ML20127G888
| ML20127G888 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1985 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 0015C, 15C, 5211-85-2110, NUDOCS 8506260124 | |
| Download: ML20127G888 (7) | |
Text
.
OPERATIONS
SUMMARY
MAY, 1985 The Unit was snut down the entire month by order of the NRC. Core cooling was provided by the Decay. Heat Removal System. The primary plant was maintained at about 110*F and 45 psi with a bubble in the Pressurizer. The secondary side of both OTSGs were in full wet layup.
Major Safety Related Maintenance The following major maintenance work was performed during the month.
Most work was identified during the Hot Functional testing that was performed during April,1985.
Tendon Surveillance - An inspection program was initiated on the Reactor Building tendons in accordance with.the periodically scheduled surveillance program. This program will continue into June, 1985.
Decay Heat Removal Valve DH-V Repairs to DH-V-2 (stem / pressure seal ring replacement)-were completed with the repacking of the valve, reinstallation of the operator and electric leads and testing per SP1300-3R. All work is complete.
Main Steam Safety Relief Valves MS-V-19A/B/C & MS-V-20C - Repairs to Main Steam Safety Rel' ef Valves, which were leaking by the seat were completed in May, 1985. The valves were disassembled and seats / discs were lapped by the manufacturer representative (Dresser). The valves were reassembled and set by the Dresser representative, and will be tested in June,-1985.
In addition, the discharge flanges of the relief. valves were inspected and tightened, and a leaking union was repaired on MS-V-17C. This work will be reported to the INP0 NPRD system.
Packing Leak-Off Piping on Valves RC-V-1/3 and MU-V-1A - Packing leak-off piping elimination was completed during May,1985.
Leak-off nipples were cut ~
and pipe caps installed and welded in place. Drain header piping ends were also capped and welded. All welds were NDE inspected satisfactorily.
Waste Disposal Liquid Piping at WDL-V Replacement of piping at valve WDL-V-62 (pin hole leak in pipe) started in May,1985.
Insulation / heat trace was removed, affected piping was cut-from the system, and new pipe was fitted up-and welded into the system. The weld joints were NDE inspected by QC/ANI satisfactorily. Heat trace and insulation was reinstalled and an operational leak check will be performed later.
Reactor Coolant Pumps RC-P-1B/C/D - Repairs to the motor oil systems which had oil -leaks were accomplished in May,1985. RC-P-1B motor oil was drained, fittings were cleaned and tightened, and the motor was refilled with oil.
RC-P-1C and RC-P-1D motor oil systems were drained, new oil tubing and fittings were installed and the systems were refilled with oil. The systems
-were leak tested satisfactorily.
8506260"124 850 g,
y M' P"
^
roa
2 Make-up Pump Motor MU-P-1A - Repairs to MU-P-1A motor which had oil leaks were completed in May, 1985. The motor oil return line from the bearing was found to have an accumulation of dirt. The oil return line was cleaned and the motor tested satisfactorily.
Decay Heat Removal River Water Pump DR-P-1B - Repairs to DR-P-1B (high vibration) were completed during May,1985. The motor was removed, the pump removed, disassembled, overhauled and reinstalled.
The motor was tested satisfactorily per IST 1300-3D.
Precoat Filter WDL-F-1B - Filter element change out of WDL-F-1B (high D/P) was performed in May, 1985. The filter dome was removed and the old elements removed. New elements were installed and the filter dome reinstalled.
Testing of the filter is continuing.
Air Handling System Purge Valve AH-V-1A - Repairs to AH-V-1A actuator because the valve would not stay at the 30 position during flow testing commenced in May, 1985. The actuator was opened and the yoke pin rollers were found broken / worn.
New rollers were fabricated and installed in the actuator.
Testing will continue. AH-V-1D actuator was inspected and no damage found.
This work will be reported to the INP0 NPRD system.
50-289 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME TMI-I DATE 5/31/85 3 -
g REPORT MONT1f Ma v. 1985 3
.3 ?
3 h.5k Licensee
$-r, g,,
Cause & Corrective e
No.
Date g
3g jj$
Event g7 o3 Action to fU H
$5 5
j;5g ReporI
- mU Prevent Recurrence c5 Regulatory Restraint Order 1
85/05/31 F
744 D
1 N/A ZZ ZZZZZZ i
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (F-(,m) 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)
E-Operator Training & License Examination F Administrative 5
G-Operatjonal Error (Explain)
Exhibit I - Same Source Il-Other (Explain)
~ *...
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 k.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
If answer is yes, in general, what vill 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 submitting 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 capacity (177 fuel assemblies).
OPERATING DATA REPORT DOCKET NO.
50-289 DATE 05/31/85 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES 1., UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
MAY
,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 CH7NGES 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.
3623.
94200.
- 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)
O.
O.
76531071.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.
O.
25484330.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
23840053.
- 19. UNIT SERVICE FACTOR 0.0 0.0 33.1
- 20. UNIT AVAILABILITY FACTOR 0.0 0.0 33.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 32.4
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 30.9
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 64.1
- 24. SHUTDOhTNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
i
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-l DATE 05/31/85 COMPLETED BY C. W. $ vth 3
TELEPHONE (717) 948-8551 MONTH:
MAY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0.
17 0.
2 0.
18 0.
3 0.
l'9 0.
4 0.
20 0,
5 0.
21 0.
6 0.
22 0.
7 0.
23 0,
8 0.
24 0.
9 0,
25 0.
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.
O a
- e GPU Nuclear Corporation Nuclear
- ,ome:r8o s
Middletown, Pennsylvania 17G57 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
June 17, 1985 5211-85-2110 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 Mr. Mcdonald:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report May, 1985 Enclosed please find two (2) copies of the May, 1985 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.
Sincerely,
. D. H kill Director, TMI-1 HDH:JGB:spb Attachments cc:
V. Stello Dr. T. E. Murley 0015C
- l GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation