ML20093E162

Monthly Operating Rept for June 1984

ML20093E162
Person / Time
Site:	Crane
Issue date:	06/30/1984
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM)
References
5211-84-2167, NUDOCS 8407170393
Download: ML20093E162 (6)

Text

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OPERATING DATA REPORT s

DOCKET NO.

50-289 DATE mv 18, inga COMPLETED BY c ti. w+h

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TELEPHONE 717_g a p'_ p qq1 l

OPERATING STATUS NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

JUNE

,1984.

3. LICENSED THERMAL POWER (MWT):

2535.

14. NAMEPLATE RA'1*ING (GROSS MWE):

871.

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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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:

i THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD 720 4367.

86160

12. nut 1BER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8

13. REACTOR RESERVE SHUTDONN HOURS 0.0 0.0 838.5

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 ENERCY GENERATED (MWH) 0 O.

25484330

18. NET ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

23840053.

19. UNIT SERVICE FACTOR 0.0 0.0 36.2 20 UNIT AVAILABILITY FACTOR 0.0 0.0 36.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 35.4

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 33.8

.23. UNIT FORCED OUTAGE RATE 100.0 100.0 60.5

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:

8407170393 840630 I

PDR ADOCK 05000289 R

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c-AVERAGE DAILY UNIT POWER LEVEL DOCK $T NO.

50-289 UNIT TMI-1 DATE anly 1 c;. 1994 COMPLETED BY c. k_ nnuth 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.

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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 O.

31 N/A 16 0

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50-289 UNIT SHUTDOWNS AP'D POWER REDUCTIONS DOCKET NO.

UNIT NAME TML-1 DATE July 15. 1984 CObrLETED BY C._H. Emvth REPORTMONTH mwr-lon4 TELEPHONE 717-948-B551 w.

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Cause & Corrective g{4 g,~

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Event RT Action to 4

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5je 3my Report me mo Prevent Recurrence oO E

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1 84-01-07 F

744 D

1 N/A ZZ ZZZZZZ f

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2 3

4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain)

I-Hanual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheels for Licensee C-Refueling 3 Automatic Scram.

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

E-Operator Training & License Examination F-Administrative 5

Goperational Error iExplain)

Exhibit I - Same Source Ilother (Explain)

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July 11,1984

' 3200-84-263 OPERATIONS

SUMMARY

The unit was in cold shutdown the entire report period by order of the NRC.

Core cooling was provided by the Decay Heat Removal System (except during short periods of high grid load). On June 4, partial draining of the RCS was commenced to enable valve repacking and other maintenance work that was identified during Hot Functional Testing.

On June 18 the RCS was filled, vented and was pressurized on June 19 to enable running of a RCP. As a result of slight increases in boron and tritium concentrations in the "B" OTSG secondary while the RCS was pressurized to 300 PSI, the RCS was again partially drained to enable bubble testing of "B" OTSG tubes. This testing was performed on June 25.

RCS work the remainder of the month involved entry into both OTSGs for. eddy current and tube plug verification.

MAJOR SAFETY RELATED MAINTENANCE During the month the following major maintenance items were completed.

Reactor Coolant Pump RC-P-1B Fabricated, installed, and painted new Nuclear Service Closed Cooling Water Piping to RC-P-1B oil and air coolers. The old piping was damaged and/or lost during RC-P-1B overhaul. All work is now complete.

Makeup Valve MU-V-205 Disassembled valve and replaced the stem and disc assembly because the tip of the disc was broken off.

The problem was identified by low flow through valve. All work was complete and tested with satisfactory results.

Chemical Addition Sample Valve CA-V-4B Replaced stem and disc assembly because old stem was scored / scratched resulting in excessive packing leak off. Valve was local leak rate tested after repairs and all work was complete.

Once Through Steam Generators RC-H-1A/_B Removed the upper and lower manways and handholes on "B" OTSG and upper manway and handhole on "A" OTSG for bubble / drip testing because of tube leakage identified by increased boron in the secondary side. Eddy current inspections commenced and will continue in July followed by repairs to identified leaking tubes.

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REFUELING,INFORMATION RECUEST l

I 1.

Name of Facility-L Three Mile Island Nuclear Station, Unit 1 I

2.

Scheduled date for next refueling shutdown:

[

Unknown 3

Scheduled date for restart following refueling:

t Unknown t

h.

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?

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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 t

(Ref. 10 CFR Section 50.59)?

r 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:

r 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 nudber of fuel assemblies (a) in the core, and (b) in the spent fuel

[

1 storage pool:

5 (a) 177 (b) 208 8.

The present licensed spent fuel pool storage capacity and the size of i

any increase in licensed storage capacity that has been requested or is planned, in number of fuel assedblies:

The present licensed capacity is 752. There are no planned increases at this time.

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The projected date of the last refueling that can be discharged to the spent i

fuel pool assuming the present licensed capacity:

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1988 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

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Nuclear Eu",ia';;;=""

Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Dir s' Olal Number:

July 13,1984 5211-84-2167 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 June Monthly Operating Report Enclosed please find two (2) copies of the June Operating Report for Three Mile Island Nuclear Station Unit.

Sincerely,

f. D.

kill, Director, TMI-1 HDH:mle Attachments cc:

V. Stello Dr. E. T. Murley i-l l

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