ML20003C844

Monthly Operating Rept for Feb 1981

ML20003C844
Person / Time
Site:	Three Mile Island
Issue date:	03/15/1981
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML20003C842	List: ML20003C841 ML20003C844
References
NUDOCS 8103180565
Download: ML20003C844 (5)

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i OPERATING DATA REPORT -

.i DOCKET NO. 50-289 DATE 3-15-81 COMPLETED BY D. C. witchell t TELEPHONE ('17) 048 a m OPERATING STATUS Three Mile Island Nuclear Station', Unit I l

l. Unit Name

2. Reporting Period:. Februarv 19}l

3. Licensed Thennal Power (MWt):

2m .

4. Namepiste Rating (Gros MWe): 871

5. Dengn Electrual Rating (Net MWe):

019

6. Maximum Dependable Capacity (Grom MWe):

840 7#D

. 7. Maximum Dependable Capacity (Net MWe):

8. If Chands Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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9. Power Level To Which Restricted,if Any (Net MWe):

10. Reasons For Restnctions,if Amy:

' This Month Yr to.Date Cumulatise

11. Hours In Reporting Period 672. 1416.' 56929. .

12. Nanber Of Hours Reactor Was Critical 0.0 0.0 31731.8

.13. Reactor Reserw Shutdown Hours 0.0 0.0 839.5 0.0 0.0 31180.9

14. Hours Generator On.Line 0 D. 0.0 0.0

15. Unit Reserve Sheadown Hous 0.0 . 0.0 76531071.

16. Gros Thennel Energy Generated (MWH)

O* O. -'c454J30.

17. Grom Elecencal Energy Generated (MWH)

u. u. 4as4uuaa.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 33,g j 19. Unit Semce Factor 0.0 U.o 54.8

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net)

. 0.0 0.0 53.3

22. Unit Capedty Factor (Using DER Net) 0.0 0.0 51.1 100 O~ 100.0 37.1

23. Unit Forced Outage Rat,

24. Shracowns Scheduled Over Next 6 Months (Type. Dete.and Duration of Eacht: s. I P

25. If Shut Down At End Of Report Penod.Estinnated Date of Startup:

26. Units In Test Status (Prior to Commercini Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8103180565a !

AVER AGE D AILY UNIT POWER LEVEL DOCKET NO. 289 l 31T UII-I DATE March 15, 1981 COMPLETED BY - D. C. Mitehell TELEPHONE -(717) 948-8553 MONTH February 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL tMWe-Net) (MWe-Nt s 1 0 g7 o-2 0 jg 0 ,

3 0 0 39 4 0 0 3

5 0 0 21 0 '

6

0

. 7 0 0 3

3 0 0 -

24 9 0 3 0 0 '

10 0 26 II 27 0 12 0

s 0 l

0 13 0 29 14 0 3o 0 I$ 0 0 3g 16 0 s

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i IX)CKET NO. 50-2R9 UNIT SilUTUOWNS AND POWER REDUCTIONS UNIT NAME IMI-I _

DAlt Harch 15. 1180 REPORT MONill February , COMFt.E1Eli BY D. C. M11che1I TELErilONE f 7171 943-8553

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Nie- l> ate Event Action soi

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• $"5 e7 Repms

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j di g Prevent Recurr'end 6 l.

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Regulatory Rentraint Order 1 2/1/81 F 672 D 1 i

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F: Forced Reason: i Methoil:-  !

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Exhibit G . Instdicthms S: Scheduled A Fquipment Failure (Explain) I-Manual ,

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for Preparatiim of Data 8

B Mahitenance of Test l 2 Manual Scram. Entey Sheets for'l.icchsee  ! : ,

C-Refueling -

3 Automatic Scram. l ;

ll; l Event Repor)(l_ER) fileINtfREC-I D-Regulatory Restelction 4-Other(Emplain)! ; i'  ; j l

! j ' 0161)

E Operator Training a license Examinathm 4 - ' ' I i

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F-Administrative , .

, i i 5 , , l 1 G-Operational Error (Explain) Exhibit 1 - S 6mejSourye Il-Other (Explain t ' -

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OPERATIONS SDDfARY The Unit was shutdown the entire month by order of the NRC. Core Cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RELATED MAINTENANCE l During the month of February, the Unit was in cold shutdown while restart activities were in progress. The following major maintenance items were performed.

Refueling Outage Surveillance Testing continued for the snubber program with snubbers being tested and reinstalled, minor bleed rate adjustments being performed. As required by Technical Spec-ifications, additional snubbers were pulled as a result of f ailures.

This program will continue into March.

The local leak rate testing surveillance programs, started in February, progressed with no excessive leak rates recorded. This ~

surveillance will continue in March.

Replacement of one of the Industrial Coolant Isolation Valves (RB-V-7) -- -_-

was in progress during this month with the following items being

. performed.

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- - 1. Insulation removed from valve and pipe around valve.

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2. Pneumatic operator removed. - ---

3. Valve cut from pipe.

- .- - -- .4. Weld preparations performed. ~

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5. Fitup inspections performed. . . . . _ . _ _

6. Hot /roct pass welds performed.

7. Final weld out in progress. - - - -

This work was performed with satisfact9ry results. ---~ ~ ~ ~

+ - - - __

--Restart task on PORV and Safety Valve Indication (tie-in portion),

was performed with satisfactory restilts. .Thic included welding-of - - ----

iilpples to elbows, drilling of holes into elbow, installation of

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pipe to first isolation valve. No problems were encountsred~whire performing this work. _.._ _ _ _ _ __.,

96K M e-m me om.wh.,..%m..e ,

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l I** REFLTf.ING IhTORMATION REOUEST

1. Name of Facility:

Three Mile Island Nuclear Station, Unit I

2. Scheduled date for next refueling shutdown:

Unknown

3. Scheduled date for restart following refueling:

(

Unknown

4. Will refueling or resumption of operation thtraafter require a technical specificat:!.on change or other license amendment?

i 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 Comunittee 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.

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5. Scheduleddate(s)forsubmittingproposedlicensingactionandUupporting information:

6. Important licensing considerations associated with refulling, e.g. new or different fuel design or supplier, unreviewed design or performance

_ analysis methods, significant changes in fuel design, new operatin; procedures:

N/A

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

(a) 177 (b) 208 '"

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8. The presert licensed spent ft.1 pool storage capacity and the size of any increase in licensed sto age capacity that has been requested or is planned, in number of fuel i esemblies:

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 lischarged to._the._ spent fuel pool assuming the present licensed capacity:

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

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