ML19211A648

Monthly Operating Rept for Nov 1979

ML19211A648
Person / Time
Site:	Three Mile Island
Issue date:	12/17/1979
From:	Stair J METROPOLITAN EDISON CO.
To:
Shared Package
ML19211A647	List: ML19211A646 ML19211A648
References
NUDOCS 7912200368
Download: ML19211A648 (5)

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, AVERAGE DAILY UNIT POWER LEVEL

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Docket No.10-280

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Unit 1 Date December 17, 1979

• Completed By Telephone (215) 921-6579 DA'? AVERAGE DAILY POWER LE'<EL DAY AVERAGE DAILY POWER LEVEL OMe-Net) ONe-Net)

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, OPERATING DATA REPORT Docxet ho. 50-289

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Date December 17, 1979 Completed By J. R. Stair OPEF.ATING STATUS Telephone (215) 021_As70

1. Unit Name: Three Mile Island Nuclear Station

2. F.eporting Period: November e

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3. Licensed Thermal Power (MWt): 2535

k. Nameplate Rating (Gross MRe): 871 5 Design Electrical Rating (Net MWe): 819

6. Max. Dependable Capacity (Gross Mwe): 8h0 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 MWe):

10. Reasons for Restrictions, If Any:

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Month Yr. to date Cumulative

11. Ecurs in Reporting Period 720. 8016. 46705,

12. No. of Hours Reactor was Critical 0.0 1128.0 31731.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 838.5

14. Hours Generator On-Line 0.0 1128.0 31130.9 15 Unit Reserve Shutdevn Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated UGH) 0. 2828hh8. 76531071.

17 Gross Elect. Energ7 Generated (!GH) O. 94599o. 25h8h330.

18. Net Electrical Energy Generated (IGH) -3510. 848301. 23840316.

19 Unit Service Factor 0.0 14.1 66.8 .

20. Unit Availability Factor 0.0 14.1 66.8 _

21. Unit Capacity Factor (Using MDC Net) -0.6 13.6 64.7

22. Unit Capacity Factor (Using DER Net) -0.6 12.9 6'3

23. Unit Forced Outage Rate 100.0 ,

85.4 2,. 7" 2h. Shutdowns Scheduled Over Next 6 Months (Type, Date, anu Duratica of Each):

i 25 If Shut Down at End of Report Period, Estimated Date of Startup;

26. Units In Test Status (Prior to Cc=mercial Operation): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY

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UNIT SHUTDOWNS AND POWER' REDUCTIONS Docket No. 50-289

• Unit Name TMI-1

'. REPORT MONTH November

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Date Dece'mber 17. 1979

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Completed By J,'R. Stair

• Telephone (215) 921-6579 No. Date Type l cu System Component Cause and Corrective -

gg n og gg Code 4 Code 5 Action to Prevent Recurrence

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1 11 / 1 / 7 9 F 720 D 1 .Regelatory Restraint Order j 1

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i I:F Forced 2Reason: 3 Methods S: Scheduled A-Equipment Failure (Explain) 14fanu al

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B-Maintenance or Tc':t " '

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24fanual Scram. Event . m t (LER, - j C-Refueling 3-Automatic Scram. "

D-Regulatory Restriction h-Other (Explain) '

E-Operator Training & Licensee Examination -

F-Administrative G-Operational Error (Explain) 5 Exhibit 1 - Srme Scurce 1 g

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OPERATING

SUMMARY

Unit I remained in cold' shutdown with the "B" Decay Heat Removal System providing core cooling.

MAJOR SAFETY RELATED MAINTENANCE Spent Fuel piping indications #13, 14, and 22 were repaired satisfactorily. The repair included removal of the indication, weld prep of the pipe and installation of a spool piece or dutchmen (included fit up, welding). The repairs were performed without adversely affecting the cooling of the spent fuel pools.

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i634 017

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REFUELING INF0FMATION REQUEST _

1. Name of Facility: .

Three Mile Island Nuclear Station, Unit 1

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2. Scheduled date for next refueling shutdown:

Unknown 3

Scheduled F. ate for restart following refueling:

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Unknown

4. Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment?

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If answer is yes, in general, what vill these'be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Consittee 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?

A=endnent No. 50, Cycle 5 reload, was approved on 3-16-79 Scheduled date(s) for submitting proposed licensing action and suppcrting 5

infor=ation:

N/A

6. Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures:

N/A ,

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

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(a) 177 1634 018 (b) 208

8. The present licensed spent fuel pool storage capaci planned, in number of fuel assemblies:

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

at this tine.

9 The Projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1986 is the last refueling discharge which allovs full core off-load ,

capacity (177 fuel assemblies). . .. . ? - ...

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