ML20087G585
| ML20087G585 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/29/1984 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 5211-84-2071, NUDOCS 8403200068 | |
| Download: ML20087G585 (6) | |
Text
.
a OPERATING DATA REPORT DATE Mnrch it toga COMPLETED BY c. u. smv. eh
~ ~- ~~ O P E RAT I NG ' S TAT US - ~~ ~ -~ ~ ~
NOTES 77 UNIT NAME':
THREE MILE 75 LAND UNITT
'2 REPORTING PERIOD:
FEBRUARY,1984
- 3. LICENSED THERMAL POWER (MWT):
2535.
~47MAMEPLATE RATING ~(GROSS MWE)T 8717
~
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
824.
~7.-~ MAXIMUM' DEPENDABLE CAPACITY ~(NET MWE):
7767
~
~
- 8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
' _10 REASONS FOR RESTRICTIONS, IF ANY:
k'
'A THIS MONTH YR-TO-DATE CUMMULATIVE 117 HOURS ~IN REPORTING" PERIOD 696.
14~40 83233---
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 839.5-
- 14. HOURS GENERATOR ON-LINE
^ '
- - ~ ~ ~
070~
0.~0 - - 3118 0. 9 ',
15 UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0:
- 16. GROSS THERMAL ENERGY GENERATED (MWIT)
O.
O.
76531071.
17 GROSS ELECTRICAL ENERGY GENERATED (MWH)'- - - 0
~~~07~
'254843307, 18 NET ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
23840053.i
- 19. UNIT SERVICE FACTOR 0.0 0.0 37.5!
. 2 0.~ ~ UNIT AVAILABILITY FACTOR ~ ~--^-
1 70 070
-~3775"
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 36.6 2 2 '. UNIT CAPACITY FACTOR (USING DER NET) 0.0.
0.0 35.0
- 23.~ UNIT FORCED OUTAGE RATE ~~ - -
10070 10070 5970~
24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS'(TYPE, DATC TAND DURATION ~OF EACH
~
~ - ~
l
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE.OF STARTUP:
-1 i -
N"" ^
' 229eH. _ _ _.. M A 8403200068 B40
. t
+_
AVERAGE DAILY UNIT POWER LEVEL p--
DOCKET NO.
50-289 UNIT TMI-1 DATE March IL 1984 COMPLETED BY C. W. Smyth l TELEPHONE (717) 948-855l MONTH:
FEBRUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
-- ---(MWE-NET)
(MWE-NET) 1 0
17 0
2 0
18 0.
. 3
____._.o,...____ _ _.._ ____ _ 19
._ _.0. _
4 0
20 0
5 0
21 0
- 6
-0.-
-- -22 0.
7 0
23 0
8 0
24 0
9-O.
25 n_
L 10 0.
26 0
11 0
27 0,
12 0
28
^ _
13 0,
29 0,
14 0
30 N/A
. _. ~ ~~ ~ 15
'--~~~ ~~ 0. ".- - -
31 N/A 16 0
l i
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50-289
'JNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME TML-I DATE March. 15 1984 COMPLETED BY. C. W. Smyth REPORT MONTH March 1984
. /717T oAn-9;si TELEPHONE r.
'S 5
c e
ci Cause & Corrective k"".
1 5
E 75b No.
Date x
e:
2 g a:
Event uT Action to
$5 5
j di j Report a
<5 0 Prevent Recerrence d
- E" 1
84/02/01 F
744 D
1 N/A ZZ ZZZZZZ 1
1 2
3 4
f: Forced Reason:
Method:
Exhibit (.
..st ructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Pr paration of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E. Operator Training & License Examination F-Administrative 5
G-Operatg',nal Error (Explain)
Exhibit I Same Source Il-Other (Explain)
L
c?ERATING
SUMMARY
1 The unit was shutdown the entire month by order of the NRC. Core coling was pro-vided by the Decay Heat Removal System. The primary has been dep^ressurized and g
temperature has been maintained at about 130 F.
