ML20207S215
| ML20207S215 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/28/1987 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 5211-87-2058, NUDOCS 8703190138 | |
| Download: ML20207S215 (7) | |
Text
.
OPEPATIONS
SUMMARY
FEBRUARY, 1987 The unit entered February in a refueling shutdown condition with the Reactor Vessel Head renoved.
Preparations to drain the fuel transfer canal were in progress. On February 2,1987, the fuel transfer canal was drained to 1 foot below the shallow end. The plenum was set in the vessel on February 13th and the Reactor Vessel Head was installed on the 14th. At the end of the month the Reactor Coolant System was being prepared for fill.
MAJOR SAFETY RELATED MAINTENANCE During the month of February, the following najor maintenance items were performed:
Emergency Diesel Generator EG-Y-1B - Emergency Diesel Generator EG-Y-1B work included the decision to replace the cylinder liners due to liner leakage.
The diesel engine was disassembled, new cylinder liners installed and the diesel engine was reassembled.
Preventative maintenance and annual inspection work were also acconplished.
A test run of the diesel was performed and all inspection results were satisfactory.
OTSG Energency Feedwater Nozzle Replacenent - The OTSG Emergency Feedwater nozzle replacement work conpleted in February. Work included remachining one (1) shell gasket seating surface on the "A" OTSG. A new nozzle was installed and the riser reinstalled. The three (3) remaining risers / nozzles were renoved and inspection revealed no further machine work was required.
New nozzles were fit-up and the risers reinstalled. Work on the "B" OTSG included the fit-up of the three (3) remaining new nozzles and the reinstallation of the risers.
M0 VATS Valve Testing - Motor Operator Valve Analytical Testing (MOVATS) continued in February and was completed for this outage.
Reactor Yessel Head Reinstallation Work - The Reactor Vessel (RV) Head reinsta11ation was completed in February with the following itens conpleted.
The RV head studs / nuts were cleaned and NDE inspections completed. The shallow end of the fuel transfer canal (FTC) was drained and deconned.
Reactor Vessel flange hole plugs were renoved and the flar:ge holes cleaned.
The FTC seal plate was renoved and stored. The upper plenum was rigged and installed in the Reactor Vessel. The RV head was rigged and installed on the reactor, and the RV studs were "unparked" and tensioned.
The cable platform was reinstalled and the intermediate Closed Cooling water spool to the RV head was connected.
The PI/TC cables, RV head inventory tracking system, RV head RTD, and "A" to "B" power cables reconnected. The CRDM and APSR mechanisns were recoupled.
The RV head insulation was reinstalled and the deep end of the FTC drained and deconned.
The RV head missile shields were reinstalled above the reactor.
b (5
C703190138 670228 PDR ADOCK 05000289 R
PDR t
7
Valve DH-Y-1 (Decay Heat) Repacking Work - Valve DH-V-1 was repacked with the Chesterton packing program. Work included evaluation and testing of the RCS heatup rate to deterndne how long the Decay Heat Renoval System could be shut off.
Interference itens (snubber and fire detector) were renoved and the yoke clamp bolts were loosened. The valve operator along with the yoke assenbly were raised a few inches and set on blocks. The valve was then placed in the backseat position.
The packing was removed from the valve and new Chesterton packing installed. The valve was noved off the backseat and the operator and yoke assenbly lowered and reconnected to the valve body.
Interference items were reinstalled. The valve packing leak off line was eliminated by welding a plug in the valve bonnet and capping the drain line piping.
OPERATING DATA REPORT DOCKET NO.
50-289 DATE 2-28-87 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
FEBRUARY,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.
- 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 672.
1416.
109513.
- 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.
(, WH)
O.
O.
31518871.
- 17. GROSS ELECTRICAL ENERGY GENERATED M
(. WH) 0.
O.
29469975.
- 18. NET ELECTRICAL ENERGY GENERATED M
'19. UNIT SERVICE FACTOR 0.0 0.0 35.8
- 20. UNIT AVAILABILITY FACTOR 0.0 0.0 35.8
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 34.4
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 32.9
- 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 Refuelino Outaae.
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
March 25.1987
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE 2-28-87 COMPLETED BY C W. Smyth TELEPHONE (717) 948-8551
- MONTH: -FEBRUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0.
17 0.
1 2'
O.
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 0.
27-0.
12 0.
28 0.
13 0.
29 N/A 14 0.
30 N/A 15 0.
31 N/A 16 0.
50-289 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME TMI-I DATE 2-28-87 COMPLETED BY C.W..Smyth REPORT MONng FEBRUARY TELEPHONE i/1/) 948-8551 l
e e
y, 3 u, $
b **
c ee Cause & Corrective e
E4 Licensee g't.,
.E.
E 7
g g, a.
Action to No.
Daic g,
3g i
jg5 Event sy H
$5 5
jgg Report a N0 Prevent Recurrence 6
87-01 2/28/87 S
672 C
N/A N/A N/A N/A Shutdown for Refueling Outage 1
4 1
1 2
3 4
F: Fos ted Reason:
Method:
Ex!.iois G - Instructions S Stheduled A-fquipment FadureiLxplam) 1-Manual for Preparaison of Data B. Maintenance of Test 2-Manual Serarn.
Enity Shecis for Licensee C Refueling 4 Autonutie Scram.
Event Report (LER) FdeiNtlREG-D-Regulatory Resiriction 4-Other (tipl.imi 0161) l -Operator Training & l.itenw I umnution F Adnunistrative 5
Estnbit I SJme Source onal I.i ror (lipl.am l G Opera } Explain) 11 Other(
6 Actually used Exhibits F & 11 NUREG 0161
t.
REFUELING INFORMATION RE0 VEST 1.
Nane 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 25, 1987 (Estimated)
(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 7R)
If answer is yes, in general, what will these be?
Basic Refueling Report.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to cbtermine 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 cktermined.
5.
Scheduled date(s) for submitting proposed licensing action and supporting i nformation:
Novenber 1,1987.
6.
Inportant licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfornance analysis methods, significant changes in fuel design, new operating procedures:
None 7.
The number of fuel assenblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 284 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 assenblies:
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 assundng the present licensed capacity:
1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
A t
a GPU Nuclear Corporation gggf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Nurnber:
March 13, 1987 5211-87-2058 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 February, 1987 Enclosed please find two (2) copies of the February,1987 Honthly Operating Report for Three Mile Island Nuclear Station, Unit-1.
Si ncerely, l
pfukill H. D.
Vice President & Director, TMI-l HDH:DVH:spb cc: Dr. T. E. Murley R. Conte Attachments 0015C 6d
?
9
,I i
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation 2