ML19322A252
| ML19322A252 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/09/1979 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19322A251 | List: |
| References | |
| NUDOCS 7902280323 | |
| Download: ML19322A252 (7) | |
Text
..
s.
AVERAGE DAILY UNIT POWER LEVEL 50-289 Docket No.
1 Unit 02/09/79 Date D. G. Mitchell Completed By 921-6579 Telephone MONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne't)
(MWe-Net) 791 1
789 17 2
786 18 800 3
799 19 797 h
796 20 790 793 i
796 21 5
794 6
791 22 787 798 23 r
8 798 2h 784 801 789 9
25 788 795 26 10 787 792 27 11 787 783 28 12 788 779 29 13 788 14 791 30 791 789 31 15 16 791 l
7902280323
--a
OPERATINGDkTAREPORT Docket No.
50-289 -
~,
Date 02/09/79' Completed By D. G. Mitchells OPERATING STATUS Telephone 921-6579
.1.
Unit Name:
Three Mile Island 2.
Reporting Period:
January 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): 8h0 7
Max. Dependable Capacity (Net MWe):
776 8.
If Changes Occur in Capacity Ratings (Items No. 3 through 7) Sir.ce Last Report, Give Reasons:
NA 9
Power Level to which Restricted. If Any (Net MWe):
NA NA 10.
Reasons for Restrictions, If Any:
MONTli iR TO DATE Cumulative Thh 7hh 38713 11.
Hours in Reporting Period 12.
No. of Hours Reactor was Critical Thh.0 Thh.0 119h7.8 0.0 0.0 838.5 13 Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line 7h4.0 Thh.O 30796.0 ~
0.0 0.0 r;
15 Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWE) 18726h8 18726b&
viisiv s971 17 Gross Elect. Energy Generated (MWH) 62h721 62h791 951690s7
- 18. Net Electrical Energy Generated (MWH) 588664 58866h 23580679 100.0 100.0 79 6 19 Unit Service Factor 100.0 100.0 79.6 20.
Unit Availability Factor 102.0 102.0 77.0 21.
Unit Capacity Factor (Using MDC Net) 22.
Unit Capacity Factor (Using DER Net) 96.6 96.6 7h.h 23 Unit Forced Outage Rate 0.0 nn L.A 2h. Shutdowns Scheduled Over Next b Months (Type, Date, and Duration of Each):
Refuelinrr outarre 02/17/70 (Duration 6 weeks) 25 If Shut Down at End of Report Period ~, Estimated Date of Startups
- 26. Units In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l
-w
D k8m Em 3N% m9C S
yo
- e-oLCW CE-
=g 5Yo xl,4geP 3C en-om 3W
,%aa e e-x*(3G sser: wm MV r
t v
n) o ro 4aaU 9U18D y,e ga esan k*
=*'
e5S os 2
D ir n
f p
t u o
o g3 ee 98*
0OR w ras a ao s
nr eR rH a
dio s
r W a a* e a na=
u(
e ott nt e D
R htc enb t ua cen ehe ivu MSR LEN 8M 3 'o3E meg 8-W S'W E g* o i U,
Coc.
1
!GOh
? ??8'e$
Y{rg$e mk7% nNf*L 2" genn$a Fdp "hg5
[p7r*Bao"$$
?"a gar %on r8Q.*
mhg5 Ra5-
?@2sEm
?8 rsa E
?PG "k'Dk [* m4R-yPt g.
^$-[mc c
?@{.$n' E$ZS$#
?L M
$n@ 1EES e. d $,m E. W I uP rod e
7 a$n3E*
ll
[e@n ooE Myy mNf*L
\\NE5*
i"8.
o4oG E" ^WE$E
T!E-1 Operating Summary January 1979 Unit Performance The unit operated at essentially 100% full power, except for the power reductions described below.
