24 0.

9 0.

25 0.

10 0.

26 0.

11 0,

27 0.

12 0.

28 0.

13 0,

29 0.

14 0.

30 0.

15 0.

31 N/A 16 0.

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M GPU Nuclear Corporation

. Nuclear

,ome:r8o s

Middletown, Pennsylvania 17057 0191 l

717 944 7621 TELEX 84-2386 Writer's Direct Dial Number:

July 12, 1985 5211-85-2126 I

Office of Management Information and Program Control Attn:

W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Mcdonald:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report June, 1985 Enclosed please find two (2) copies of the June,1985 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.

Sincerely, l

,}

. D. Hukill Director, TMI-1 HDH:JGB:spb Attachments cc:

V. Stello Dr. T. E. Murley l

0015C

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

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