ML20112E639

Monthly Operating Rept for Feb 1985

ML20112E639
Person / Time
Site:	Crane
Issue date:	02/28/1985
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
5211-85-2058, NUDOCS 8503270063
Download: ML20112E639 (6)

Text

y-OPERATING DATA REPORT DOCKET NO.

50-289 DATE February 28.198! -

COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

FEBRUARY,1985.

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:

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THIS MONTH YR-TO-DATE CUMMULATIVE-I

11. HOURS IN REPORTING PERIOD 672.

1416, 91993.

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8 l

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5 l

14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH)

-O.

O.

76531071.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.

O.

25484330.

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.

O.

23840053.

19. UNIT SERVICE FACTOR 0.0 0.0 33.9

20. UNIT AVAILABILITY FACTOR 0.0 0.0 33.9 l

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 33.1

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 31.6

23. UNIT FORCED OUTAGE RATE 100.0 100.0 63.2 i

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:

0503270063 050228 PDR ADOCK 05000289 v

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1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE February 28. 1985 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 MONTH:

FEBRUARY 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 N/A 14 0.

30 N/A 15 0.

31 N/A 16 0.

50-289 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME TMI-I DATE February 28. 1985 COMPLE1ED BY C. W SmLth REPORT MONTH Februarv. 1985 f '17D4B-n55T 1ELEPHONE w.

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4 F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regularory Restriction 4-01her (Explain) 0161)

E-Operator Training & License Examination F. Administrative 5

G-Operat}'onal Error (Explain)

Exhibit I - Same Source Il-Other (Explain)

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. w OPERATIONS

SUMMARY

-The Unit-was.in cold shutdown the entire month by order of the NRC.. Core cooling was provided by the Decay Heat Removal System. The Reactor Coolant System was partially drained to permit OTSG tube repair work to continue. The secondary side remained in full wet layup the entire month.

Major Safety Related Maintenance OTSG's RC-H-1A/B - During February,1985 the OTSG _ tube plugging was completed with the installation of 53 B&W rolled type tube plugs installed in the "A"

0TSG upper tubesheet. Wall thinning calculations were performed on_18 rolled plugs and pull testing was satisfactorily performed on 7 plugs. There were 93 B&W ribbed mechanical plugs installed in the "A" OTSG lower.tubesheet. Tube plugging in.the "B" 0TSG included 5 rolled and 5 welded plugs in the upper.

tubesheet, and 10 ribbed plugs.in the lower tubesheet. The lower nenways are being installed and a " bubble test" of the OTSG's will be performed in March.

NUCLEAR SERVICES CLOSED COOLING PUMP NS-P-1B - The NS-P-1B pump overhaul was completed during February,1985. The pump was reassembled, the coupling was aligned and the pump was run tested satisfactorily.

AIR HANDLING SYSTEM PURGE VALVES AH-V-1A/B/C/D - Work continued on the Air Handling purge valves AH-V-1A/B/C/D during February, 1985. The following work items were completed:

AH-V-1A - The valve was opencd and the old seats were removed.. New seat material was cut, installed and fit into the valve. Work is

' in progress and will continue in March, 1985.

AH-V-1B - The valve was opened and the old seats were removed. New seats were cut and installed. The seats were shimmed, fit and pressure drop test and " snoop" inspections were performed. Work will continue in March, 1985.

AH-V-1C - The valve.was opened and the old seats removed. New seats were cut, installed, shimmed and fit. A pressure drop test and " snoop" inspection were performed. The valve was closed and local leak rate testing was satisfactorily performed. All work is complete.

AH-V-1D - New seats were fit, shimmed, and installed.

Pressure drop test and " snoop" inspections were perf rmed.

The bearings were greased and the valve was satisfactorily local leak rate tested. All work is complete.

DECAY HEAT VALVE - DH-V Decay Heat Removal Valve DH-V-1 (terminal block not environmentally qualified) work was completed during February,1985. The operator motor leads were discovered to be frayed and a new motor was installed. The motor leads were butt spliced with Ray Chem heat shrink instead of using a terminal block. All work is complete.

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REFUELING INFORMATION REQUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

Unknown 3

Scheduled date for restart following refueling:

Unknown b.

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

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)?

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

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

Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A 6.

Important licensing considerations 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:

N/A 7

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

(a) 177 (b) 208 8.

The present 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 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).

GPU Nuclear Corporation Nuclear

,omeereo s

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

March 18, 1985 5211-85-2058 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 February, 1985 Enclosed please find two (2) copies of the February, 1985 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.

Sincerely, b

. D. H0 kill Director, TMI-1 HDH:JGB:spb Attachments cc:

V. Stello Dr. T. E. Murley 0015C d

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