ML19262C008
| ML19262C008 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1980 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19262C005 | List: |
| References | |
| NUDOCS 8001220417 | |
| Download: ML19262C008 (5) | |
Text
'.
OPERATING
SUMMARY
Unit #1 remains in cold shutdown with the "B" Decay Heat Removal System providing core cooling.
MAJOR SAFETY RELATED MAINTENANCE With the plant operating in the cold shutdown condition, DR-P-lB developed high vibration. The backup pump (DR-P-1 A) was placed in operation to allow repairs to be performed on the "A" pump. The following maintenance work was performed:
1.
Motor uncoupled from pump.
2.
Motor removed for access to pump.
3.
Motor bearings replaced and rotor balanced.
4.
Pump disassembled; tolerance readings taken 5.
New shift tolerance readings taken.
6.
Pump assembled; tolerance readings taken.
7.
Motor installed.
8.
Pump to motor alignment checks taken.
9.
Pump to motor coupled.
10.
IRD readings and ISI test performed.
The tests were performed with satisfactory results.
019,20
a 1
a.
Date 1/15]80 Cc=pleted By D. C. Mitchs11 OPERATING STATUS Telephene (215) 091 47o 1.
Unit Ne=e: Three Mile Island Nuclear Station Reporting Pericd:
3 Licensed Ther=al Power (Wt):
2535 k.
Na=eplate Rating (Gross !Ge):
871 5
Design Electrical Rating (Net MWe):
819 6.
Max. Dependable Capacity (Gross !Ge): 8ho i
7 Max. Dependable Capacity (Let MWe):
776 8.
If Changes Occur in Capacity Ratings (Ite=s No. 3 thrcugh 7) Since Last Report, Give Reasons:
9 Pcver Level to which Restricted. If Any (Net ige):
10.
Reasons for Restrictions, If Any:
/'__
Month Yr. to date Cu=ulative
- 744, 8760.
46729. -
11.
Ecurs in Reporting Period 12.
Zio, of Ecurs Reacter was Critical 0.0 1128.0 31731.8 0.0 0.0 839.5 13.
Reactor Reserve Shutdown Hours 14.
Hours Generator On-Line 0.0 1128.0 311S0.9 15 Unit Reserve Shutdevn Ecurs 0.0 0.0 0.0 16.
Gross Ther=al Energy Generated (IGH)
O.
2828kh8.
76531071.
17 Gross Elect. Energy Generated (!GH) 0.
94599o.
25 hah 3?0.
-3763.
848038.
23840053.
18.
Net Electrical Energy Generated (!OTH) 19 Unit Service Factor 0.0 12.9 66.7 66.7 0.0 12.o 20.
Unit Availability Facter 21.
Unit Capacity Factor (Using MDC Net)
-0 7 12.5 64.'
22.
Unit Capacity Factor (Using DER Net)
-0.6 11.8 62.3
- 20. 7 --
100.0 85,4 23.
Unit Forced Outage Rate 2k.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duratica of Each):
25 If Shut Dcun at End of Report Period, Estimated Date of Startup;
- 26. Units In Test Status (Prior to Cc==ercial Operation):
FORECAST ACHIE7ED INITIAL CRITICALITY INITIAL ELECTRICITY COM:ERCIAL OPERATION
.,... :3.T:2 2
3 1785.285 e -.* - e 5% = L = =* =
._A m _ _
-. ii3%, ~
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AVERAGE DAILY UNIT POWER LEVEL Docket No.10-289 Unit 1
Date 1/15/80 Completed By Telephone (215) 921-6570 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net)
Q&e-Net)
-5
-5 1
-5
-5 2
g
-5 3
19 l
-5
-6 h
20
-5
-6' 5
-5
-5 6
22
-5
-5 7
23
-5 8
~
24
-5
-5 5
-5
-5 30 26
-5
-5 g
~
-5 12 28
-5 13 29 Ik
~
30
-5 15 31
-5 16 L785.286.-
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h52$h'h !&a.. _Y r
f UNIT SIIUTDOWNS AND POWER REDUCTIONS Docket No.
50-289 I
nh Name ]4 i
REPORT MONTH DECEMBER Date h6n,rv 15. 1980_
j g ',
Completed By D.
G. Mitchell 4
Telephone (215) 921-6579 1
f
+'
l S
{
System Component Cause and Corrective
. !]
No.
Date Type cv g
Code h Code 3 Action to g
gg g
og gg Prevent Recurrence j
43 g
g g,o g,y
$$U 0SY
- k k,
eme und
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.j i
1 12/1/79 F
744 D
1 Regulatory Reasons due to TMI-II g
l Accident g
Ln I
s.- )3 O,..
.' t
^#
,n
'L f
i 6
l 2 eason:
3
" U - I""*"" " ""
I: Forced R
Method:
F f r Preparation of Data y
S: Scheduled A-Equipment Failure (Explain}
1-Manu al Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram.
ePort (LER) File p
ven C-Re fueling 3-Automatic Scram.
~
T' j
D-Regulatory Restriction 14-Other (Explain) t, 4
E-Operator Training & Licensee Examination F-Administrative 5 Exhibit 1 - Same Source
.(
G-Operational Error (Explain)
-/I H-Ot,her (Explain}
9 w
()
REFUELING INFORMATION REQUEST 1.
Na=e of Facility:
Three Mile Island Huclear hatic:., Uni: 1 2.
Scheduled date for next refueling shutdown:
Unknown Scheduled date for restart following refueling:
3 Unk:2cvn Will refueling or resu=ption of operation thereafter require a technical 16 specification change or other license amend =ent?
If answer $s yes, in geners.1, what vill these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cc==ittee to dete mine whether any unreviewed safety questions are associated with the core reload (3ef. 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
A=end=ent No. 50, Cycle 5 reload, was approved on 3-16-79 Scheduled date(s) for submitting proposed licensing action and supporting 5
infomation:
3/A I=portant licensing censiderations associated with refueling, e.g. new 6.
or different fuel design or supplier, unreviewed design or perforrance analysis =ethods, significant changes in fuel design, new operating procedures:
s/A The nu=ber 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 8.
any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
There are no planned i:.ereases The present licensed capacity is 752.
at this time.
The projected date of the last refueling that can be discharged to the spent 9
fuel pool assu=ing the present licensed capacity:
1986 is the '.. refueling discharge which allows full core off-load capacity (177 fuel asse=blies).
I'785 288..
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