ML19296C218
| ML19296C218 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/15/1980 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19296C213 | List: |
| References | |
| NUDOCS 8002250401 | |
| Download: ML19296C218 (5) | |
Text
.
OPERATIONS SUrtf1ARY Unit #1 remains in cold shutdown with core cooling being provided by the "A"
Decay Heat Removal System.
MAJOR SAFETY RELATED ftAINTEllAflCE Work on modifications to permit restart continued. Pipe indications D-315 and M-1 were repaired. Repair included removal of affected sections of pipe and installation of dutchmen. All welds passed X-ray examinations.
8002250 9'4/
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Urr.RATISG DATA REFChT uocr.et 50.
50-284 Date 2/15/80 Cc:npleted By D_
- c. uttekn11 OPERATI?!G STATUS Telephone (214 021-.4 fo 1.
Unit Nc=c: Three Mile Island !!uelear Station 2.
Reporting Period: Januarv 1980 3
Licensed Thermal Power (!Gt):
2539 k.
Nameplate Rating (Gross K4e):
871 5
Design Electrical Rating (Net M'Je):
819 6.
Max. Dependable Capacity (Gross !Ge): 8LO 7
Max. Dependable Capacity (Net !Ge):
776 8.
If Changes occur in Capacity Ratings (Ite=s No. 3 through 7) Since Last Report, Give Reasons:
9 Power Level to which Restricted. If Any (Net !Ge):
10.
Reasons for Restrictions, If Any:
y.-
Month Yr. to date Cu=ulative 744-744.
47473.,
11.
Hours in Reporting Period 12.
No. of Hours Reactor was Critical O.0 0.0 31731.8 0.0 0.0 839.5 13.
Reactor Reserve Shutdown Hours l
lb. Hours Generator On-Line 0.0 0.0
'1130.9 15 Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Ther=al Energy Generated (16"d)
O.
O.
76531071.
17.
Gross Elect. Energy Generated (K4H)
O.
O.
2548h330.
- 18. Net Electrical Energy Generated (K4H)
O.
O.
23840053.
19 Unit Service Factor 0.0 0.0 65.7 -
0.0 0.0 65.7 20.
Unit Availability Factor 21.
Unit Capacity Factor (Using MDC Net) 0.0 0.0 63.7 22.
Unit Capacity Factor (Using DER Net) 0.0 0.0 61.3 100.0 100.0 22/2
- 23. Unit Forced Outage Rate 2h.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
i 25 If Shut Down at End of Report Period, Estimated Date of Startup; 26.
Units In Test Status (Prior to Co==ercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY
~
INITIAL ELECTRICITY CC!GERC."AL OPERATION A
e e.'
.b a < e, m A e
$w g h me e.
-+
I-
_1 c 3-
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a-- + =_ __ gle_ _
AVERAGE DAILY UITIT PO*JER LEVEL Docket No.10-280 Unit 1
Date 2/15/80 Cc=pleted By D. G. Mitchell Telephone (215) 021-6570 MONTH Januarv DAY AVERAGE DAILY PO'JER LEVEL DAY AVERAGE DAILY PO'4ER LEVEL
(!Ge-Net)
(!Ne-Net) 0 1
0 17 2
0 18 0
0 3
0 19 h
o 20 0
5 0
21 0
6 0
22 0
0 7
0 23 8
0 2h 0
0 0
25 9
10 0
26 0
0 11 0
27 12 0
28 0
0 13 0
29 0
14 0
30 0
15 0
31 16
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gd G
aulme*'
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$0-289 I
Docket No.
UNIT SHUTDOWNS AND PCVER REDUCTIONS Unit Na::e TMI-I REPORT MONTH JANUARY Date Feb ru ary 15. 1980 Completed By D. C. Mitchell Telephone (215) 921-6579___
No.
Date Type m
System Component Cause and Corrective
.I, l
Code 4 Code 5 Action to gg og gy o
e Prevent Recurrence 43 ggo tg, g 55E 8Oj i
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esa dA=
i 1
1 1/1/80 F
744 D
1 Regulatory Restraint Order
,8
.)
,J 1
- 1
..I s
I s
2 eason:
3
" Exhibit G - Instructions I: Forted F
R rtethod:
f r Preparation of Data S: Scheduled A-Equipment Failure (Explain) 14tanual B-Maintenance or Test 241anual Scram.
Event Report (LER) File a
C-Refueling 3-Automatic Scram.
j D-Regulatory Restriction 14-Other (Explain) 3 4
~
E-Operator Training & Licensee Examination F-Administrative G-Operational Error (Explain)
Exhibit 1 - Some Source H-Other (Explain) d-
,'l
.it
REFUELING INFO?m TION REOUEST f
I
\\
!l l
/
1.
Nase of Facility:
a u
..ile Island Hucle.u Oca:icn, W.: 1 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
Unknown Will refueling or resumption of operation thereafter require a technical h.
specification change or other license amendment?
If answer is yes, in general, what vill these be?
If answer is no, has the reloaa fuel design and core configuration been reviewed by your Plant Safety Review Co==ittee to determine whether any unreviewed safety questions are associated with the core reload (Re.?. 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
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Scheduled date(s) for submitting proposed licensing action and supporting 5
information:
N/A Important licensing considerations associated with refueling, e.g. new 6.
or different fuel design or supplier, unreviewed design or perfor=ance analynis methods, significant changes in fuel design, new operating procedures:
N/A The number of fuel assemblies (a) in the core, and (b) in the spent fuel 7
storage pool:
(a) 177 (b) 208 The present licensed spent fuel pool storage capacity and the size of 8m 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.
The projected date of the last refueling that can be discharged to the spent 9
fuel pool assusing the present licensed capacity:
1986 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
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