ML20100Q472
| ML20100Q472 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/29/1992 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-92-2043, NUDOCS 9203170042 | |
| Download: ML20100Q472 (6) | |
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Pvst Of fice Box 480 I
Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8005 March 12, 1992 C311-92-2043 U;-S. Nuclear Regulatory Commission Attn: Document Control Desk
-Washington, D.C, 20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station, Unit I (THI-1)
Operating License No. DPR-50 Docket No. 50-289 Honthly Operating Report for February 1992 Enclosed are two copies of the February 1992. Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely,
&qW T. G. BrougWton Vice President and Director, THI-J WGH Attachments cc: ' Administrator, Region I TMI Senior Resident Inspector a
9203170042 920229 f-
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PDR ADOCK 05000289
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P PDR GPU Nuc: ear Corporation is a subsdary of Generar Putcc Utinfies Corporanon s'
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OPERATIONS
SUMMARY
FEBRUARY 1992 The unit entered the month operating at 100% power producing 868 MWe, As a result of a partial EFW actuation on 1/22/92, modifications to the emergency feedwater control valve circuitry were performed and testeo.
The feedwater valve controllers were replaced at the same time.
On 2/13/92, a meeting was held between GPUN management and the NRC to discuss the TMI-l SALP results.
The unit closed the month operating at 100% power.
MAJ0LSAFli t RELATED MilNTSNMG1 During February, the following major safety related maintenu ce activities were performed:
S13 tion Blackout Diesel Generater EG-Y-4 The Station Blackout Diesel Generator lubricating oil modification was completed during the ronth. Work accomplished included installation of a volume booster to increase the oil supply to the upper bearings during engine starts and repair of various engine oil leaks. Upon completion of the work, a test run of the engine was satisfactorily completed and the SB0 diesel generator was returned to service.
Instrument Air Compressor IA-P-4 Increasing temperatures on Instrument Air Compressor (IA-P-4) caused its removal from service. The compressor inner and after coolers were ramoved and inspected by maintenance personnel.
Both cooler bundles were found coated
. ith NALCO corrosion inhibitor which adversely affected their heat exchange w
capability. The tube bundles were cleaned and reinstalled.
IA-P-4 testea satisfactorily and was retarned to service.
Dperav Heat _ River Water Strainer DR-S_la Decay Heat River Water Strainer (DR-S-1A) was removed from service to repair oil leaks and install a vented oil sightglass on the drive unit.
New motor bearings were. installed while the drive unit motor was removed and disassembled. The motor oil seals were also replaced and the motor was reassembled.
New drive unit oil seals and a vented sightglass were installed.
A modification was made to add oil 'tarough the drive unit cover.
DR-S-1A was reassembled, satisfactorily tested and returned to service.
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4 OPERATING DATA REPORT
^
l DOCKET NO.
50-289 DATE Maren 12, 1992 COMPLETED BY W G HEYSEK i
OPERATING STATUS TELEPHONE (717) 948-8191 1.. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
- 2. REPORTING PER.IOD:
FEBRUARY 1992
- 3. LICENSED THERMAL POWER:
2568
-4,. NAMEPLATE RATING (GRO'S MWe):
871
- 5. DESIGN ELECTRICAL. RATING (NET MWe):
_819 6.' MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
856
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
808 B.
(F CHANGES. OCCUR IN (ITEMS 3-7) SINCE.LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
. 10. AEASONS FOR RESTRICYIONS, IF ANY:
THIS MONTH YR-TO-DATE CUMMULATIVE
-11. HOURS IN: REPORTING PERIOD (RRS) 696.0 1440.0 153361.0
- 8171.0 s
- 13. REACTCL RESERVE SHUTDOWN % VS (HRS) 0.0 0.0 224,5.6 i14.KHOURS GENERATOR ON-LINE-(HRS) 696.0 3440.0 7 709 A
- 15. UNIT KESERVE SHUTDOWN HOURS (HRS) 0.0 6.0 00
'16. GROSS THERMAL' ENERGY GENERATED (MWH) 1784246 3692373 18786%.8 17.JCROSS ELECTHICAL ENERGY.' GENERATED (MWH) 597823 12372E4 632M 023
- 38. NET ELECTRICAL ENERGY GENERATED (MWH) 564208 1167900' 5932!.' 25
- 19. UNIT SERVICE' FACTOR _
(%)
100.0 100.0 50.3 4
-20.JUNIT AVAILABILITY FACTOR _
(%)
100.0 100.0 50.3
'31. UNIT _ CAPACITY' FACTOR (USING MDC NET) 100.3 100.4 49.2 22.' UNIT CAPACITY FACTOR (USING DER NET) 99.0 99.0 47.2
'23. UNIT FORCF,0 OUTAGE RATE (4) 0.O_
-0.0 44.0
_ UNIT. FORCED OUTAGE HOURS.
(HRS) 0.O' O.0 60648.7 e
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-24,' SHUTDOWNS; SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
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$25. ~IF SHUT DOWN AT END OF REPORT. PERIOD, ESTIMATED DAff. OF STARTUP:
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AVERAGE DAII.Y UNIT POWER LEVEL DOCKET NO.
50-289 UNIT THI-1 DATE March 12, 1992 COMPLETED BY U G HEYSEK 4
TELEPHONE (717, 948-8191 MONTII:
FEBRUARY r-DAL
' AVERAGE DhII! POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i
(MWe-NET)
(MWe-NET)-
1 811 17 810 2
811 18 809
'3 811 19 807 4
811 20 808 6
813 21 809
-6 814 22 810 7
,813 23-807
'8 813 24 809 9-814 25 all i
~10 '
814 26 811 11-811 27 810 j
12' 815 28 808 i
13 812 29 812 14 811 30
!!A 15 806 31 NA
'16 B07 1
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. UNIT SHUTDOWNS AND PCWER' REDUCTIONS DOCKET NO.
50-289 t? NIT N?)(E TMI-1 REPORT MONTH -February 1992 DATE. March 12, 1992
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COMPLI"IED BY W. G. Hevsek TELEPHoliE (117) 948-8191 Method of
^ Licensee Mystem :ornpoemt Cause & Corre;tive No-Date Type' Duration Reason'
. Shutting Event Code
- Code Actfon to (Hours)
Doim Report #
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Present Recurre y.
ll.
Reactor
- I i
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NONE i
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1
' 2 3
4 F Forced Reason Method Exhibit G - Instructions for S Scheduled A-Ecpipment f ailure (Explain) 1-Manual pr<paration of Data Entry Sheets a-Maintenance or Test 2-Nml Scrara for Licensee Event Report (LER)
C-Refueling 3-Autonutic Scram File (WREG-0161)
D-Regulatory Restriction 4-Other (Explain)
E-operator Training & Licensing Examination S Exhibit 1 same source F* Achinistrative C-Operational Error (Explain) 6 Actually used exhibits F & II NUREG 0161 I
W-Other (Explain) 5 i
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1 BEVELUi(LIEORMATION RE00EST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
September 17, 1993 (10R) 3.
- Scheduled date for restart following current refueling: NA 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? NA If answer is yes, in general, what will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee 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?
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
None, planned.
6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
GPU Nuclear has installed four Westinghouse Lead Test Assemblies during the reload of the TMI-1 core for cycle 9 operation.
Westinghouse fuel technology will be utilized to the extent possible.
7.
The number of fuel assemolies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 521 8.
The present licensed spent fuel pool storage capacity and the size of cny increase in licensed storage capacity that has oeen requested or is planned, in number of fuel assemblies:
The present licensed capacity is 752. Planning to increase licensed capacity through fuel pool reracking is in progress.
- 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
The 9R (1991) refueling discharge was the last to allow full core off-load capacity (177 fuel assemblies).
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