ML20027D418
| ML20027D418 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/15/1981 |
| From: | Smyth C METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML20027D417 | List: |
| References | |
| NUDOCS 8211040269 | |
| Download: ML20027D418 (5) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE october 15, 1981 COMPLETED BY _ C. W. Smyth TELEPHONE (73 7) 968-8551 OPERATING STATUS Three Mile Island Nuclear Station, Unit I
- 1. Unit Name:
September, 1981
- 2. Reporting Period:
2535
- 3. Licensed Thermal Power (MWt):
871
- 4. Nameplate Rating (Gross MWe):
819
- 5. Design Electrical Rating (Net MWe):
840
- 6. Maximum Dependable Capacity (Gross MWe):
/76
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Thmugh 7) Since Last Report. Give Reasons:
- 9. Power Leve! To Which Restricted,If Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
This Month Yr..to.Date Cumulative 720.
c;:-l.
62064.
- 11. Hours In Reporting Period 0.0 0.0 31731.8
- 12. Number Of Hours Reactor Was Critica]
0.0 0.0 839.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9
- 14. Hours Generator On.Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.
IC. Gmss Thermal Energy Generated (MWH)
O.
O.
25464330.
- 17. Gross Electrical Energy Generated (MWH) u.
23d,4 m 3.
u.
- 18. Net Electrical Energy Generated (MWH) 0.0 0.0 50.2
- 19. Unit Service Factor U*U UU 50.2
- 20. Unit Availability Factor 0.0 0.0 48.9
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 go
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 43.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
Forecast Achieved
- 26. Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 4
8211040269 211015 pW7 3 PDR ADOCK 05000289 R
8 PDR
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 IMI-I WIT October 15, 1981 DATE COMPLETED Ey C. W. Smvth (717) 948-8551 TELEPHONE September, 1981 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(Mwe. Net i 1
0 37 0
0 2
0 y3 0
3 0
39 0
4 0
20 0
5 0
21 0
6 0
23 0
7 0
23 0
0 8
24 0
0 9
25 10 26 0
0 11 27 0
12
- s 0
0 13 29 0
0 14 30 0
0 15 31 0
16 l
l l
t 50-289 DOCKET NO.
UNil SilU1 DOWNS AND POWER REDUCTIONS
'IMI-I UNIT N AME DATE October 15. 1981 COMPLETED BY C. W.
Smyth REPORT MON 111 September, 1981 11?LEPflONE (717)948-8551 i
i "t
.$ E Y
Licensee Eg h
Cause & Corrective 84 3g&
No.
Date h
Wg 3
Action to Event t; ?
fU dE E
jdg Report 8r NO Prevent Recurrence H
d egu a ry estraint Order j
1 9/1/81 F
720 D
1 i,
i I'
I 2
3 4
l F: Forced Reason:
Methml:
Exhibit G. Instructions 5: Scheduled A. Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2 Manual Scram.
Entry Sheels for 1.icensee C Refueling 3 Automatic Scram.
Event ReporI (l.ER) File (NilRI'G-3 D Regulatory Restriction 4-Other (Explain) 0161)
E Operator Training & l.icense Examination F Administrative 5
j 3
G-Operat)onal Error (Explain t Exhihii I. S ame Source ll Other (Explain) i 1
i
MGNTHLY OPERATIEG REPORT Operating Summary Hot Functional Testing was being completed at the beginning of this report period. Testing performed was described in the August Operating Report. On September 9, 1981, the Unit was returned to cold shutdown where it has remained the remainder of this report period.
Major Safety Related Maintenance While operating at 2155 psi, 532 F, Decay Heat Valve, DH-V-1, developed a small seal ring leak. Repair to the valve was performed by rein-jecting furmanite into the seal ring area. The leakage from the seal ring area was reduced. The leakage was stopped when the system was placed in-service.
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REFUELING INFORMATION REOUESI i
f
)
4 i
1.
Name of Facility:
l Three Mile Is, land Nuclear Station, Unit I 2.
Scheduled date for next refueling shutdown-Unknown 3.
Scheduled date for restart following refueling:
Unknown 4.
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.
1 2
5.
Scheduled date (s) for submitting proposed licensing action and supporting information:
N/A 6.
Important licensing considerations associated with refueling, e.g. new i
or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
I N/A 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.
I 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 refueling discharge which allows full core off-load capacity (177 fuel assemblies).
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