The unit's output was reduced to 93% full power on January 4,1979, to reduce the overload condition on Heater Drain Pump 10 (HD-P1C) while post-maintenance alignment and testing was being completed on HD-P1B.
After placing HD-P1B in service, the unit was returned 100% full power.
The unit's output was reduced to 95% full power on January 6, 1979, to perform a scheduled Technical Specifications surveillance on the Main Steam Safety Valves.
On January 13, 1979, the unit's output was reduced to 65% full power to perform scheduled Turbine Stop Valve testing.
On January 17, 1979, the unit's output was reduced to 90% full power as a result of HD-Plc bearing failure. At the time of the failure, HD-P1A had been taken out of service to repair a casing leak, but it was returned to service to permit 100%
power operstionLwhile the hD-Plc bearing was being repaired.
The unit's output was reduced to 75% full power on January 17, 1979, due to the inadvertent closing of anextraction steam valve (EX-V1B) which supplies steam to the hB feedwater heater.
The condenser cleaning system was operated with abrasive Amertap balls from January 15, to the end of the month.
It is expected that the abrasive Amertap balls will be used until the 1979 refueling outage commences, which is scheduled for February 17, 1979, in an attempt to verify the condenser performance improvements indicated by the August 1978 abrasive Amertap ball tests.
l I
January Safety Related Maintenance Results of the inservice inspection test on DR-PlA indicate'd high vibration on the lower motor bearing, which required the pump to be taken out of service for repairs.
The following work was performed after the redundant pump, DR-PlB, was tested:
.a.
The pump was disassembled b.
The following pump parts were replaced:
1.
Bowl assembly 2.
Shaft 3
Bearings 4.
Tube c.
The pump was reassembled d.
A new motor was installed e.
Pump to motor alignment was checkei The inservice inspection test was performed on the rebuilt pump with satisfactory results, and the pump was returned to service.
All work vaa performed within the time limitatim set forth in TMI-1. Tehnical Specification 3.3.2.
l l
i.
~
REFUELI: G Ii!FOR"f,TIO:i RE1Ur3f 1.
Ilar.e of facility:
Three fIile Island Ifuelear Station, Unit 1 Scheduled date for, next refueling shutdottn:
2.
February 17, 1979 Scheduled datE for restart fo11ovids refueling:
3 April 2, 1979 Will refueling or resumption of operation.thereafter reqt; ire a technical 4.
specification change or other license amendment?
If answer is yes, wh'at, in general *, vill these 'be?
s 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 cluestions are associated with the core reload (Ref.
10 CFR Section 50.59)?
If no such review has taken plape, when is it scheduled?
Yes The Proposed Technical Specification for-Cycle-5 provide changes in.
the core protection safety limits, radial-local peak vaffesj quadrant power tilt limits, power imbal'ance limits, boron requirements, control rod position limits, and APSR limits'. Many of these new limits should be bounding for future cycles.
Scheduled date(s) for submitting proposed licensing action and supporting 5
information:
Technical Specification Change Request fro. 86 was submitted December 28, 1978.
Important licensing considerations associated with refueling, e.g., new 6.
or different fuel design or supplier, unreviewed design or perfomance analysis nothods, significant changes in fuel design, new operating procedures:
tr/A The number of fuel assemblics (a) in the core and (b) in the spent fuel 7
storage pool.
a) 177 b) 160 1-
'S.
e.
,The present licensed spent fuel' pool storage e,apacity and the size of any 8.
has been requested or 10 Planned, inercase in.licsncerl storage capacity th2, in number of fu'cl a:menblies :
The present licensel. capacity is e752.
There are no plannci increases at this time.
The projected da'te of the last refueling that can be dischar,ged to the-9 spent fuel pool assuming the present licensed capacity:
~
1986 is the last refueling. discharge which allows fill core'off-load capacity (177 fuel assemblies).
e O
O e
e J
e e
e e
g i
o o
e e
j e
9 4
e De e
iy a
D 9
9 I
e a
T 2-
^
..