ML19254D009

Monthly Operating Rept for Sept 1979

ML19254D009
Person / Time
Site:	Three Mile Island
Issue date:	10/15/1979
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19254D003	List: ML19254D002 ML19254D009
References
NUDOCS 7910190281
Download: ML19254D009 (5)

Text

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OPERATING DATA REPORT Docket No. 50-289 Date Cetober 15. 1979 Completed By D. G. Mitchell OPERATING STATUS Telephone (215) 921-6579

1. Unit Name: ho vilo Tc1 wa twn 3

2. Reporting Period: September 3 Licensed Thermal Power (MWt): 2535

h. Nameplate Rating (Gross !Ge): 871 5 Design Electrical Rating (Net MWe): 819

6. Max. Dependable Capacity (Gross MWe): 840 7 Max. Dependable Capacity (Net MWe): 776

8. If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:

9 Power Level to which Restricted. If Any (Net IWe):

10. Reasons for Restrictions, If Any:

bbnth Yr. to Date Cumulative 720 6ssl 44520

11. Hours in Reporting Period

12. No. of Hours Reactor was Critical 0.0 1199 n ,1731_o 13 Reactor Reserve Shutdown Hours 0.0 0.0 838.s lb. Hours Generator On-Line 0.0 1128.0 11100 o 15 Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0 2828448 76531071 17 Gross Elect. Energy Generated (MWH) 0 945996 25484330

18. Net Electrical Energy Generated (MWH) -3160 9 5o71 , 23q5973g 19 Unit Service Factor 0.0 17.2 70.0

20. Unit Availability Factor 0.0 17 9 ,o 9

21. Unit Capacity Factor (Using MDC Net) -0.6 16.9 67.4

22. Unit Capacity Factor (Using DER Net) -0.5 16.0 cm _t

23. Unit Forced Outage Rate 100.0 79.6 16.0

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; April 1, 1980

26. Units In Test Status (Prior to Cocmercial Operation): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i190 058 q910 19 0 2~ 0 /

Docket No. 50-289 UNIT SIfUTDOWNb AND POWER REDUCTIONS S ptanber Unit Name Three Mile Island 1 REPORT MONTII Date October 15, 1979 Completed By D. G. Mitchell

- Telephone (215) 921-6579 No. Date Type l $2 m System Component Cause and Corrective nm l S $g g Code h Code 5 Action to Prevent Recurrence g ng g o g g

• d5E 8@j ine 3 ?i r.

1 9/1/79 F 720 D 1 Regulatory Restraint Order i

1F: Forc ed 2Reason; 3 - ns kue dons Methods ""

S: Scheduled A-Equipment Failure (Explain) 1-Manual

1. *E # " "

B-Maintenance or Test 2-Manual Scram.

C-Refbeling Event Report (LER) File

_ 3-Automatic Scram. -

e D-Regulatory Restriction h-Other (Explain) o E-Operator Training & Licensee Examination F-Administrative O G-Operational Error (Explain) Exhibit 1 - Same Source U' II-Other (Explain)

I -

I REFUELING INFORMATION REQUEST

1. Name.of Facility:

Three Mile Island Nuclear Station, Unit 1 .

r\

2. Scheduled date for next refueling shutdown:

Unknown l

l 3. Scheduled date for restart following refueling:

Unknown i

f 14 Will refueling or resamption of operation thereafter require a technical specification change or other license amendment?

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

l 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 placa, when is it s'had"1r 17 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 l .

l 6. Important licensing considerations associated with refueling, e.g. new i

or different fuel design or supplier, unreviewed design or performance l

• 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:

f (a) 177 (b> 212

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 758. There are no planned increases at this time.

4 The projectcel date or t.hr lunt, rnruoline that enn bo linchared to the npe n t, ruel pool nnnoming the prenonL ! !cou +d enpac i t.y :

1986 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

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OPERATING

SUMMARY

Unit I remains in cold shutdown with the "A" Decay Heat Removal System providing core cooling. On September 6, 1979, core cooling shifted from the "B" to the redundant "A" Decay Heat Removal string. The transfer resulted from a failure of the coupling between the "B" Decay Heat pump and motor. Repairs to the coupling were completed on September 12, 1979.

MAJOR SAFETY RELATED MAINTENANCE

SUMMARY

While the primary plant was being cooled, using the "A" Decay Heat system, the damaged "B" Decay Heat pump coupling was replaced. Following replacement, cold and hot alignment checks and additional testing were performed. All testing proved satisfactory and the pump was returned to service. The cause of the failure was determined to be a lack of lubrication in the coupling spider.

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