ML19210D374
| ML19210D374 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/15/1979 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210D373 | List: |
| References | |
| NUDOCS 7911260368 | |
| Download: ML19210D374 (5) | |
Text
,.,
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-280 Unit 1
Date October 1970 Completed By D. G. Mitchell Telephone (215) 021-6979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
CNe-Net) 1
-5 17
-5 2
-5 18
-5 3
-h 19
-h h
-5 20 h
5
-5 21 h
h 6
-5 22 h
7
-5 23 8
-h 24
-5 9
-3 25
-5 10
-5 26
-5 11
-5
-5 12
-5
-5 13 '
-5 29
-5 14
-5 30
-5 15
-5 31
-5 16
-5
' "1 296 79112 60 3 h
OPERATING DATA REPORT Docket No.
50-289 Date October 1o70 Completed By D. G. Mitchell OPERATING STATUS Telephone (2151 021-6R70 1.
Unit Name: Three Mile Island Nuclear Station 2.
Reporting Period:
October 3
Licensed Thermal Power (MWt):
2535 h.
Nameplate Rating (Gross MWe):
871 5
Design Electrical Rating (Net MWe):
819 6.
Max. Dependable Capacity (Gross MVe): Sh0 7
Max. Dependable Capacity (Net MWe):
776 8.
If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:
9 Power Level to which Restricted. If Any (Net MWe):
10.
Reasons for Restrictions, If Any:
Month Yr. to date Cumulative Th5 7296.
hs26;.
11.
Hours in Reporting Period 12.
No. of Hours Reactor was Critical 0.0 1128.0 31731.8 0.0 0.0 838.5 13.
Reactor Reserve Shutdown Hours lb.
Hours Generator On-Line 0.0 1128.0 31180.0 0.0 0.0 0.0 15 Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
O.
2828hh8.
76531071.
17 Gross Elect. Energy Generated (MWH) 0.
945996.
25h8h330.
- 18. Net Electrical Energy Generated (MWH)
-3h02.
855311.
238h7326.
19 Unit Service Factor 0.0 15.5 68.o 0.0 15 5 68.9 20.
Unit Availability Factor 21.
Unit Capacity Factor (Using MDC Net)
-0.6 15 1 66.8 22.
Unit Capacity Factor (Using DER Net)
-0.6 lh.3 6h.3 100.0 82.0 17.7 23 Unit Forced Outage Rate 2h.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25 If Shut Down at End of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Co:::mercial Operation} :
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1 N l
?!97
UNIT SHUTDOWNS AND POWER REDUCTIONS Docket No.
50-287 Unit Name TMI 1 REPORT MONTH October Date 11/15/79 Completed By D. G. Mitchell Telephone (215) 921-6579 e
~~
l
{
System Component Cause and Corrective No.
Date Type a
n Code k Code 5 Action to gg g
og gg ng g
ggo g
g Prevent Recurrence d N [d 0'Ej N Il m 1
10/1/79 F
744 D
1 Regulatory Restraint Order 1: Forced 2 Reason; 3
" Exhibit G - Instructions F
Methodi S: Scheduled A-Equipment Failure (Explain) f r Preparation of Data 1-Manu al B-Maintenance or Test n
s for Mcensee 2-Manual Scram.
Event Report (LER) File C-Refueling 3-Automatic Scram.
-j D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & Licensee Examination
~
F-Administrative G-Operational Error (Explain)
Exhibit 1 - Same Source o
II-Other (Explain)
CO
OPERATING SIDDIARY Unit I remains in cold shutdown with the "B" Decay Heat Removal System providing core cooling.
MAJOR SAFETY RELATED MAINTENANCE Two of the several intergranular stress corrosion cracks were repaired in the Spent Fuel System. The details of these repairs will be reported in the November Operating Report.
1IO)
/
~ l 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 h. Will refueling or resumption of operation thereafter require a tecalical specification change or other license amendment? If answer is ye5, 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 infor=ation: 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 The number of fuel assemblies (a) in the core, and (b) in the spent fuel T. storage pool: (a) 177
- 7q (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: 1986 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies). .}}