ML19344B014

Monthly Operating Rept for Jul 1980

ML19344B014
Person / Time
Site:	Three Mile Island
Issue date:	08/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19344B012	List: ML19344B011 ML19344B014
References
NUDOCS 8008250374
Download: ML19344B014 (6)

Text

. .

OPERATING

SUMMARY

The unit was shutdown the entire month as a result of 3/28/79 p)g

\,, Unit-ll accident. Core cooling was provided by the Decay Heat i Removal System. l MAJOR SAFETY RELATED MAINTENANCE L

During the month of July, 1980, the Unit operated in the cold shutdown mode of operation with restart modification activities

, in progress. Tho major maintenance work performed during this nonth are outlined below:

( 1) Eddy Current Testing activities completed. I i 2) Pressurizer Relief Valve Testing completed.

3) Emergency Diesel Generator "B" maintenance activities.

4) Spent Fuel Cooling Loop "A" x-ray work.

. Eddy Current Testing activities were completed on OTSG-B this month with one (1) tube stabilized and plugged as a preventive measure only. The following work was performed:

a) Removal of lower primary manway.

)

b) Eddy Current Test results obtained.

c) f 0TSG tube stabilizing and plugging mockup training.

d) Stabilizing OTSG tube.

c) Plugging OTSG tube.

f) Reinstallation of'manways and handholes, g) Removal of clean rooms, and the storing of test equip-ment.

i Tube plugging / stabilization was performed with satisfactory re- ,

! sults.

The pressurizer code safety valve (RC-RV-1E) was tested and re-installed on the pressurizer. -The valve was tested and rea justed d to obtain the necessary pop pressure. A leak check of the valve indicated that internal repair work was required. The valve was disassembled under the direction of a factory representative and lapping of the disc and seat was performed with satisfactory re-i sults. After satisfactory results of the leak check and pop testing, the valve was reinstalled. Cold pipe measurement readings were taken prior to torquing the valve flanges. The initial pop test results and the cold pipe measurement readings are in the process of being evaluated.

Emergency Diesel Generator 1B (EG-Y-1B) was removed from service to l

inspect the generator bearing and clearances, PM calibratons of instruments, and corrective maintenance items. The generator bearing and bearing sleeve were sent to the manufacturer to be remachined.

The PM calibrations were performed with satisfactory results. The l

corrective maintenance items such as, oil leaks, gasket replace-ment on turbo charger, etc., are in progress and will be completed 7 next month.

1 I

W250 $f/f T-'-

1-- -*--'*----v' 'v'r '---i-r- eme----- w-7 wr-e-,-- w m v + = , "v e t*T--- * - m -O vr m e - "vm- --e +'g------* --v-w=-'- +-='-c*--t-v- f--**' - v,-

Operating Summary Page 2 The Spent Fuel System Loop "A" - welds (11) were x-rayed with the following results:

4 - no problems 2 - need to reevaluate UT report 5 - some type of repair work required At present time it is being determined what type of epair is required.

w M

DOCKET NO.

50-289 -

UNIT SilUT1) OWNS AND POWER REDUCTIONS 'I M I- I UNIT NAME i

. DATE Ancust 15 1980 COMPLETED BY D- C. Mircho11 REPORT MONT11 . July 1980

TELEPHONE (21'O 921-6579 I

No. Date g

.5 ?

3g 3

(

h .Y k jg&

Licensee Event

,g E

u?

h.'

o3 Cause & Corrective Action to

• $ #i0

$: j@g Repori #

f' Prevent Recurrence c5

• egu atory Restraint Order 1 7/1/80 F 744 D 1 1

i 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Sst.a; iled A Equipment Failure (Explain) 1 Manual for Preparation of Dat.:

B. Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LE R) File INURI G-D. Regulatory Restrietion 4-Oiher (Explain) 0161)

L-Operator Training & License Examination F Administrative 5 -

G-Oper,ational Error (Explain) Fshibit 1 Same Source Il-Ot her (E xplain) i e

.- = _ .

AVERAGE DAILY UNIT POWER LEVEL

- DOCKET NO. 50-289 g.lT THI-I DiTE August 15, 1980 COMPLETED BY D. G. Mitchell TELEPHONE (215) 921-6579 MONTH July 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL DiWe-Ned (Mwe. Net; 1 0 17 __

0 2 0 gg 0 3

0 i9 0 0 0 4 20 0 yg 0

5 6 0 22 0

7 0 23 0 ,

s b 24 0 9

0 0 25 0

10 26 0

II 27 0 12 0 0 28 13 29 0 0 0 14 30 15 0 31 0 16 0

~

l

_m- . _ _ _ _ _ _ _ -_ . - _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ _ _ _ . - - _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ ________ _ _ _ _ _ - _ _

OPERATI*iG DATA REPORT -

DOCKET NO. 50-289 DATE Aucust 15, 1980 COMPLETED BY D. C. Mitchell TELEPilONE (?l s) 921-6579 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

July 1980

2. Reporting Period: ,

2535 .

3. Licensed Thermal Power (MWt):

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 Any (Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr. to Date Cumulatise

11. Hours in Reporting Period 744 5111. sig40. ,

0,0 0.0 31731.8

12. Number Of Ilours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

. 0.0 0. 0 . 819.s 0.0 0.0 31180.9

14. Ilours Generator On-Line 0,o 0,0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Energy Generated (MWil)

O. O. 25464330.

17. Gross Electrical Energy Generated (MWil) A 30"J '

U* U*

18. Net Electrical Energy Generated (MWH) 0.0 0.0 60.1

19. Unit Service Factor U*U U*U 60.1

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 58.4 0.0 0.0 56.2

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 29.8

23. Unit Forced Outage Rate

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

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIA L OPER ATION

("/77 )

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?

4 s

~

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. l S. 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 fual 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 refueling 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).