ML19211A648
| ML19211A648 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/17/1979 |
| From: | Stair J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19211A647 | List: |
| References | |
| NUDOCS 7912200368 | |
| Download: ML19211A648 (5) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No.10-280 Unit 1
Date December 17, 1979 Completed By Telephone (215) 921-6579 DA'?
AVERAGE DAILY POWER LE'<EL DAY AVERAGE DAILY POWER LEVEL OMe-Net)
ONe-Net)
-5 1
-5 17 2
-4 18
-5
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3
- - 3
-5 19 h
-5
-5 20 5
-5
-5 21 6
-5
-5 22 7
-5
-5 23 8
-5 24
-5 n
-5
-5 gg
-5
-5 lo 26 n
-5
-5 27 12
-5
-5 28 13
-5
-5 29 14
-5
-5 30 15
-5
-5 31 16
-5 1634 014
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OPERATING DATA REPORT Docxet ho.
50-289 Date December 17, 1979 Completed By J.
R.
Stair OPEF.ATING STATUS Telephone (215) 021_As70 1.
Unit Name: Three Mile Island Nuclear Station 2.
F.eporting Period: November e
3.
Licensed Thermal Power (MWt):
2535 k.
Nameplate Rating (Gross MRe):
871 5
Design Electrical Rating (Net MWe):
819 6.
Max. Dependable Capacity (Gross Mwe): 8h0 7
Max. Dependable Capacity (Net MWe):
776 8.
If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:
9 Power Level to which Restricted. If Any (Net MWe):
10.
Reasons for Restrictions, If Any:
?
w.
Month Yr. to date Cumulative 11.
Ecurs in Reporting Period 720.
8016.
- 46705, 12.
No. of Hours Reactor was Critical 0.0 1128.0 31731.8 13.
Reactor Reserve Shutdown Hours 0.0 0.0 838.5 14.
Hours Generator On-Line 0.0 1128.0 31130.9 15 Unit Reserve Shutdevn Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated UGH) 0.
2828hh8.
76531071.
17 Gross Elect. Energ7 Generated (!GH)
O.
94599o.
25h8h330.
- 18. Net Electrical Energy Generated (IGH)
-3510.
848301.
23840316.
19 Unit Service Factor 0.0 14.1 66.8 20.
Unit Availability Factor 0.0 14.1 66.8 _
21.
Unit Capacity Factor (Using MDC Net)
-0.6 13.6 64.7 22.
Unit Capacity Factor (Using DER Net)
-0.6 12.9 6'3 23.
Unit Forced Outage Rate 100.0 85.4 2,.
7" 2h.
Shutdowns Scheduled Over Next 6 Months (Type, Date, anu Duratica of Each):
i 25 If Shut Down at End of Report Period, Estimated Date of Startup;
- 26. Units In Test Status (Prior to Cc=mercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMERCIAL OPERATION t
$~
1634:015 e
e e.
e ee==ee%
a.em--mm e
-he m e m-em e,
e
UNIT SHUTDOWNS AND POWER' REDUCTIONS Docket No.
50-289 Unit Name TMI-1 REPORT MONTH November Date Dece'mber 17. 1979 Completed By J,'R.
Stair Telephone (215) 921-6579 l
No.
Date Type cu System Component Cause and Corrective Code 4 Code 5 Action to j
gg og gg n
g ggo g,g Prevent Recurrence
'j
- $8 80j 5
MM=
1 1
11 / 1 / 7 9 F
720 D
1
.Regelatory Restraint Order j
1 t
1
.j d
u i
1 n.
2 eason:
3 mn " - Ine E ' S,,5 i
I: Forced F
R Methods S: Scheduled A-Equipment Failure (Explain)
P*
"~
14fanu al B-Maintenance or Tc':t 24fanual Scram.
Event. m t (LER, -
j C-Refueling 3-Automatic Scram.
D-Regulatory Restriction h-Other (Explain)
E-Operator Training & Licensee Examination F-Administrative 1
5 Exhibit 1 - Srme Scurce G-Operational Error (Explain) g H-Other (Explain}
p<
Ch JI[j 4.,
OPERATING
SUMMARY
Unit I remained in cold' shutdown with the "B" Decay Heat Removal System providing core cooling.
MAJOR SAFETY RELATED MAINTENANCE Spent Fuel piping indications #13, 14, and 22 were repaired satisfactorily.
The repair included removal of the indication, weld prep of the pipe and installation of a spool piece or dutchmen (included fit up, welding).
The repairs were performed without adversely affecting the cooling of the spent fuel pools.
i634 017
REFUELING INF0FMATION REQUEST _
1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 Scheduled date for next refueling shutdown:
2.
Unknown Scheduled F. ate for restart following refueling:
3 Unknown Will refueling or resu=ption of operation thereafter require a technical 4.
specification change or other license amendment?
If answer 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 Consittee 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?
A=endnent No. 50, Cycle 5 reload, was approved on 3-16-79 Scheduled date(s) for submitting proposed licensing action and suppcrting 5
infor=ation:
N/A Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfor=ance 6.
analysis methods, significant changes in fuel design, new operating procedures:
N/A The nunber of fuel assemblies (a) in the core, and (b) in the spent fuel T.
storage pool:
(a) 177 1634 018 (b) 208 The present licensed spent fuel pool storage capaci 8.
planned, in number of fuel assemblies:
There are no planned increases The present licensed capacity is 752.
at this tine.
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 allovs full core off-load capacity (177 fuel assemblies).
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