ML19305E371

Monthly Operating Rept for Mar 1980

ML19305E371
Person / Time
Site:	Three Mile Island
Issue date:	04/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19305E370	List: ML19305E369 ML19305E371
References
NUDOCS 8004230495
Download: ML19305E371 (5)

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I OPERATING DATA REPORT .

DOCKET NO. 50-289 DATE Anril 15, 1980 ,

COMPLETED BY D- C. Etchell  :

TELEPHONE (2151 921-6579 .

I OPERATING STATUS 1 1. Unit Name: Three M1e Tal nnd Nur 1 par Stntion. Unit I \ I

2. Reporting Period: March 1980 ,

3. Licensed Thermal Power (MWt):

2535 j 4. Nameplate Rating (Gross MWe): 871

5. Design Electrical Rating (Net MWe):

813

[

6. Maximum Dependable Capacity (Gross MWe): 840  :

7. Maximum Dependable Capacity (Net MWe): 776  ;

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

i 9. Power Level To Which Restricted. If Any (Net MWe): l

10. Reasons For Restrictions. If Any. i t

This Month Yr.-to-Date Cumulatise  ;

744, 2184. 48913.

11. Hours in Reporting Period 0.0 -

0.0 31731.6 [

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0.0 0.0 839.5

14. Hours Generator On-Line 0.0 -0.0 31180.9 -

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 j

16. Gross Thermal Energy Generated (MWH) O. O. 76531071.  !

17. Gross Electrical Energy Generated (MWH) O. ,

O. 25484330. -

18. Net Electrical Energy Generated (MWH)- O. O. 23840053.

19. Unit Service Factor 0.0 0.0 63.7 j

20. Unit Availability Factor 0.0 0.0 63.7  ;

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 61.9 '

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 59-.5 l

23. Unit Forced Outage Rate 100.0 100.0 24.9 l l 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):

i l

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

26. Units in Test Status IPrior o Commercial Operation): Forecast Achieved j .

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8004230 % <

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 m'IT TMI-l Pril 15, 1980 ,

DATE COMPLETED BY D. G. Mitchell TELEPHONE (215) 921-6579 MONTH March 1980 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (ywe. Net )

0 0 1 y7 2 0 gg 0 3 0 0 39 4 0 0 20 .

0 0 5 ;g 6 0 22 0.

7 0 0 23 8 0 0 24 9 0 0 25 10 0 0 26 11 0 0 27 12 0 0 28 13 0 29 0 14 0

30 0 15 0 33 0 16 0 s

INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt,

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DOCKET NO.

50-289 -

UNIT SilUTDOWNS AND POWER REDUCTIONS TMI-1 UNIT NAME DATE April 15: 19R0 COMPLETED BY D. G. Mitchell REPORT MONTH MARCII 1980 TELErilONE (215) 921-6579 w.

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5 4E 7

y Lic n5

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• ., Cause & Corrective E. -3 N* o- Daic s. E' : .c 5 a: Event u? 9"g Action to

$2 54 jd Report a <E 0 jO Prevent Recurrence 1 4/1/80 F 744 D 1 Regulatory Restraint Order 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructitms

~ S: Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Event Report (l.E R) File (NUREG-D Regulatory Restriction 4 Other (Explain) 0161i E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I Same Source (9/77) Il-Other (Explain) .

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MONTHLY OPERATING SUt1 MARY The unit was in cold shutdown the entire month by order of the NRC. Core cooling was performed using the A Decay Heat System.

IIAJOR SAFETY RELATED MAINTENANCE Inspection of the following Decay Heat System valves was performed:

DH-VSA/B BWST to decay heat pump suction isolation valves SA Disc required machining 5B Disc was turned for necessary adjustment DH-V14A/B BWST to decay heat pump suction check valves. Internals were replaced on both valves.

DH-V57A/B Relief valves between DH-V14A/B and DH-V5A/B. Relief ,

setpoints were adjusted.

While performing this maintenance the redundant decay heat string remained in service and the BWST was empty. Where applicable, blue checks were performed before returning valves to service.

Weld repair was completed on inter-granular stress corrosion cracking indication r B-100 (Sodium Thiosolfate tank to Building Spray Pump "B" piping). All final welds were X-rayed and found to be satisfactory.

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REFUELIN3 INFORMATION REQUEST

1. Na=e of Facility:

Three Mile Island Nuclear Station, Uni: 1

2. Scheduled date for next refueling shutdown: ,

Unknown .

3 Scheduled date for restart following refueling:  ;

Unknown  ;

14 . Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment?

If ansver is yes, in general, what vill these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deter: 2ine whether any unrevieved safety questions e.re associated with the core reload

~ (Ref. 10 CFR Section 50 59)7 If no such review has taken place, when is it scheduled?  ;

Amend =ent No. 50, Cycle 5 reload, was approved on 3-16-79

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5 Scheduled date(s) for sub=itting proposed licensing action and supporting information: >

N/A

6. Important licensing considerations associated with refueling, e.g. nev or different fuel design or supplier, unreviewed design or performance .

i analysis methods, significant changes in fuel design, new operating procedures: .

k N/A .

7 The number of fuel assemblies (a) in the core, and (b) in the spent fuel l

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 capac~ity:

• 1986 is the last refueling discharge which allows full core of'f-load capacity (177 fuel assemblies). , .;-- g .

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