ML20066C548

Monthly Operating Rept for Oct 1981

ML20066C548
Person / Time
Site:	Three Mile Island
Issue date:	11/15/1981
From:	Smyth C GENERAL PUBLIC UTILITIES CORP., METROPOLITAN EDISON CO.
To:
Shared Package
ML20066C547	List: ML20066C545 ML20066C548
References
NUDOCS 8211100047
Download: ML20066C548 (5)

Text

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OPERATING DATA REPORT

• DOCKET NO. 50-289 DATE . November 15, 1981-COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS Three Mile Island Nuclear Station _ Unit I

1. Unit Name:

2. Reporting Period: October. 1981 2535 .

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gros MWe):

819

) 5. Design Electrical Rating (Net MWe):

840

6. Maximum Dependable Capacity (Gross MWe):

776

7. Maximum Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings (Items Number 3 Thmugh 7) Since I.ast Report. Give Reasons:

i

9. Power 1.svel To Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions.lf Any:

This Month Yr to.Date Cumulative 745. 7296. 62809.

I1. Hours in Reportag Period 31731.8 0.0 0.0

12. Number Of Hours Reactor Was Critica! 0.0 839.5 0.0

13. ReactM Reserve Shutdown Hours 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. Gmss Thermal Energy Generated (MWH)

D. O. 23464330.

17. Gross Electrical Energy Genersted (MWH) u. U. 4;devusa.

18. Net Electrical Energy Generated (MWH) 0.0 49,6 J 0.0 l 19. Unit Service Factor 49.6

20. Unit Amilability Factor 0.0 4g,3

- 0.0

21. Unit Capacity Factor (Using MDC Net) 0.0 46.3 0.0

22. Unit Capacity Factor (Using DER Net) 100.0 43.8 300.0

23. Unit Forced Outage Rate *

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

l

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

Forecast Achieved

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

l INITIAL CRIT!CALITY ,

INITIAL ELECTRICITY N COMMERCIAL OPERATION

( 4 77 8211100047 811113 PDR ADOCK 05000289 s.

R PDR

AVERAGE D AILY UNIT PdWER LEVEL

• DOCKET NO. 289 IMI-I WT DATE November 15, 1981; COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 October, 1981 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (gwe. Net)

I 0 37 ,,_

0 2 0 3g 0 3 0 39 0

0 0 4 20 0 0 5 23 6 0 ,, 0 7 0 23 0

8 0 2 0

0 0 9 25 0

10 26 II 27 0 12 0 28 0 0 0 13 29 14 0 30 0 '

15 0 33 o 16 0 ,,

i

, p}a*-

m .

t .

UNIT SilUTDOWNS AND POWER REDUCT10NS IX)CKET NO. 50-289 .'

! UNIT NAME TML-1 l DATF. November 15,1981 l

COMPLETED Ry C. W. Smyth -.

I REPORT MONT11 October TELErtIONE f7171 948-8551 l

i T -

.$E Licensee E -t, Cause A Corrective -

No. Date H(

7. g "h .}Yf gec Event :T di'0 k%l 0

Action to

$E E j dij g Report

• Prevent Recurrence , ,

a - , : [i .. l>

?,[:' i ?

1 10/1/81 F 745 D 1 Regulatory Restrairit Order;.I ,

9 i

I l

r' I 2 3 4 F: Forced Reason: Method: Exhibit G instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparatism of Data .

B. Maintenance of Test 2. Manual Scram. Entry Sheets for Licensee

C.Refuellreg 3 Atttomatic Scram. Event ReporI (LE R) File (NUREG.

I D. Regulatory Restriction 4 Other (Explain) 0161)

' E Operator Training A License Examination .

F. Administrative 5 l G. Operational Error (Explain) Exhibit I Same Source

. II-Other (Explain) a

. OPERATING

SUMMARY

Th2 unit wzz in cold chutdown the cntira;rcp;rt p;riod' by crdir of the NRC. Core cooling was provided by the Decay Heat Removal System.

~

- ~ Y MAJOR SAFETY RELATED MAINTENANCE Reactor Coolant Pump,,"C" (RC-P-lC) would not rotate by hand. The

' Reactor Coolant System was partially drained to permit pump to motor uncoupling. Measurements with the oil lift system in service were performed to ensure proper lif t operations. These measurements were taken with satisfactory results. The pump / motor were un-coupled and attempts were made to rotate the motor. The motor would not rotate by hand. Inspections of the motor oil system and motor bearings were performed. A broken oil fitting to the #6 shoe on the upper bearing was replaced and the oil system returned to normal operation. A rotation check on the motor was performed by

~

hand with satisfactory results. Alignment .! the pump to motor is in progress.

Cavitating venturies were installed in the Emergency Feedwater System (Restart Modification LM-13) . The following work was performed.

A. The system was drained and isolated.

B. The piping was cut and prepped for installation of venturies.

C. Fitup/ Welding. ,

D. Welding inspections performed with satisf actory results. t Testing of the cavitating venturies will be performed at a later time.

e N..

t - e =

- REFUELING INFORMATION REOUEST .

1. Name of Facility: .

7:ThreeMileIslandhuklear_ Station,UnitI;,_ . f- , . - _ _ . ,

, 2. ,

. . ~..... .-.

2. Scheduled date for next refueling shutdown: ,

Unknown -

~i:~

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 Comittee to detemine 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.

t

5. Scheduled date (s) for submitting proposed licensing action and supporting inf oriniition:

N/A

6. Important 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 cere, and (b) in the spent fuel '

storage pool:

(a) 177 i ' " '

l (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. ,

L 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 capacity (177 fuel assemblies).

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