ML19322A316
| ML19322A316 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/05/1979 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19322A315 | List: |
| References | |
| NUDOCS 7904190037 | |
| Download: ML19322A316 (4) | |
Text
-
. AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-289 Unit TfE-1 h/5/79 Date-D. G. Mitchell Completed By 215-921-6579 Telephone MONTH March 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe *Te't)
(Mile-Net)
-10 1
-6 17
-10 6
18 2
-10 3
-7 19
-10 h
-6 20
-11 5
-6 21
-13 6
-6 22 7
-6 23
-13
'8
-6 24
-13 9
-5 25
-18
-6
'L6
-28 10
-6 27
-38 11 12
-6
-28 41
-13
-5 29
-37 14
-5 30
-18 31
-13 15.
16
-10 790419003 7 L..
.I
OPERATING DATA REPORT Docket No._
50-289
~
Date h/5/79 Completed By D.C. Mitchell TPERATING STATUS Telephone 215-921-6579 1.
Unit Name:
Three Mile Island Unit 1
-2.
Reporting Period:
March 1979 3
Licensed Thermal Power (MWt):
2535 4.
Nameplate Rating (Gross MWe):
871 5.
Design Electrical Rating (Net MWe): 819 6.
Max. Dependable Capacity (Gross MWe): 840 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:
4 MONTH YR-TO-DATE CUMULATIVE 744 2160
'h0129 11.
Hours in Reporting Period 12.
No. of Hours Reactor was Critical 0
1128 31731.8 13 Reactor Reserve Shutdown Hours 0
0
_ 898.'5
- 14. Hours Generator On-Line 0
1128 31180.9 0
0 0
15 Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 0 2828hh8 76531071 17 Gross Elect. Energy Generated (MWH) 0 945996 25h84330
- 18. Net Electrical Energy Generated (MWH)
-9147 8795h8 23871563 0
52.2 77.7 19 Unit Service Factor 20.
Unit Availability Factor 0
52.2 77.7 21.
Unit Capacity Factor (Using MDC Net) 0 52.5 75.3 22.
Unit Capacity Factor (Using DER Net) 0 49 7 72.6 0
0 h.8
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duratior of Each):
25 If Shut Down at End of Report Period, Estimated Date of Startup Unknown
- 26. Units In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL E1ECTRICITY COMMERCIAL OPERATION
I 1l1 l
,!ll
$O aO, i= w$chBM 8,E* E.
wPe*
h6m 5g
=l 3s
- &8a IOh xGo" e%.
y3t*
nON & 4 nPxt yg-e
-&e?mG oaeN,mke r
t v
yg n) o ro mNm$a o8y0g" S a gn aoMMma7*
os g
D i r n
f p
oOa* -
9gu gaa dO t u o
og ee ao s
nr eR rH a
dio s
r W2g* y,gMMmga u(
e ott nt e D
R htc enb t ua cen ehe ivu MSR LEN e
wb4*
m
- e n
H a
w $ab^
"Wa9p a l
HOa@r O H*
mOA1 N h o".
x
- mo52Xa
>'n#c 7a @r m$ y g m@%Ba" 2, m j a P#*O" % en&
t whmb%
n %0 %a3a 8 oM gw&
W 4 md.d# Me eEoU @o nSe b % mo g.
t E.S weeg ^MB m H abh wym w! o?aa m4B-r
~ g mP nm~"
eb*Iwg4 ygQa&$"
w'hr Rg 5E n o3Bs@ #* D,g W e7@m8 %gn,Cg t
nb$E " M%yS E3egn% ggg mW$3n" Wa9 vI M n m8MO nbE@ ^ WE$D
\\
1
i
-1 8
t J.
OPERATING
SUMMARY
^
The unit _vas shutdown during the entire month-of March. On March 27, primary system heatup was commenced..On March 28, while preparing for criticality, Unit 2 underwent a turbine trip and a subsequent reactor trip..- Following the incident, the.. decision was made to return Unit 1 to a cold' shutdown condition..This was done and the unit has remained
. in cold shutdown through -the end of the report period.
5 I-MAJOR SAFWPY RELATED MAINTENANCE 1
The unit continued in a refueling / maintenance outage status. The
- following major maintenance evolutions vere completed:
4-
^
- 1, Corpleted fuel shuffle 2.
Performed core verification-i'
-3.
Installed reactor vessel plenum h.
Installed reactor vessel. seal plate 5. Installed'and tensioned reactor vessel he._
]
~.6.
Installed reactor vessel head insulation and fans
'7 Coupled.APSRs:and CRDMs 8.
Connected CRDM/PI cables 1
-9'. ' Inspections. vere performed on RCP-1A and 1D seals. While performing a motor inspection on RCP-1C, two shoes of the upper guide bearing were found partially wiped and were replaced.
~
i' All; disassembled RCPs were coupled, aligned, and balanced.
~ 10.
Corrective' maintenance-vas' performed on EG-Y-1Bl(emergency diesel)
I injectors 11.
Control rods were drop tested 12.
19 new incore detectors were installed-I 13.
RC-RV-1B tested satisfactorily within limits.
4 t'
t -
I o
4 g._
1 I
s 4
{
w w-
-r-.r
-*?-
-+
e-m ee+.y-
+
eWW ' e
+w*
F-+
e-m 4
--r-+-m
7 REFUELING TNFORMATION REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
i Unknown 3.
Scheduled date for restart following refueling:
Unknown h.
Will refueling or resumption ot* operation thereafter require a technical specification change or other license amendment?
If answer in 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 nafot.y rpinntionn nro acroc int.od wi th the co rt-rel oad (Ref.
' o f.' FH. ;ec L t on
'.>0. 'f))'s If no such review has taken place, when is it schedulel?
Amendment No. 50, Cycle 5 reload, was approved on 3-16-79 Scheduled date(s) for submitting proposed licensing action and supporting 5
in formation :
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
,f 7
The number of fuel assemblies (a) in the core', and (b) in the spent fuel storage pool:
(a) 177 (b) 212
}
8.
The present licensed spent thel 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:
?
\\
4 The present licensed capacity is 752. There are no planned increases
~
at this time.
J 9
The projected date of the last refueling that can be discharged ot the spent fuel pool' assuming the present licensed capacity:
s 1986 is the last refueling discharge whi,ch allows full core off-loal capacity (177 fuel assemblies).
-