ML20129H941
| ML20129H941 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1985 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 5211-85-2055, NUDOCS 8506070697 | |
| Download: ML20129H941 (6) | |
Text
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OPERATIONS
SUMMARY
MARCH, 1985 The Unit was in cold shutdown the entire month by order of the NRC. Core cooling was provided by the Decay Heat Removal System.
During the month, work was completed on the OTSGs as identified below. The Reactor Coolant System was filled and vented, and the secondary was placed on cleanup. A vacuum was drawn and the turbine was placed on the turning gear. At the end of the month, the decision was made to delay system testing in order to plug a number of OTSG tubes whose integrity had continued to be investigated. This work will be reported in the April 1985 report.
Major Safety Related Maintenance During the month of March, 1985 the following major maintenance items were performed:
OTSGs A/B - The OTSG repair program continued with satisfactory drip and bubble tests and the reinstallation of manway and handhole covers.
During the last week of the month, preparations were made to reopen the generators to plug tubes with greater than 40% thru wall Eddy Current indications. Work platforms were erected and tooling staged.
Plugging will commence in April, 1985.
AIR HANDLING PURGE VALVES AH-V-1A/1B - Seat replacement work on AH-V-1A and AH-V-1B was completed, followed by satisfactory local leak rate testing.
DECAY HEAT REMOVAL PUMPS DH-P-1A/B - DH-P-1A/B seal flush water piping replacement work was completed. New high pressure valves were welded, penetrant tested, and hydrostatically tested in the shop. The old piping and valves were removed from the pumps and the new pipe / valves and tubing were installed. All work was completed.
BUILDING SPRAY PUMPS BS-P-1A/B - BS-P-1A/B seal flush water replacement work was completed. New high pressure valves were welded, penetrant tested, and hydrostatically tested in the shop satisfactorily. The old piping / valves were removed from the pumps and the new piping / valves and tubing were installed.
All work was completed.
SCREEN WASH PUMP SW-P-1A - SW-P-1A work resulting from high vibration readings commenced. The pump was disassembled and removed, parts were replaced as required, and the impeller / shaft was balanced. The bowl assembly was reassembled and the pump reassembly and reinstallation is in progress. Work will be completed in April,1985.
MARINITE FIRE BARRIER REPLACEMENT - Fire barrier replacement work (Marinite Board, Kaowool/Cerafiber) commenced.
Broken, damaged or missing marinite board was replaced and joints, cracks, etc., were sealed with Kaowool/Ceraff ber. Screen House work and Intermediate Bldg. work was completed and Control Bldg. work is in progress.
8506070697 850331 PDR ADOCK 05000289 bg4 R
PDR l
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' OPERATING DATA REPORT DOCKET No.
- 50-289 DATE March 31_ 198 COMPLETED BY rW hth TELEPHONE (7171 948-855 OPERATING STATUS NOTES
.1. UNIT.NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
MARCH
,1985.
- 3. LICENSED THERMAL POWER (MWT) :
2535.
- 4. NAMEPLATE RATING (GROSS MWE) :
871.
5 ~. DESIGN ELECTRICAL RATING (NET MWE) :
819.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :
824.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
- 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:
THIS MONTH YR-TO-DATE CUMMULATIVE-
- 11. HOURS IN REPORTING PERIOD 744.
2160.-
92737.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5
- 14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0.
0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.
O.
76531071.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)'
O.
O.
25484330.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.
O.
23840053.
- 19. UNIT SERVICE FACTOR
- 20. UNIT AVAILABILITY FACTOR 0.0 0.0 33.6 0.0 0.0 33.6 21.-UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 32.9 l
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 O.0 31.4 l
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 63.5 i 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
I
r:
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-l DATE March 31. 1985 COMPLETED BY c.W. Smyth TELEPHONE (717) 948-8551 MONTH:
MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0.
17 0.
2-O.
18 0.
3 0.
19 0.
4 0.
20 0.
5 0,
21 0.
6 0.
22.
O.,
7 0.
23 0.
8 0.
24 0.
9 0.
25 O.
10 0,
26 0,
11 0.
27 0.
12 0.
28 0.
13 0.
29 0.
14 0.
30 0.
15 0.
31 0.
16 0.
d-
DOCKETNO. 50-289 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME TMI-I DATE narcn $1, 1985 REPORT MONTH MARCH, 1985 COMPLETED BY C. W. Smyth TELEPHONE (717) 94Q661 "s
e c.
3 5
.2 _e E
2.s g Licensee E%
g4 Cause & Corrective No.
Date
{
gg g
jg5 Event uT
['3 o-Action to
$E jig Report a N0 Prevent Recurrence 6
1 85/03/31 F
744 D
1 N/A ZZ ZZZZZZ Regulatory Restraint Order 1
2 3
4 F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation 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)
EOperator Training & License Examination F-Administrative 5
G-OperatJonal Error (Explain)
Exhibit I-Same Source 11-01her (Explain)
6 REFUELING INFORMATION REQUEST 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 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?
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?
Amendment No. 50, Cycle 5 reload, was approved on 3-16-79 5
Scheduled date(s) for submittin'g proposed licensing action and supporting information:
N/A-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:
N/A T.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 208 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. 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:
1991 is the last refueling discharge which allows full core off-load l
capacity (177 fuel assemblies).
l-i
/
/
GPU Nuclear Corporation Nuclear
- ,omgr8o Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number:
April 18, 1985 5211-85-2055 Office of Management Infomation and Program Control Attn:
W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Mcdonald:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report March, 1985 Enclosed please find two (2) copies of the March, 1985 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.
Sincerely, Ql-} // 0 Y VH. D. Heki 1 Director, THI-1 HDH:JGB:spb Attachments cc:
V. Stello Dr. T. E. Murley gjf 0015C I
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
.