ML20085K587
| ML20085K587 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/14/1983 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 5211-83-300, NUDOCS 8310210037 | |
| Download: ML20085K587 (7) | |
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE October 14, 1983 COMELE.TED_BLC. L Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. POPORTING PERIOD:
SEPT
,1983.
1, LTCENSED THERMAL _P.OWER_ (EWT.) ?
?R19-
- 4. NAMEPLATE RATING (GROSS MWE):
871.
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819.
_ 6 liAXIMUbLDEPINDABLE__CAEACTTY ( GROSS._ MWE1:
R2O 7
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
l
, 8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE) 10 d EASONS._ EOR _ RESTRICTIONS._lE_.ANY?
4 TNTg MnNTM V P_- T O.D L "
C UEUU LATl_VI______
- 11.. HOURS IN REPORTING PERIOD 720 6551.
79584.
D. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8 13.. REACTOR RESERVE _ SHUTDOWN _ HOURS
.0 0
__0. 0_.._ _. _
23ft.5 _._
14 HOURS GENERATOR ON-LINE 0.0 0.0 31180.9 (5. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 E.... GROSS SHERMAL_INERGY_ GENERATED _(MWH)__
0 ___.
_D._.-__26531D11._._
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
25484330
- 13. NET ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
23840053.
- 9._ UNIT. SERVICE _ FACTOR 0. 0_._... _0. 0_ __
39.2 10 UNIT AVAILABILITY FACTOR 0.0 0.0 39.2
't.
UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 38.2
- 2 m UNIT CAPACITY _ FACTOR _IUSING.. DER _ NET) 0. 0_ _ _ _ _ _
0. 0_. _
3_6.6_ _
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 56.9
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
- 95. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
f310210037 831014 PDR ADOCK 05000289 L
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 nAmr October. 14. 1983 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551
~
MONTH:
SEPT DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWE.-NET)
(MWE_-SEP )
- 1 0,
17 0,
2 0
18 0.
3 n;
io n_
4 0.
20 0
5 0
21 0
6
- J.
99 n;
7 0
23 0
8 0
24 0
_9 n;
9; n_
10 0
26 0.
11 0
27 n.
__m12 0
29 0.
13 0
29 0
14 0
30 0
%.5 Q,
31 N/A 16 0
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50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME TMi-1 DATE October 14. 1983
~
REPORT MONTil September, 1983 COMPLETED BY
_C. W. Smyth f7. ~TV4~84551~
17 TELEPHONE "e'
.33 3
.[k I.icensee
,E-t, b
Cause & Corrective
~
8.%
No.
Date g
3g g
_g g 5 Event u?
3 Action to 3 5 :!
lleport 8f
<5 0
$U Prevent Recurrence e
u c5 Y
1 83/09/01 F
744 D
1 N/A ZZ ZZZZZZ i
2 3
4 l'
Foned Reason:
Metiuxt:
Exhibit G -Insnuctions S: S( hed uled A I~quipment Failure (fixplain) 1-Manual for Prepaiation of Data li Maintenance of Test 2 Manual Scram.
I:ntry Sheets for I.icensec C RcIncling 3 Automatic Scram.
livent Report (1.liR) File (NilRI G-D Regulatory Restriction 4-Oti.cr (lixplain) 0161)
I! Operator lraining & licenw 1% amination
~
F. Ad.ninist ra t ive 5
G Operaljonal 1 rror (l xplaitt)
I:xhibit 1 S une Somic 11 Other ( E xplain)
t
+
OPERATIONS
SUMMARY
The unit was shutdown the entire month by order o'f the NRC.
For most of the month the plant was in hot shutdown with four Reactor Coolant Pumps running.
Hot Functional Testing was being performed in accordance with approved proce-dures.
Major evolutions included:
1.
Primary System Hydro to 2285 PSIG on 9/1/83.
2.
Cooldown and heatup with Kr 85 leak check on 9/7 and again on 9/19/83.
3.
Power load transfer test on 9/30/83.
All testing was performed satisfactorily and provided additional confidence in the leak tightness of the OTSG tubes.
MAJOR SAFETY RELATED MAINTENANCE The following major safety related maintenance was performed during the month:
Several valves in' the chemical addition system that leaked thru or had pack-ing leaks and did not function as designed were repaired and tested satis-factorily.
. The snubber testing program continued during the month and will continue in October.
The decay heat removal river water pump (DR-P-1B) was repaired following damage to the impeller caused by partial intake of a desilting_ suction hose.
The pump was disassenbled, shaft runout readings were taken, the bowl assembly was replaced and the pump was re-assembled.
All post maintenance testina was performed satisfactorily.
Repairs were made to instrument air valve IA-V-20 which would not close. The bonnet and stem assembly was replaced and the valve was satisfactorily leak rate tested.
Main steam relief valve testing was conducted during the month with 11 of 18 valves identified as weeping.
Repair work planning is in progress while actual repair work will commense at a later date..
The pressurizer spray line isolation valve, RV-V3, was repaired after it was found to be leaking through. The limitorque operator torque switch was found to be out of adjustment. After adjustment the valve was tested satisfactorily.
The governor drive motor for emergency diesel (EG-Y-1 A) wa's found to be def-fective and replaced. Testing was unsatisfactorily performed when the governor would not properly run down speed in manual.
Diesel testing was then reperformed satisfactorily. An NPRD failure report will be submitted.
-n-
- Inspection / investigation work on RM-A-5 was performed as follows:
Installed Redundant Monitor Performed Calibrations Checks Inspected /Meggared Cables i
Performed Voltage Checks Connected Recorder to Monitor Parameters Associated with Monitor Silt was removed from the bottom of the river water screen house as part of the annual desilting program.
i i
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I
EE?TEL:::3 :::FOFFEICI: EE:TIEC 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
Unknown L.
Will refueling or resu=ption of operation thereafter require a technical specification change or other license mnendment?
If answer is yes, in general, what vill these be?
If answer is no, has the reload fuel desigr and core configuration been reviewed by your Plant Safety Review Co=rittee to deterrine whether any unreviewed safety questions are associated with the core relcad (Ref. 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 5
Scheduled date(s) for submitting proposed licensing acticn and supporting information:
N/A 6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed iesign or performance analysis methods, significant changes in fuel design, new operating procedures:
N/A 7.
The number of fuel assemblies (a) in the cere, ani (t) in the spent fuel storage pool:
(a) 177 (b) 206 8.
The present licensed spent fuel pool storage capacity and the size of 1
any increase in licensed storage capacity that has teen requested or is planned, in nudber of fuel assedblies:
The prz:sent licensed capacity is 752.
There are no planned increaces at this time.
- c "'c-harged to the spent 9
The projected date of the last refueling tha-
-e-fuel pool assuming the present licensed capacity 1987 is the last refuelinE discharge which allevs full core off-1 cad capacity (177 fuel assenblies).
i
t
, ~f GPU Nuclear Corporation
. Nuclear
- e m S r 8o o
e Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
October 14, 1983 5211-83-300 Office of Management Information and Program Control Attn:
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 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for September Enclosed please find two (2) copies of the September Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, H.h.Hukill Director, TMI-l HDH:vj f Enclosures l
cc:
V. Stello l
Dr. Thomas E. Murley
//
j GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation