ML20079C122
| ML20079C122 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1991 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-91-2062, NUDOCS 9106180432 | |
| Download: ML20079C122 (6) | |
Text
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6 3 Nuclear OPU Nuctsar Corporation
- o"rs
- ,/8o Middletown, Pennspvania 170$7 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(711) 948-8005 June 12, 1991 C311-91-2062 U. S. liuclear Regulatory Commisalon Attnt Document Control Desk Washington, D.C.
20555 Centlement
Subject:
Three Mile Island 13uclear Station, Unit I (TMI-1)
Operating License 13o. DPR 50 Docket tio. 50-289 Monthly operating Report May 1991 Enclosed are tw copies of the Hay, 1991 Monthly Operating Report for Three Mile Island tiuclear Station, Unit 1.
Sincerely,
,Y T. G. Br ghton Vice President & Director, TMI-1 WGH Attachments cc: Administrator, Region I THI Senior Resident Inspector 9106180432 910531 F'DR MiOC K 05000209 R
F'DR
/
GPU Nuclear Corporahon is a subsidiary of Gene'ai Pubhc Uhht:es Corporation f
~
y
s OPERATIONS
SUMMARY
MAY 1991 THI Unit 1 operated the entire month of May at -93% [cwor producing ~780 MWo gross electrical generation.
Reactor power continues to be limited by high 0750 level caused by secondary side fouling on the "B" loop. As of Hay 31, 1991 the turbine had been on-line continuously for 416 days.
Plant personnel continue to to closely monitor several off normal conditions.
The A Reactor Coolant Pump #1 Seal Leakoff flow has continued to increase.
Monitoring and evaluation o this condition are continuing.
Primary /Socondary leakrate has increased to -0.057 gpm but remains below the administrative limit of 6 gph above baseline.
MAJOR SAFITI_EELATED Mall {IENANCE l
During Hay, the following major Safety Related maintenance items were l
l completed:
hakeuo system __Sgp1 Iniection Filter MU-F-(&
Based on the need to control increasing #1 seal leak-off, Reactor Coolant Pump seal injection filter MU-F-4A was replaced with a different style filter.
A new filter housing and 1 micron filter element replaced the old housing which held a 5 micron filter element.
Elimination of the larger particles from the seal water supply system by the smaller sized filter is expected to positively effect seal performance. All welds passed required inspectione and a hydro-static test of the modified system piping was satisfactorily completed prior to MU-F-4A being turned over for operation.
Nuclear Service River Water Chegk_ Valve NR-V-20B Nuclear Service River Water Pump discharge check valve NR-V-20B was removed from service and disassembled to determine the cause of the disc sticking in the open position.
Upon inspection, it was found that swing arm wear allowed the disc to becomo cocked and wedge in the open position. After the valve seating surfaces were cleaned, a new disc swing arm was installed and the valve reassembled.
Post maintenance testing was satisfactorily completed and the valve returned to service.
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE ilone 1P, 1991 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
- 2. REPORTING PERIOD:
KAY 1991
- 3. LICENSED THERMAL POWER:
2568
- 4. HAMEPLATE RATING (GROSS KWe):
871
- 5. DESIGN ELECTRICAL RATING (NET MWe):
819
- 6. KAXIMUM DEPENDABLE CAPhCITY (GROSS HWe):
856
- 7. KAXIMUM DEPENDABLE CAPACITY (NET MWe):
808 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET HWe):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS HONTH YR-TO-DATE CUKHULATIVE
- 11. HOURS IN REPORTING PERIOD (HRS) 744.0 3623.0 146784.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 3623.0 72787.2
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2245.6
- 14. HOURS GENERATOR ON-LINE (HRS) 744.0 3623.0 71742.7
- 15. UNIT RESERVE SKUTDOWN HOURS IRRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (KWH) 1770687 8620468 175090800
- 17. GROSS ELECTRICAL ENERGY GENERATED (HWH) 581189 2902653 58863557
- 18. NET ELECTRICAL ENERGY GENERATED (KWH) 546615 2731319 55220739
- 19. UNIT SERVICE FACTOR
(%)
100.0 100.0 48.9
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 100.0 48.9
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 90.9 93.3 47.9
- 22. UNIT CAPACITY FACTOR (USIt!3 DER NET) 89.7 92.0 45.9
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 45.8
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE DATE AND DURATION OF EACH Cycle 9 Refueling Outage, scheduled to begin, on 9/27/91, with a nominal):8 to 10 week duration.
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIKATED DATE OF STARTUP:
3 l
)
e i
AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TM -1 clu ne
(,
1991 DATE COMPLETED BY W G HEYSEK TELEPilONE (717) 948-8191 HONTH:
MAY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POVtR LEVEL (MWe-NET)
(MWe-NEi) 1 740 17 729 2
745 18 739 3
747 19 747 4
748 20 747 5
744 21 739 6
743 22 732 7
745 23 729 8
744 34 728 9
745 25 7*1 10 743 26 720 11 742 27 720 12 732 28 718 13 730 29 721 14 734 30 720 15 733 31 717 16 733 l
l l
l 4
{
l UNIT SHtTIDOWNS AND POWER REDUCTIONS
~
DOCKET NO.
50-239 UNIT NAME TMI-1 REPORT MONTH May 1991 DATL June 12, 1991 s 1- ?LETED BY W. G. Heysek j
TA K3CeE (717) 946-8191 i
m
[
method of Li ensee System Camponent te se & orrectise l
2 f
- 0-Date Type Duratim Reason Shutting Event Code code Acticn to l
(Mours)
Dein Repertf
% w.
2e a re-ce 3
6 l
Reactor 5 6 g
,i NONE t
f 4
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t i
t
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f f
i 1
2 3
4 F Forced Reason method Exhibit G - Instructions for S Scheckled A-Eoaipment Falture (Esplein) 1-Manuel preparation of Data Entry Sheets
}
j 8-ataintenance or Test 2-panust Scrare for Licensee Event Report (LER) j C-Refueling 3-Automatic Scram File (WJREG-C161) i D-Regulatory Westr*ction e-Cther (Empisin)
E-Operator Training E Licensing Esaninstion 5 Exhibit 1 same source F-A&inistrative C-Operational Error (Imptain) 6 Actuelty used emhibits F & II WJoEG C161 u-Other (Emplain) 5
l
}1EEUEllliG INFORPSTP' Sl(*)5SI 2.
Name of Facility:
Three Mile IslaDd Nucasar Station, Unit 1 2.
Scheduled date for next refueling shutdowns beptember 27, 1991 (9R) 3.
Scheduled date for restart following current refueling: NA 4.
Will refueling or resumption of operation thereafter require a technical upecification change or other license amendment?
No.
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)?
No.
If no such review has taken place, when is it scheduled? 6/91.
5.
Scheduled date(s) for submitting proposed licensing action and support-ing information:
None planned.
6.
Important licenairy conaiderations associated with refueling, e.g.
new or different fuel design or supplier, unreviawed design or performance analysis methods, significant changes in fuel design, new operating procedures:
GPU Nuclear plans to install four Westinghouse Lead Test Assem-blies during the reload of the TM1-1 core for cycle 9 operation.
Westinghouse fuel technology will be utilized to the extent possible.
7.
Tho number of fuel assemblies (a) in the core, and (b) in the spint fuel storage pools (a) 177 (L) 441 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assembliec The present licensed capacity is 752.
Plannang 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:
1991 is the last refueling discharge which allows full core off-load capacity ( 17 ~. fuel a=semblies).
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