ML19345H538

Monthly Operating Rept for Apr 1981

ML19345H538
Person / Time
Site:	Three Mile Island
Issue date:	05/15/1981
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19345H533	List: ML19345H532 ML19345H538
References
NUDOCS 8105210219
Download: ML19345H538 (5)

Text

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OPERATING DATA REPORT DOCKET NO.

50-289 DATE' Mav li. 1981 COMPLETED BY D. C "itchell 1

TELEPHONE (lli) 04P S553 4

OPERATING STATUS "1 tree Mile Island Nuclear Station, Unit I

1. Unit Name:

Anril 1981

2. Reporting Period:

2535

3. Licensed Thermal Power (MW:):

671

4. Nameplate Rating (Gross MWe):

819 S. Design Electrical Rating (Net MWe):

840

6. Maximt". Dependable Capacity (Gross MWe):

776

7. Maximurc Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (1: ems Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restric rd. If Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr. to-Dat e Cumulative 719.

2879.

58392.

i1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 3.0 0.0 31731.8

13. Reactor Reserve Shutdown Hours 0.0 -

O.O n,o,g 0;0 0.0 31180,9

14. Hours Generator On.Line 00 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Energy Generated (MWH)

O.

O.

D464DO.

17. Gross Electrical Energy Generated (MWH) 0, v.

43eauvaJ.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 53.4

19. Unit Service Factor u.o v.o 53.4

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net).

0.0 0.0 51.9 0.0 0.0 49,9

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 38.9

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:

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

Forecast Achievea INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPERATION

'9 8165210219

AVERAGE D AILY UNIT POWER 1.EVEL DOCKET NO.

50-289 TMI-I UNIT DATE May 15. 1981 COMPLETED BY

__D.

G. Mitchell TELEPHONE (717) 948-8553 MONni April, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mbe-Net)

(MWe Neti I

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i 50-289 DOCKET NO.

UNIT SilUIDOWNS AND POWER REDT!CTIONS UNIT NAME 'IME-l DATE May 15. 1981 COMPLETED BY D G. Mitchell REPORT MONT1f April, 1981 TELEPilONE (117) 948-8553 5 E

.E Licensee

[-(

k"3 L

Cause & Corrective No.

D.ite k

5@

o55 Event

~ '!

Action to g

P

$E 5

jgg Report 8r in U u

Prevent Recurrence b.

egu a ry straint Order 1

4/1/81 F

719 D

1 I

2 3

4 F: Forced Reason:

Methal:

Exhibit G -Instructions S: Scheduled A Fquipment Failure (Explain) 1 Manual for Preparation of Dasa B. Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C. Refueling 3 Automatic Scram.

Event ReporI (LERI File INUREG-

,l D. Regulatory Restriction 40ther (Explain) 0161)

E-Operator Training & IJcense Examinailun

(

F. Administrative G. Operational Error (Explain)

Exhibit i. See Source ll-Other (Explaint

(

a

OPERATIONS

SUMMARY

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

MAJOR SAFETY RELATED MAINTENANCE During the month, major safety related maintenance included:

Borated Water Storage Tank Work consisted of adjusting the hanger on the eight (8) inch recire line, completing the twenty-four (24) inch spool re-placement, and filling the tank with borated water. Work on the twenty-four (24) inch spool piece progressed with the following work being performed.

1.

.Fitup of new spool and inspection by QC and Code Inspector.

2.

I!ot and Root weld pass.

3.

Information x-ray of hot and root pass weld.

4.

Weld repair of hot and root pass weld including in-formation x-ray.

5.

Weld out of welds.

6.

Final x-ray.

The final x-ray results showed no indication in the weld.

Filling of the BWST started at the completion of the twenty-four (24) inch spool job with about forty-eight (48) feet of water pumped into the tank during the month.

Rescles of inspections on the eight (8) inch recire flange and the twenty-four (24) inch spool showed no leaks were present.

Filling of tha BWST will progress into May.

Local Leak Rate Testing Testing progressed this month with satisfactory results.co date. Approximately 85 percent of the testing has been ccmpleted.

Emergenev Feedwater Check Valves Emergency Feedwater valves EF-V-12 A/B (check valves in EFW lines to OTSGs) were inspected. Minor repair work was required.

REFUELING IFFORMATION I2OUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit I 2.

Scheduled date for next refueling shutdown:

i

.I Unknown 3.

Scheduled date for restart following refueling:

Unknown 4.

Will refueling or resumption of operation thereafter 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 your Plant Safety Review Committee to determine whether any unreviewei 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, W ele 5 reload, was approved on 3-16-79.

5.

Scheduled date (s) for submitting proposed licensing action and supporting information:

N/A 6.

.Important licensing considerations associated with refueling, e.g. new

'or different fuel design or supplier, unreviewed design or performance.

pnalysis methods, significant changes in fuel design, new operating

}

procedures:

N/A 7.

The number of fGeT assemblies (a) ib~ths ~ core, and (b) in the spent fuel i

storage pool:

l (a) 177 (b) 208 l

8.

The present licensed spent fuel pool storage capacity and the size of i

any increase in licensed storage capacity that has been requested or is planned, in number of fue1~ assemblies:

The present licensed capacity is 752. There are no planned increases at this time, f

l 9.

The projected date of the last refue'.ing that can be discharged to the spent fuel pcol assuming the present licensed capacity:

I 1986 is the last refueling discharge which allows full core off-load p

capacity (177 fuel assemblies).

i

-n,