ML19220A854
| ML19220A854 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/01/1978 |
| From: | Lengel R Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19220A851 | List: |
| References | |
| MOR-780228, NUDOCS 7904250037 | |
| Download: ML19220A854 (6) | |
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AVERAGE DAILY U' TIT PCWER TiEL Docket :To.
30 220 Un'.t TM!-2 Da -
'- a h 1.
1^7C Cc=?leted By F.
A. ' enzel Telephone 215 020-?601. Ext. ILS DAY A7ERAGE DAILY FCWER EIEL DAY A7ERAGE DAILY PCWER CIEL C&e-Net)
(MWe-Net) i 1
-c 17 2
-6 18 k
3
-c 19
-c h
-5 20
-3 5
-5 21 0
6
-6 22
-9 7
-6 23
-9 8
-6 2h
-10 9
-6 25
-10 10
-6 26
-10 11
-5 27
-10 12
-5 28
-9 13 k
29
- IA lh
-3 30
- IA 15 h
31
- IA 16
-5 t[~=(}. Q v3 mL, k b V
CPERATING DATA REPCRT Decket No.
- n en Date
'!1rch 1,1979 R
A-L*E2*i Conpleted Sy CPE'ATING STA"US Telephcne o ^c-?
"c
,a y~-^
1.
Unit Name:
'hraa ila Island Unit 2 2.
Reporting Period: Feb.~22*7 107 3
Licensed Ther=e.1 Power (E4t):
'~72 k.
Naneplate Rating (Gress M'Je):
901 5
Design Electriesi Rating (Net M*40): cre 6.
Max. Dependable Capacity (Gross M'4e):
- e 7
Mc.. Dependable Capacity (Net M'4e):
8.
If Changes Occur in Capacitf Ratings (Items No. 3 through 7) Since last Report, Give Reasons:
'I /.i.
9 Pover Level to which Restricted. If An.v (Nct T4e):
'!/A 3/A 10.
Reasons fer Restrictions, If Any:
ve vrN-"I YR. TO DATE
'""CIAT:'lE
., n 2j^.
7lg 11.
Hours in Reporting I'eriod 12.
No. of Hours Reacto:. ras Critical 13 Reactor Reserve Shutdown Hours 14.
Hours Generator On-Line 15 Unit Reserve Shutdevn Hours 16.
Gross Thermal Energy Generatd (M'4H) 17 Gross Elect. Energr Generated (M'4H) 18.
Net Electrical Energy Generated (M'4H) 19 Unit Service Factor 20.
Unit Availability Factor 21.
Unit Capccity Fac;cr (Using MDC Net) 22.
Unit Capacity Factor (Using DER Net) 23 Unit Forced Outage Rate 2h.
Shutdevns Scheduled Over Next 6 Months (Type, Date, and Duratien of Each):
N/A 25 If Shut Jevn at End of Repcrt Period, Estimated Date of Startupt N/A
- 26. Units In Test Status (?rior to Cc==ercial Operation):
FCRECAST ACHIEVED INI'"IAL CRITICALITY
?/25/79 INI"'IAL ELEC"RICI"'Y WOL/~9 CCMMERCIAL OPES.ATION
- '? - /- o i ~ p.
<w,.
I
%k
UNIT S!!UTDOWHS AND POWER REDUCTIONS Docket No.
5 0-1: >i)
Unit Name
'ng_p REPORT MONTl!
p,.1,,,,,,,,.;,
Date M:t t'c h 1, 19'f 8 Completed By it. A.
1,e n,,e j Telephone P I 'i-9.o9 - 3(,01, E x t. Iht No.
Date Type S7
'h l
m System Component Cause and Corrective
.
- 5. A p.
Code h C d* 5 Action to o
o em oo eg
- f..c E
,o d 'o Prevent Recurrence d
y j *' 4' y jj j a d =!i
R o si
- x tn m f
I l
i IF; Forced 211eason:
3
" Exhibit G - Instructions Methode y
S: Scheduled A-Equipment Failure (Explain)
"E"""
1-Manu al C
B-Maintenance or Test 2-Manual Scram.
C-Refueling Event Report (LER) File 3-Automatic Screim.
f'y D-Regulatory liestriction
(
gg )
b-Other (Explain) h.
E-Operator Training & Licensee Examination Z
F-Administrative S
G-Operational Error (Explain)
Exhibit 1 - Sume Pource Il-Other (Explain) i
t REFUELING INFORPATION RECUEST
- 1. Name of Facility.
Three Mile Island - Unit 2
- 2. Scheduled date for next refueling shutdown.
15 September,1979
- 3. Scheduled date for restart following refueling.
24 Novembar, 1979
- 4. Will refueling or resumption of operation thereafter require a tecnnical specification change cr other license amendment?
Yes If answer is yes, what, in general, will these be?
The Technical Specification change for Cycle 2 will provide revised operating limit curves, rod withdrawal index limits and power imbalance 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)?
N/A If no such review has taken place, when is it scheduled?
N/A
- 5. Scheauled date(s) for submitting proposed licensing action and supporting information?
15 June 1979
- 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 assemblies (b) 0 assenblies
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested o
- planned, in number of fuel assemblies.
Present - 442 assemblies Planned - 829 assemblies based on estimates from TMI-l pool B expansion
- 9. The projected date of the last refuelin9 that can be discharged to the spent fuel pool assuming the present licensed capacity.
Oct. 1982 - based on core off load capability Oct.1986 - without core off load capability 70' TA9