ML19343A636

Monthly Operating Rept for Oct 1980

ML19343A636
Person / Time
Site:	Crane
Issue date:	11/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19343A635	List: ML19343A634 ML19343A636
References
NUDOCS 8011190273
Download: ML19343A636 (5)

Text

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AVFRAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 M -I UNIT DATE November 15, 1980*

COMPLETED BY D. G. Mitchell TELEPHONE (215) 921-6579 MONTH - October, 1980 DAY AVERAGE DAl Y PO ER LEVEL DAY AVERAGE DAILY POWER LEVEL

( MWe-Net)

I O

17 0

2 0

0

,3 3

0 0

39 4

0 0

20 5

0 0

,3 6

0 0

22 7

0 0

3 3

0 0

24 9

0 25 0

0 10

'6 0

'I 27 0

I 25 0

0 13 29 0

I4 30 0

15 0

31 0

16 0

80 2.1 y 9 0 273

OPERATING DATA REPORT DOCKET NO.

50-289 DATE November 15, 1980 COMPLETED BY D. C. Utchell TELEPHONE

(')19 921-6579 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

October, 1980

2. Reporting Period:

3. Licensed Thermal Power (MWt):

2535 871

4. Nameplate Rating (Gross MWe):

019

5. Design Electrical Rating (Net MWe):

840

6. Maximum Dependable Capacity (Gross MWe):

776

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions,if Any:

This Month Yr..to-Date Cumulatise

.745, 7320.

54049.

II. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.8 0.0 0.0 839.5

13. Reactor Resene Shutdown Hours 0.0 0.0 31180,9

14. Hours Generator On.1ine 0.0 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Grou Thermal Energy Generated (MWH)

O.

O.

23464330.

17. Grou Electrical Energy Generated (MWH)

U.

u.

zJs4uua3.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 57.7

19. Unit Service Factor 57.7 UU UU

20. Unit Asailability Factor 0.0 0.0 56.1

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 53,9

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 33.2

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Nest 6 Months (Type. Date,and Duration of Each t:

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

26. Unit 5 in Test Status tPrior o Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION gol q l

1

s 50-289 UNIT SIlUTDOWNS AND FOWER REDUCTIONS DOCKET NO.

UNI T N AME

'I M l-1 DATE Fvenber 15, 1980 COMPLETED BY D. G. Pf1 echo 11 REPORT MONT14 October 1ELEPHONE (21S) 921-6519

~.

3.5 E

c 5".

$"?

No.

Date E.

S _5 Cause & Corrective Ey CC" "

? ;e Event l?

Action to gV 3.2 0

5 Present Recurrente j d5 j Report er mu OO E

6 9

• W Rer,ulatory Restraint Order Y4.

1 10-1-80 F

745 D

1 pq OM

@E9 tenR -

C'-2 CO:

(B L

• (

I 2

3 4

F: Forced -

Reason:.

Method:

Eshibit G Instructions S: St heduled A-Equipment Failure (Esplain) 14tanual for Preparation of Data B-Maintenance of Test 2-M.mual Sesam.

Entry Sheets for 1.icemcc C Refueling 3-Automatic Scram.

Event Report II.I R) File INtf RFG-D Regulatory Restriction 4 Oher (Esplain) 0161)

IzOperator Training & Ucense f samination F Administrative 5

G Operglional 1:rror il splain t I shibit I - Sime Source It Other (r spbini

~

OPERATING

SUMMARY

The Unit was shutdown the entire month as a result of the 3/28/79 Unit 2 accident. Core cooling was provided by the Decay Heat Re-moval System.

On October 24,.the Reactor Coolant Systen was partially drained to permit the repair of the A-0TSG leaking manway and handhole covers, and to install internals in eight (8) High Pressure Injection Check Valves. The system was partially drained at the end of the report period and work was in progress. The results of the work will be reported in the November Monthly Operating Report.

MAJOR SAFETY RELATED MAINTENANCE During the month of October, Ur.it 1 operated in the cold shutdown condition with restart modifications being performed. The following major maintenance work was performed.

1) Spent Fuel Weld #95 repair.

2) Spent Fuel Weld #182 repair.

3) Make Up Pump Discharge Check Valves MU-V-73 A/B.

Spent Fuel Weld #95, located between the outlet of the Spent Fuel Cooler "B" and Spent Fuel Pool "B", was repaired by grinding out the indicated bad weld and rewelding. The final x-ray was performed with satisfactory results. Spent Fuel Weld #182 is located between Spent Fuel Pool "B" and Spent Fuel Pump "B".

The repair work asso-ciated with this weld was performed in the following sequence.

i

1) section of pipe removed

2) pipe end welds prepped

3) ~cleanlines1 and ficup inspections

4) hot and root weld passes 5) information x-ray

6) final welding

7) final x-ray Both welds were performed with the Fuel Pool level lowered. After the two (2) weld indications were repaired, a flush and operatio'nal leak check was performed with satisfactory results. After all work was performed, the Fuel Pool level was returned to normal.

Two (2) of the Make Up Pump Discharge Check Valves (MU-V-73 A/B) were repaired by installing new internals. The valves were re-aasembled and are now available for use. This work was performed to replace the valve internals with a modified design to solve a problem identified in LER #80-03. As reported in TLL 075, dated February 20, 1980, inspection of the valve internals had revealed loose hold down devices. A followup report to LER #80-03 will be forwarded describing the cause of the loose parts.

~.

e REFUELING INFORMATION 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 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 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.

1 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 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 i

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 refueling that can be disenarged to the spent fuel pool assuming the present licensed capacity:

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

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