ML20010C815

Monthly Operating Rept for Jul 1981

ML20010C815
Person / Time
Site:	Crane
Issue date:	08/15/1981
From:	Smyth C METROPOLITAN EDISON CO.
To:
Shared Package
ML20010C813	List: ML20010C812 ML20010C815
References
NUDOCS 8108210042
Download: ML20010C815 (5)

Text

__..

h OPERATLNG DATA REPORT DOCKET NO.

50-289 DATE Aucust 15, 1981 1' '

COMPLETED BY C. W._hyth TELEPHONE

'7174 968 9551 i

4 OPE, RATING STATUS Three P.ile Island Nuclear Station, Unit I

1. Unit Name:

= 2. Reporting Period:

July. 1981 2535

3. Licensed Thermal Power (MWt):

671

4. Nameplate Rating (Gross MWe):

819 l

S. Design Ele:trical Rating (Net MWe):

0 1

6. Maximum Dependable Capacity (Gross Mher {#

)

7. Maxirc.um Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

i i

l{.

9. Power I avel To Which Restricted.If Any (Nct MWe):

10. Reasons For Restrictions,If Any: _

)

1 l

J This Month Yr to.Date Cumulatise 744.

5087.

60600.

11. Hours in Reporting Period 0.0 0.0 31731.S 4

12. Number Of Hours Reactor Was Critical 0.0 0.0 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9 4

14. Hours Generator On.Line 00 0.0 0.0

15. Unit Resene Shutdowv. Hours 0.0 0.0 76531071.

4

16. Gross Thermal Energy Generated (MWH)

~

O.

O.

25464330.

17 Gross Electrical Energy Generated (MWH) u.

U.

2364uvas.

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1S. Net Electrical Energy Generated (MWH) 0.0 0.0 51,5

~

19. Urut Senice Factor 0.0 0.0 51.5

20. Unit Availability Factor l

21. Unit Capacity Factor (Using MDC Net).

0.0 0.0 au.1 0.0 0.0 gn

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 3j,5 i

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

j l

25..lf Shut Down At End Of Report Period. E;tir sted Date of Startup:

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved 4,

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.-e, AVERAGE D AILY L' NIT POWER LEVEL DOCKET NO, f0-289 M ~1 UNIT DATE August 15, 1981 COMPLETED BY - C. k'.

Smyth (717) 948-8551 TELEPHONE -

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OPERATIONS SU)D!ARY t

The Unit was shutdown the entire month by order of the NRC. Core i

cooling was provided by the Decay Heat Removal System.

FUGOR SAVETY RELATED MAINTENANCE During the month of July the Unit operated in the cold shutdown with restart modifications and Hot Functional Test preparations being performed.

The following major maintenance activities were performed.

The Integrated Loe.al Leak Rate Test (ILRT) was performed with satis-factory results. The testing.equence included:

i a)

Reactor Building Inspection prior to commencing prassurization.

b)

Pressurize Reactor Building to 12 psi.

c)

Reactor Building Inspection at 12 psi.

d)

Pressurize Reactor Building to 50.2 psi, e) Stabilize pressure at 50.2 psi.

j l.

f) Pressure drop test for twenty-four (24) hours.

i g)

Superimposed leak check.

h)

Depressurize Reactor Building to one (1) psi.

l i)

Hydrogen purge test.

I 1

Decay Heat River Water Pump (DR-P-1A) and motor were inspected.

Tolerance readings wer, taken on pump parts, motor bearings were inspected, balancing was perfJrmed on the motor and pump bowl assemblies, the pump and motor were reassembled, and motor to pump was coupled.

On-line bo'.

ing of the pump was performed with satisfactory results, ant

• te pump was returned to service.

4 e

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RETUE*.ING INFOPJ'.ATION REOUEST 1.

Name of Facility:

Three Mile Island Nuc1 car Station, Unit I 2.

Scheduled date for next refueling shutdown; Unknown 3.

Scheduled date for restart following refueling:

Unknown 4.

k'ill refueling or resumption of operation thereaf ter require a technical specification change or other license a=endment?

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 Co==ittee to determine shether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

If ro 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 sub=itting proposed licensing action and supporting information:

N/A 6.

1=portant 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 refucifng that can be discharged 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).