ML19344B546

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Monthly Operating Rept for Sept 1980
ML19344B546
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 10/15/1980
From: Mitchell D
METROPOLITAN EDISON CO.
To:
Shared Package
ML19344B543 List:
References
NUDOCS 8010210431
Download: ML19344B546 (5)


Text

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AVER AGE DAILY UNIT POWER LEVEL e

. DOCKET NO.. 50-289 I

3.IT TMI-I i

DATE October 15. 1980 CO%fPLETED BY D. G. ' ?titchell'-

TELEPHONE (717) 948-8553 MONTH September 1980-DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Neti iMWe Net) i i O ,

37 _

0 2 0 g3 0 3 0 - 39 0

4- 0 20 0
  • 5 0  ::
6- 0 22 0 i

7 0 23 0 8 0 2.g 0 9

0 0 25 I

10 0 26

^0 l 11 27 0 12 0 o 33 13 29 0 14 0 0 30 15 0 3, o 16 0 i

8010210 4 -- _ . , . . . _ -_ . . . ,. _ . , _ _ __

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OPERATLNG DATA REPORT DOCKET NO. 50-289 DATE October 15, 1980 COMPLETED BY D. G._Mitchell TELEPHONE (717) 948-8553 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name: ,
2. Reporting Period: September 1980 2535
3. Licensed Thermal Power (MWt):
4. Nameplate Rating (Gross MWe):

871 019

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. Give Reasons:
9. Power Level To which Restricted,If Any (Net MWe):
10. Reasons For Restrictions.If Any:-

j

  • This Month Yr..to.Date Cumularise I 11. Hours In Reporting Period 720. 6575. s1104.
12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.8
13. Reactor Reserve Shutdown Hours
0. O. 839.5 0.0 0.0 31180.9
14. Hours Generator On.Line U*U 0.0 0.0
15. Unit Reserve Shutdown Hours
16. Gross Thermal Energy Generated (MWH) 0.0 0.0 76531071.

O. O. 25464330.

17. Gross Electrical Energy Generated (MWH)
u. u. zJd40us).
18. Net Electrical Energy Generated (MWH) 0.0 0.0 58.5
19. Unit Service Factor U*U U*U 58.5
20. Unit Availability Factor
21. Unit Capacity Factor iUsing MDC Net) 0.0 0.0 56.8
22. Unit Capacity Fcetor (Using DER Net) 0.0 0.0 54.6
23. Unit Forced Outage Rate 100.0 100.0 u,1
24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Destion of Each):

I

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

'26. Units In Test Status (Prior to Commercial Operation): Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION I l

10/77)

DOCKET NO.

50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS ,I.H L-1 UNIT NAME DATE 10-15-80 REPORT MONTH September COMPLETED RY D. C. Mitchell.

TELEPHONE (717) 948d553 1 ._

, .3 ? 3g hY Licensee ,E*, f% Cause A Corrective

' No. Date g 3g jg5 Event -7 g o.3 Action to

  • $5 Report *r mv 5L Prevent Reuntence c2 35t

< u b

    1. " #7 " 8 "" " '#

I 9-1-80 F 720 D 1 1 2 3 4 F: Fort ed Reason: Metimd: Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C Refueling 3-Automatie Scram. Event Repori t1.ERI File INURI G-D-Regulatory Restriction 4-Oiher ( Explain) 0161)

E-Operator Training & License INamination F Administrative 5 G-Opergtional I.iror (INplain) E xhibit I - Same Source Il-Olher ( E xplain)

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OPERATING SU!e!ARY

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The' Unit was shutdown the entire month as a result of 3/28/79,  ?

2 Unit 2 accident. Core cooling was provided by the' Decay Heat Removal System. ,

MAJOR SAFETY RELATED MAINTENANCE.

While'.thel Unit was in cold shutdown. condition, the following I

major > maintenance _. item was performed.

Diesel [ Generator "A (EG-Y-1A) repair and; preventive maintenance! items were completed. This included.in-spection 'and repair -of generator bearing, compressor

' overhaul,-instrument calibration, oil leak repairs, and exhaust manifold leak-repcirs. All associated .

work was performed with satisfactc.y: test results l and wh'ile Emergency Diesel Generator "B remained l

operable. .;

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REFUELING'INFORMATION REOUEST

.l .' 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 auch review has taken place, when is it scheduled?

l Amendment No. 50, Cycle 5 reload, was approved on 3-16-79.

l

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

! N/A l 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 .

l' procedures:

l N/A 1

l 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 numberfof fuel assemblies:

'The present' licensed capacity is>752. There are no planned increases at this time.

9. The projected ~date ofLthe last refueling that can be discharged to the spent ufuel. pool' assuming the present licensed capacity:

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

l 4  !