ML20211A301
| ML20211A301 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/31/1987 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 0015C, 15C, 5211-87-2035, NUDOCS 8702190142 | |
| Download: ML20211A301 (7) | |
Text
.
OPERATING DATA REPORT DOCKET NO.
50-289 DATE l-31-87 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
JANUARY
,1987.
- 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.
l
- 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.
744.
108841.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 40085.3
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1874.1
'14. HOURS GENERATOR ON-LINE 0.0 0.0 39246.2
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.
O.
94927262.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.
O.
31518871.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.
O.
29469975.
- 19. UNIT SERVICE FACTOR 0.0 0.0 36.1
- 20. UNIT AVAILABI.LITY FACTOR 0.0 0.0 36.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 34.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 33.1
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 60.2
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH Currently in a Refuelinq Outage
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: March ZU, 1987 G702190142 B70131 PDR ADOCK 05000239 s$k R
PDR r
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-l DATE l-'31-87 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 MONTH:
JANUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0.
17 0.
2 0.
18 0.
3 0.
19 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' O.
27 0,
12 0.
28 0,
13 0.
29 0.
14 0.
30 0.
15 0.
31 0.
16 0.
l 50-289 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME. TMI-I l-J1-6/
DATE COMPLETED BY C.W. Smyth REPORT MONTH JANilARY.
TELEPHONE (7171 44R 8551 v.
f'o 3 u, E r,
.=2,e E
- , s 4 Licensee 5%
c4 Cause & Correceive L
No.
Date
,q 3g g
,g g 5 Event tr. 9 8 ~E Action to
$E E
j5g Report ::
i# G Prevent Recurrence 5
87-01 01/31/87 S
744 C
N/A N/A N/A N/A Shutdown for Refueling Outage i,
i 2
3 4
F: l'o r t ed Reason:
Method:
Exlubit G. instruttions S. Ssheduled A l'quipment Failure (Explain)
- 1. Manual for Preparation of Data 11 Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C. Refueling 1 Autonutic Stram.
Event Report (LERI Fife (NtlRI G.
D Regulatory Resiriction 4-Other (tiplain) 01611 1 -Operator Training & Iicenw I uminution F-Adnunist rative 5
Esinbit ! - Same Source G Operational in vor ( E splam )
11 Other (E splaini 6
Actually used Exhibits F & 11 UUREC 0161
REFUELING INFORMATION REQUEST a
1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
July 1, 1988 (7R) 3.
Scheduled date for restart following refueling:
March 20, 1987 (For current 6R Outage)
September 14, 1988 (7R) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes (For 6R)
If answer is yes, in general, what will these be?
Conversion to 18 month fuel cycle with associated changes to Power Imbalance, Quadrant Tilt and Rod Insertion Limits.
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?
To be chtermined.
5.
Scheduled date(s) for submitting proposed licensing action and supporting i nformation:
submitted November 3,1986.
(For 6R) 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:
None 7.
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).
GPU Nuclear Corporation Nuclear
- eme:::ao o
s Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
February 12, 1987 5211-87-2035 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report Ja nuary, 1987 Enclosed please find two (2) copies of the January,1987 Monthly Operating Report for Three Mile Island Nuclear Station, Unit-1.
Si
- erely, D. Hukil Vice President & Director, TMI-l HDH:DVH:spb cc: Dr. T. E. Murley F. I. Young Attachments 0015C
/
ip GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
OPERATIONS SIMMARY J ANUARY, 1987 The unit entered January in a refueling shutdown condition with the Reactor Vessel head removed and the plenum stored in the deep end of the fuel transfer canal. The fill of the shallow end of the fuel transfer canal was completed.
On January 2,1987, Cycle 6 refueling commenced.
On January 9,1987, the lE 4160V Bus de-energized as a result of a worker causing an overcurrent relay to trip and stay locked in.
The resulting undervoltage condition on the lE Bus caused the auto start of the B Emergency Diesel Generator.
Decay heat removal which was effected by the loss of the lE Bus was restored in 11 mi nutes. LER 87-001 provides detailed information on this event. Cycle 6 refueling was completed on January 11, 1987. At the close of the month preparations were being made to place fuel transfer canal on cleanup to the BWST (Borated Water Storage Tank).
MAJOR SAFETY RELATED MAINTENANCE During the month of January, the following major maintenance items were performed:
Emergency Diesel Generator EG-Y-1 A - Emergency Diesel Generator "A" (EG-Y-1 A) work involved reassembly of diesel parts including new cylinder liners.
EG-Y-1 A was aligned for testing and the test run started. Loading of the diesel and various inspections were performed per the vendor test requirements for new liner installation work.
During the testlng, a scoring problem occurred on the new liners which required the diesel to be disassembled and the new cylinder liners replaced.
During the reinstallation of new liners, an oil drain ring was removed from the bottom piston to eliminate problems with the liners. Also, the orifice size in the jacket coolant system was increased to allow better cooling of the diesel.
After the diesel was again reassembled, a test run was performed on the diesel.
EG-Y-1A was tested satisfactorily and the diesel was returned to service. The "B" diesel EG-Y-1B, was then taken out of service for annual inspection requirements. A leak check of the coolant system was performed.
One liner leaked and evaluations are being performed to determine if liner replacement is required. Work will continue in February.
BWST Work Items - With the Borated Water Storage Tank (BWST) drained, the following work items were completed:
- DH-V-5A/B seat leakage was corrected by machining seats, installation of a new wedge and fitting of the wedge to the seats.
A hydrostatic test was performed with satisfactory results.
- DH-V-14A/B seat leakage was repaired by installing new sen rings and replacing the disc arm on DH-V-148. A hydrostatic test was performed with satisfactory results.
- BWST heaters were replaced with new heaters.
During the refilling of BWST, one of the new heaters leaked at the electrical leads and the BWST was drained for replacement of this heater. The leaking heater was replaced and refilling of the BWST preparations continued.
OTSG Emergency Feedwater Nozzle Replacement - The OTSG Emergency Feedwater nozzle replacement work started in January. Three (3) risers and nozzles from the "A" and "B" 0TSG were removed and deconned. The six risers were moved to the machine shop for machining.
An inspection of the "A" 0TSG shell gasket seating surfaces was performed and it was determined the gasket surface of the A-3 nozzle would require machine work.
An inspection of the "B" OTSG shell gasket seating surfaces was performed and no indications were found. Machine work on the six (6) removed risers was completed and the new nozzles fit to the riser and OTSGs. Two (2) nozzles and risers were installed and torqued on the "A" 0TSG and the three (3) nozzles and risers were installed and torqued on the "B" OTSG. The three (3) remaining risers and nozzles were removed from the "B" 0TSG, deconned and moved to the machine shop.
The "B" 0TSG shell gasket seating surfaces were inspected with no defects or indications. Work is to be continued in February.
M0 VATS Valve Testing - Motor Operator Valve Analytical Testing (MOVATS) commenced in January. Forty-three (43) valves were tested.
Testing will continue and is scheduled for completion in February.
l l