ML19220A932
| ML19220A932 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/11/1978 |
| From: | Lengel R Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19220A929 | List: |
| References | |
| MOR-780630, NUDOCS 7904250105 | |
| Download: ML19220A932 (4) | |
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......s test venicr =cdified main stesa safety valves. Safety valve testing continued with = satisfactory results unnil June h, when plant eccidevn ec= enced for the removal of these safety valves and the reacter vessel head.
v.cde 5 was entered en June 5 and cutage va-> +- enced.
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3 On June ik, the reactor plen= vas rencved and ccre work cccrenced. On J=e 15, crifice rod removal sas ec=pleted. Cn June 16, inspection of L3F3s and instal-lation of hcid devn devices was ccepleted. L3PR hold devn verification was ecc-pleted en June 17 and reacter internals installation ecc=enced.
Cn June 19, the reactor vessel head was set in place. Fresently, cutage verk is centinuing including replace =ent of the 12 main steam safety valves with 20 new vs.1ves of a.u.n_..._.-... a, s.,.
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,t A7ERAGE DAILY UNIT PC'4ER LEVEL Decket No.
90 120 Unit Tr -2 Date
-11 72 Cc=pleted 3y F. A.
Eer ra'-
Telepher:e 215 02c 1601 Ect, ih3 DAY A7ERAGE DAILY FC'4ER LI7EL" DAY A7ERAGE DA'LY FC'4ER LEVEL *
(M*4e-Net )
(TJe-Net) i 1
-J'-
17
-4
~3,'
16 2
a 3
19 h
-33 20 h
5 21 0
-13 6
22 k
-12
-12 h
7 23
-9 2h 2
8 h
-"i o
25 "i
10 26 d
h 1
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A 9
A
,o 2e h
13 29 1,
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le-
- 2e negative numbers indicate that =cre enerry was supplied to the =it than was used by it.
Sese n=bers are prcvided for your infocation caly, r 9., - - e s7,)
1 r.
CPERATI'!G DATA REPCRT Decket No.
50-320 Date 8-aa iO Cc=pleted Dy R. A. :errel l '.
' dFfRATING STA'JS Telephone M c c2c. M m r- -
1.
Unit Name:
"'hree Mile Island Unit 2
'Jun e 2.
Reporting Period:
3 Licensed "'her=al Power (Y4t): 2-0c h.
Na=eplate Rating (Gross Fie): 961 5
Design Ele ctrical Rating (Net K4e'.
906 6.
Max. Depeniable Capacity (Grcss W4e): 930 7.
Max. Depr.ndable Capacity (Net Kie):
CC" 8.
If Changes Occur in Capaci+y Ratings (Ite=s No. 3 t - : ugh 7) Since Last Repert, Give Reasons:
9 Power Level to which Restricted. If Any (Net rae):
2c63 'N 10.
Rest.cns fcr Restrictions, If Any:
Pcver is limited pending additicnal 3r4 analysis
^f Sns11 3reak LCCA.
Bis Menth Yr.-to-Date Cu=ulative 720
- u. 5 2m
^^~
11.
Hours in Reporting Period V
342.2 342.2 12.
No. of Ecurs Reacter was Critical oc 636 636 13.
Reactor Reserve Shutdevn Hours lb.
Ecurs Generater On-Line 0
h2 L2 0
15 Unit Reserve Shutdcw. Ecurs 0
3 16.
Gross Thermal Energy Generated (K4H) 0 37921 37921 17 Gross Elect. Energy Generated (F4H) 0 4292 a2c2 h57CS 18.
Net Electrical Energy Generated (W4H)
-6sc7
_Le--o 19 Unit Service Facter N/A N/A N/A 20.
Unit Availability Factor N/A N/A N/A 21.
Unit Capacity Factor (Using MDC Net)
N/A N/A N/ A 22.
Unit Capacity Facter (Using DER Net)
N/A Ti/A 27 / 1 N/A 23.
Unit ? creed Cutage Rate N/A
/s 2h.
Shutdowns Scheduled Over Nex+, 6 Menths (Type, Date, and Duratien of Each):
25 If Shut Devn at End of Report Period, Estimated Date of Startup s c ?S
- 26. Units In Test Status (Prior to Cc==ercial Cperatien):
FCRECAS"'
ACHII'/ED INITIAL CRITICALITY 3-9-78 3-2S 73 INITIAL ELEC"'RICITY 3-ic-,A h-21_~c_
CCMMERCIAL OPERATICN 9-1-75 v 7.. ngay e
1..