ML20004G058
| ML20004G058 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/15/1981 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML20004G057 | List: |
| References | |
| NUDOCS 8106290067 | |
| Download: ML20004G058 (5) | |
Text
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OPERATING DATA REPORT DOCKER..e 50-289 DATE T-15 - 1981 COMPLETED BY i C '"itchell i
TELEPHONE
'717) 948-8553 l
.1 OPERATING STATUS Three Mile Islano Nuclear Statich, Unit I
- 1. Unit Name-May 1981
- 2. Reporting Period:
2535
- 3. Licensed Thermal Power (MWt):
871
- 4. Nameplate Rating (Gross MWe):
019 5.' Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross Mwen p0
- D
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur la Capadty Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To Which Restricted. lf Any (Net MWe):
- 10. Reasons For Restrictions.If Any:
This Month Yr to-Date Cumulatise 744-3623.
59136.
i1. Hours In Reporting Period 0.0 0.0 31731.a
- 12. Number Of Hours Reactor Was Critica!
0.0 co n,o,;
- 13. Reactor Reserve Shutdown Hours
^
0.0 0.0 31130,9
- 14. Hours Generator On.Line U*U 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 7653,1071.
- 16. Gross Thermal Energy Generated (MWH)
U*
0.
Za e*330.
- 17. Gross Electrical Energy Generated (MWH) u.
u.
4ao*uuaa.
- 18. Net Electrical Energy Generated (MWH) 0.0 0,o 52.7
- 19. Unit Service Factor U.0 U.o 52.7
- 20. Unit Availability Factor 0.0 0.0 51.3
- 21. Unit Capacity Factor (Using MDC Net)
~
0.0 0.0 49.2
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 39.8
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each t.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation b Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION
- 100gpi;Q M
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AVER AGE DAl'.i 1; NIT POWER LEVEL DOCKET NO.
50-289 TMI-I WIT DATE June 15. 1981 COMPLETED BY D-C.'Mitchell I
TELEPHONE (717) 948-8553 MONTH Mav 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mhe-Net) g g w,.3,g, t
0 37 o
2 0
0 18 3
0 0
39 4
0 0
20 5
0 0
21 6
0 o
7 0
o 3
a 0
0 24 9
25 0
0 j
10 26 0
Il 27 0
0 12 28 0
0
- 13 29 0
0 14 30 0
15 0
0 31 16 0
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50-289 DOCKET NO.
UNIT Sil01 DOWNS AND POWER REDl!CTIONS UNIT NAME llII-I DATE.itme 15. 1981 COMPLE1ED RY D C Mitefir11 Q
REPORT MONilg May 1981 TELEPilONE (717) 948-8553 g
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e tS CCD Regulatory hestraint Order 1
5/1/81 F
744 D
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2 3
4 F: Forced Reason:
Metimd:
Entdbit G -Instructions l
S: Scheduled A E:lulpment Failure (Explain) 1 Manual for riepasation of Data B Maintenance of Test 2 Manual Scrain.
Entry Slicens for Licensee 1 Automatic Scram.
Event Report (LFRIl'ile INtlRIG-i C Refueling D-Regulatory Restriction 4 Oil.cr (Explain) 01611 E. Operator Training A Ucense Examination F Administsative 5
INiiihit I-Same Source onal Error (Esplain)
G-Operat}E-nlaini Il-Ottier (
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,w, OPERATIONS
SUMMARY
The Unit was shutdown the entire month of May by order of the
-NRC.' Core cooling was provided by the Decay Heat Removal System.
MAJOR SAFETY RELATED MAINTENANCE During the month, while the Unit remained in the cold shutdown condition with restart activities continuing, the following major maintenance work was performed.
- 1) Decay Heat River Water Pump 1A was overhauled to eliminate high vibrations recently encountered on the pump shaf t.
The overhaul included removal, overhaul, and balancing of the motor, removal and. inspection of the pump shaf ts and housing, and in-stallation of new pump impeller bearings and line shaf ts.
The impeller was balanced and reinstalled and the bowl housing was I
inspected and reused.
Reinsta11ation of the. pump will continue into June.
l
- 2) Condensate Storage Tanks IA and IB were modified to remove the l
bladders which had been installed to minimize oxygen concentration in the water. The work included internal cleaning and inspection of the tank and installation of a new suction line screen. Work was. completed and both tanks are now refilled.
l 3)0nce Through S. team Generator "B" primary upper and lower manway and upper and lower handhole covers - work included removal of one (1) nut at a time, removal of stud lubricante, relube, re-installation of nut, and retorque. This work was performed satisfactorily.
A nspection of the bearings an Reactor Building purge valve "D" f
l (AH-V-1D) was performed. Work included:
Removal of pneumatic operator, removal / inspection of bearings, and installation of new bearings. After completion of the above work the rubber seats of both l
AH-V-1C/1D were replaced. Replacement work included-removal of duct section, removal of segment bolts and rubber seats, installation of an improved rubber seat material, and torquing of segment bolts.
Both of these jobs (seat replacement and bearing inspection) will be completed during P.he month of June.
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- 5) Repairs to WDG-V-4 were performed with acceptable r esults. The valve was taken apart,'a new disc was installed after a blue L
check verified the seating surf ace was good, the valve was re-assembled. Local leak rate testing of the valve was performed with acceptable results.
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REFUELING IhTORMATION REOUEST 1.
Name of Jacility:
i?.ree Mile Island Nuclear Station, Unit I 2.
Scheduled date for next refueling shutdown:
Unknown I
3.
Scheduled date for restart following refueling:
Unknown
~
4.
Will refueling or resumption of operation thereafter require a tec.nical 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 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 7.
The number of fuel assemblies-(a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 208
~~
i 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:
1986 is the last refueline discharge which allows full core off-load capacity (177 fuel assemblies).
.