ML20095A535
| ML20095A535 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1992 |
| From: | Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20095A522 | List: |
| References | |
| NUDOCS 9204170115 | |
| Download: ML20095A535 (5) | |
Text
_. _ _. _
4 OPERATIONS
SUMMARY
MARCH 1992 The unit entered the mcnth operating at 100% power producing 862 MWe.
Several reactor building entries have been conducted to add snubber fluid to the "B" RCP snubber reservoir since it was determined that snubber fluid has been leaking at a rate of approximately 0.06 gpd. The total leakage projected for the duration of a 500 day operating cycle is 30 gallons. The PRG rewiew of the circumstances of the snubber leakage concluded that the snubber is operable. The unit continued to operate at 100% power for the duration of the month.
MAJOR SAFETY RELATED MAINTENANCE During March, the following major safety related uaintenance activities were performed:
Miscellaneous Waste Evaporator WDL-1;1B The Miscellaneous Waste Evaporator WDL-Z-1B was removed from service for corrective and preventive maintenance.
The work accomplished included replacement of vacuum pump WDL-P-22A, cleaning of the concentrator and level controller sight glasses, stroking the level controller (LC-40) and replacement of the diaphragms in the evaporator valves.
WDL-Z-18 operated satisfactorily during testing and was returned to service.
River Water Strainer Drive Units A modification to the River Water Strainer drive units was completed in March.
Vented sight glasses were installed on the drive units of RR-S-1A, DR-S-1B, and SR-S-lC. While the drive units were removed from the strainers for installation of the sight glasses, the covers were modified to permit. oil addition to the units. The motors on RR-S-1A and DR-S-1A were disassembled and overhauled.
The equipment operated satisfactorily during testing and was returned to service, i
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9204170115 920413 PDR ADOCK 05000289 R
OPERATING DATA REPORT DOCKET NO.
50-289 DATE COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
- 2. REPORTING PERIOD:
MARCH 1992
- 3. LICENSED THERMAL POWER:
2568
- 4. NAMEPLATE RATING (GROSS MWe):
871
- 5. DESIGN ELECTRICAL RATING (NET MWe):
819
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
- 834
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
- 786
- 8. IF CMANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- Retroactive to 11/15/91, the MDC values have been adjusted down by 22 MWe due to MW-Hour meter recalibration and unidentified losses.
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
- 10. REASONS FOR' RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD (HRS) 744.0 2184.0 154105.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 2184.0 78915.0
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2:45.6
- 14. HOURS GENERATOR ON-LINE (HRS) 744.0 2184.0 77840.2
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1906278 5598651
.189467696
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 638672 1875936 63870195
.18. NET ELECTRICAL ENERGY GENERATED (MWH)
-602916 1770816
.59920141 19.~ UNIT SERVICE FACTOR
(%)
100.0 100.0 50.5.
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 100.0 50.5
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 103.1 103.2 49.5
- 22. UNIT CAPACITY FACTOR (USING DER NET) 98.9
'99.0 47.5
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 43.8 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60648.7
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
^
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
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_ ~. -.... - -, -. -,
4 AVERAGE. DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE.
COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:
MARCH.
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)
(MWe-NET) 1 809 17 810 2
808 18 812 3
811 19 813 4
811 20 813 5
809 21 813 6
809-22 813 7
809 23 813 8
805 24 813 9
804 25 811 10-803 26 809 11 1 810 27 808 12 814 28 810 13 814 29 810 14 813 30 811 15 813 31
'010 16 813 4
t UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289
+
UNIT NAME TMI-l I
REPORT MONTH March 1992 DATE CONPLETED BY W.. G. Heysek TELEPHONE.(717) 948-8191 i
i Method of Licensee System :eneywnt Cause & Corrective bo-Date Type' Ouration Reason' shutting Event Code Code Action to (Hours)
Down Report #
Prerent Recurrence Reactor *
- g*
NONE k
1 2
3 4
F Forced Reason Method Exhibit G - Instructiom for S Scheduled A Equipnent Failure (Emptein) 1-Manual preparation of Data Entry Sheets 8-Maintenance or fest 2-Manual Scram for Licensee Event Report (LER)
C-Refueling 3-Automatic scram File (NUREG-0161) 0-Regulatory Restriction 4-Other (E % ain) l E-Operator Training & Licensing Exaraination 5 Exhibit 1 same source F-Administrativa G-Operational Error (Explaif')
6 Actuot ty used exhibits F & II NUREG 0161 H-Other (Emplain) r P
S
t REFUELING INFORMATION RE0 VEST 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.tnd 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)7 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.
/.
The number of fuel assemblies (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 any increase in licensed storage capacity that has been 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 allew full core off-load capacity (177 fuel assemblies).
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