The secondary plant has been in full wet layup. Vacuum was maintained on the secondary the first week of the month.
The Reactor Coolant System was partially drained to between 11 and 18 inches above the cold leg center line to prepare for repairs to Reactor Coolant Pump 1B.
MAJOR SAFETY RELATED MAINTENANCE Reactor Coolant Pump (RCP-1B )
Because of high vibrations, RCP-1B was removed from service in the previous month.
After a thorough review and analysis of the pump and motor, it appears probable that the pump shaft is cracked.
The pump shaft and impeller will be replaced from spares in the warehouse.
The motor to pump spool piece was removed and alignment checks were performed and ultrasonic inspections of the pump shaf t were taken. These in-spections resulted in the decision to disassemble the pump.
Structural interferences to motor and pump internals removal were removed, motor electrical leads were lif te'd and the motor was removed and placed on its storage stand. Motor preventive mainten-ance is in progress while the pump is being disassembled.
This work will continue into March.
The cause of high vibration is still unknown.
Depending on the outcome of the inspec-tions of RCP-1B, the three remaining pumps will be inspected as necessary.
Seal Injeccion Filter (MU-F4A/B) Repairs Repair to MU-F4A/B, reported last month were completed during February.
The closure plug seating surfaces were filled with belzona compound in order to stop closure plug leaks.
Post repair testing was performed satisfactorily.
Imcal Leak Rate Testing CM-V1, 2, 3, and 4 and CA-V4A/B were satisfactorily leak tested.
This test program will continue during March.
Nuclear Service Closed Cooling Pump NS-PlB Overhaul of NS-PlB was performed because of noise and high vibration.
The cause was
.'etermined to be the worn bearings.
The bearings were replaced, the pump was re-
- sembled and aligned.
Pump monitoring is now in progress.
Core FJood Valves CF-V1B and CF-V4B Because of suspected pressure seal gasket leaks, CF-VlB and 4B were disassembled and in pected.
Pit marks were found on CF-V1B and were removed.
The valves were re-assembled.
Testing will be performed during March.
.=
REFUELING INFORMATION REQUEST 1.
Name of Facility:
i Three Mile Island Nuclear Station, Unit 1 2.
ficheduled date for next refueling shutdown:
4 Unknown 3
Scheduled date for restart following refueling:
i Unknown 4
h.
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?
I If answer is no, has the reload fuel-design and core configuration been reviewed by your Plant Safety Review Ccamittee to determine whether l
any unreviewed safety questions are associated with the core reload j
(Ref. 10 CFR Section 50 59)?
)
If no such review has taken place, when is it scheduled?
l Amandment No. 50, Cycle 5 reload, was approved on 3-16-79 5 -
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
,1 i
N/A 6.
I:!portant licensing censiderations associated with refueling, e.g. new j
or different fuel design or supplier, unreviewed design or performance i
analysis methods, significant changes in fuel design, new operating procedures:
N/A 7
The number of fuel assemblies (a) in the core, and (b) in the cpent fuel storage pool:
1 (a) 177 1
(b) 208 8.
The present licensed spent fuel pool storage capacity and the size of i
any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
l 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 capacity:
l 1988 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
MNuclear
"!sur,ian"r" "
Route 441 South Middletown. Pennsylvania 17057-0191 717 944 7621 TELEX 84-2386 Writer's Direct Olal Number:
Parch 15, 1984 5211-84-2071 Office of Management Information and Program Control Atta:
W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I (HfI-1)
Operating License No. DPR-50 Docket No. 50-289 February Monthly Operating Report Enclosed please find two (2) copies of the February Operating Report for Three Mile Island Nuclear Station, Unit I.
Sincerely, s
H. D. Hukill, Director, DfI-1
{
HDH;mle I
Attachments cc:
V. Stello Dr. T. E. Murley l
y
-D Ifl GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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