ML20009D070

Monthly Operating Rept for June 1981

ML20009D070
Person / Time
Site:	Crane
Issue date:	07/15/1981
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML20009D067	List: ML20009D066 ML20009D070
References
NUDOCS 8107230087
Download: ML20009D070 (5)

Text

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OPERATLNG DATA REPORT DOCKET NO.

50-289 DATE Julv 15. 1981 COMPLETED BY D.

C. Mitchell TELEPHONE (7171 OLA R99' OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

June. 1981

2. Reporting Period:

2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

819

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gro:

4e): g0

1. 'b

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cumulative 720.

4343.

50856.

I1. Hours in Reporting Period 0.0 0.0 31731.8

12. Number Of Hours Reactor Was Critical 0.0 0.0 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9

14. Hours Generator On-Line U*O 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Et,ergy Generated (MWH)

O.

O.

254be330.

17. Gross Electrical Energy Generated (MWH)

~

u.

u.

2 3 64.ue;.

18. Net Electrical Enerr., Generated (MWH) 0.0 0.0 52.1

' 19. Unit Service Factor.

U*U u.u 52.1

20. Unit Availability Factor 0.0 0.0 50.7

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 48.6

22. Unit Capacity Fa: tor (Using DER Net) 100.0 100.0 40.7

,23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

l

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

Forecast Achieved

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l INITIAL CRITICALITY L

INITIAL ELECTRICITY COMMERCIAL OPERATION L

8107230087 810716 PDR ADOCK 05000289 to/7;i t.

R PDR.

... ~.

[F

~

r AVER AGE DAILY UNIT POWER LEVEL

^

6 DOCKET NO.

50-289 TMI-I

' WIT DATE July.15, 1981 COMPLETED BY D

G. Mitchell TELEPHONE (717) 948-8553

~

June,-1981 MONTH DAY AVERAGE DAIL ' OWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) 1-0 17 0

2-0 0

jg 3

0 0

,9 4

0 0

20 5

0' 0

21 0

6 0

22

7 0

o 73 3

0 0

2.s 0

0

9 2c 0

.10 26 0-11 27 0

0 12 28 0

13 29 0

0 14-30 0

0 15 31 0

16 0

a

-~

50-289 DOCKET NO.

. UNITSilUTDOWNS ANI) POWER REDUCTIONS UNIT NAME Ihl-l DATE July 15. 1981

~

COMPl.ETED ilY D. C. Mitchell REPORT MON 111 June TEl.E. etONE- (7171 QAR-R551 h

e re 3 en a 5

bICCR5CC h,

Cause & Corrective

$ _C 3

gyy

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gJI' g

N

.c 3 n:

Event

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3 Adlon to d"E cE j6g Report it

<N G jU Prevent Recurrence H

8 ReRuintory Restraint Order 1

6/1/81 F

720 D

1 i

r i

2 3

4 F: Forced Reason:

Metliod:

Exhibit G - Instructions S: Schednted A Equipment Failure (Explain) 1 -Manual for Preparation of Data Il Maintenance of Test 2 Manual Scram.

Entry Sheets f or Licensee C. Refueling 3 Aufomatic Scram.

Event ReporI (I.ER) File INilRI:G-D Regulatory Restriction 4 Other (Explain) 0161)

E Operator Training A IJcense Examination F. Ad minist ratIve 5

Exhibit I Same Source G-Operaljonal Error (Explain)

Il Other (Explain)

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OPERATIONS

SUMMARY

-The plant. remained' in cold shutdown the entire month by order of

'the NRC. The Decay Heat Removal System provided core cooling.

g-MAJOR SAFETY RELATED MAINTENENCE During the month of June ~ the - following major maintenance items were performed.

~1) -Local Leak Rate Test (LLRT) y This test was completed during this month with satis-4

~ factory results.

The total as left. leakage was within th'e acceptance-criteria required for preparation of.the Integrated Leak Rate Test of the Reactor Building.

2) ~ Integrated Leak Rate Test (ILRT)

Preparation for the test-began with the following items being performed.

a)

Instrument. calibrations.

b) Paactor Building inspected.

c) !!,quipment protected.in Reactor Building.

d) Gas bottles, flamables, oil, etc. removed.

e) Manometers installed.

f).Tess ianel area setup (tables, lights, etc.).

Building pressurization began during July and was successfully completed.- Details will be reported in the July Report.

3) Purge Valve AH-V-1A Inspection of the bearings for purge ~ valve AH-V-1A was performed and the following work was performed, a) Removed pneumatic operator, b) Removed bearing / inspect bearings.

[

c) Regreased bearings.

d)

Installed bearings.

e) Reinstalled operator.

Af ter completion of the bearing inspection work, the rubber

. seat in the valve was replaced. Replacement work included opening the direct access port, removal of old rubber material, clean up of seat area, reinatallaton of new rubber seats, torquing of segment bolts, etc.

A pre-liminary leak check was perforned to see if any leaks were present.

The access pcrt was closed and a satisfactory, final leak check was perfor:ed.

4)

Decay Heat River Water Pumo (DR-P-1A)

Pump work progressed with the pump being reassembled, motor balanced and coupled to pu=p.

On line balancing of the pump and motor was unsuccessfully attempted.

The motor and pump were removed : and inspections are being perf ormed to de-termine the cause of high.bration. This work continued into July and will be discussed in the July Report.

-..E REFUELING IhTORMATION REOUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit'I 2.

Scheduled date.for next refueling shutdoin:

Unknown 3.

Scheduled date for restart following refueling:

. Unknown 4.

Will refueling or resumption of operation thereefter require a technical specification change or other license amendment?

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 yot'r Plant Safety Review Committne to determine whether any unreviewed safety questions are associated with the core reload

'(Ref.-10 CFR Section 50.59)?

such avieu has taken place, when is 1*. scheduled?

Amendment No. 50, Cycle 5 reload, was approved on 3-16-79.

5.

Sc.ieduled date (s) for submitting proposed licensing action and supporting information:

N/A 6.

Importent licensing considerations associated with refueling, e.g. new or.different fuel design or supplier, unreviewed design or performance anal 7cis methods, significant changes in fuel design, new operating procedures:

N/A The number of fuel assemblics (a) in the core, and (b) in the spent fuel 7.

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.

The projected date of the last refueling that can be discharged to the spent 9.

fuel pool assuming the present licensed capacity:

1986 is the last refueling discharge which allows full core off-load yp3ci capacity (177 fuel assemblies).

.