ML19322A222
| ML19322A222 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/10/1979 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19322A221 | List: |
| References | |
| NUDOCS 7901180142 | |
| Download: ML19322A222 (6) | |
Text
_ _ _ _ _ _ _ - _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ __
P DECEMBER, 1978 TMI-l OPERATING
SUMMARY
Although experiencing high pressure feedwater leaks, the Unit operated at 100% Reactor Power until December 3,1978 when it reduced to 97% full power.
in order to evaluate a heater drain pump 1-C (HD-P-lC) overload condition following the HD-P-1B bearing failure.
The Unit escalated back to 100%
power until December 10, 1978 when a bearing failure on HD-P-1 A (with HD-P-1B still out of service for repairs) caused reduction to 75% power.
While at reduced power, the "B" high pressure feedwater string was iso-latad to reduce the heater drain loading on HD-P-lC.
HD-P-1B was placed back in service late on 12/10/78 and the Unit began to escalate back to 100% (obtaining approximately 90%) but again was reduced to 75% when HD-P-1B suffered a bearing failure and broken shaft.
(HD-P-1Astill out of service for repairs). While at 75% power,because of the unavail-ability of a second heater drain pump, it was decided on December 11, 1978 to go /
to 65% power and conduct the Turbine Stop Valve Testing.
With the Turb... Stop Valve Testing complete and with two operable heater drain pumps (HD-P-1 A and HD-P-lC) the Unit escalated back to 100% full power on 12/11/78, however the "B" High Pressure Heater String remained isolated.
HD-P-1B remained out of service for the remainder of the month to perform a complete pump overhaul. During the week of 12/18/78, after successfully isolating the 48 High Pressure Heater, six failed tubes were plugged.
Known tube failures in the 2B Heater could not be repaired due to incomplete isolation of the 2B Heater. The "B" High Pressure Heater String was placed back into service on 12/21/78 regaining approximately 14 MWe in generation.
The Unit remained at full power for the remainder of the month.
MAJOR SAFETY RELATED MAINTENANCE There i as no major safety related maintenance performed during the month.
l; 7901186FQ.
6.
L>
- AVERAGE DAILY UNIT POWER LEVEL ~
i Docket No.
50-289
^
Unit 1
Date 1/10/7 9 I
Completed By D. G. Mitchell Telephone 921-6579 MONTH December 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
-(MWe-Net)
-1 781 17 778 I
2 781 18 781 3
778 19 784 h
778 20 786 5-787 21 786 6
786 22 799 i
-7 784 23 802 802 8
781 2h l
9 78h 25 797 j
10 724 26 803 i
11 772 27 803 12 796 28 804 j
_13 793 29 795 1h 793 30 799 800 15 791 31 16 784 i
l OPERATING DATA REPORT Docket No.90-289 Date January 10, 1979
)
D.G. Mitchell Completed By OPERATING STATUS Telephone 921-6579 1.
Unit Name:
Three Mile Island Nuclear Sta., Unit 1 2.
Reporting Period: December 1978 3
Licensed Thermal Power (Wt):
2535 k.
Nameplate Rating (Gross We):
871 5
Design Electrical Rating (Net We): 619 d40 6.
Max. Dependable Capacity (Gross We):
7 Max. Dependable Capacity (Net We):
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 An" (Net MWe):
10.
Reasons for Restrictions, If Any:
Month YR to dat~e Cummulative 7hh 8760 37969 11.
Hours in Reporting Period 7545.5 30603.8 12.
No. of Hours Reactor was Critical Thh.0 0.0 0.0 838.5 13.
Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line 7h4.0 Th55.h 30052.9 0.0 0.0 0.0 15 Unit Reserve Shutdown Hours 16.
Gross Thermal Energy Generated (WH) 18_65952 18309058 73702623 17 Gross Elect. Energy Generated (MWH) 622006 6044532 24538334
- 18. Net Electrical Energy Generated (MWH) 585905 5673616 22992015 100.0 85.1 79.2 19 Unit Service Factor 20.
Unit Availability Factor 100.0 85.1 7o.9 21.
Unit Capacity Factor (Using MDC Net) 101.5 82.1 76.5 22.
Unit Capacity Factor (Using DER Net) 96.2 79.1 73.9 0.0 2.8 h.9 23 Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling 2/17/79,6 weeks.
25 If Shut Down at End of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY C0!O!ERCIAL OPERATION
gg8 m.
9amne i%
CO28U goX0
?*
biMc\\oO 3
E CEd Z8G YH:H 5
dhf o$8do HosH\\O d%G hU hag 4 #
O. O
- l+ o'DO c
sGH lsG ONH1 w
N r
t v
W n) o ro CNnaa 9Ut 3h&
!e h*oo*Meo+cr@
O 1
ZO*
D%@
G os D
i r n
f p
oOg "
oOa
>o r8
+O t u O
O g3 ee c
aO S
nr eR rH a
dio s
r k@m p Fog *MoDoC 1
u(
e ott nt e D
R htc enb t ua cen ehe ivu MSR LEN ZOZM
-c 1
H. NO N 8 N0 W
YEdH 1
H bm +c
- C Oam N.
2o 8
Z +Cha -
M. Oo EWGA
>I p rt1h+c mEEy ^ fg* b
$" NMh4P+cMOp OM O.+cp H
bB
.C 7
tI y+cm $8 O Rmmt
$ "k h 8 em %O' t
1 "t o omOO 2
N bE mo c
^t"Mtv % Ho d
$8d B1t OI 2GH m u
- e 4
c O!E o C hB.
t !
^$Mo oEH v Ci A O4 E5Eo+c g r
'p0 ' RN H mE Me d@ A e 4$d$ P [gDh pMg oaEo t
)
%i rDH M5 7*
1 a
>YE&r ~
I U PlG C C,oe
\\
D 3
Ogd@A+c OaE M@Q nhy*b E
- I
?M E%$O Q
1
.\\
REFUELING INFORMATION REQUEST 1.
Name of facility:
Three Mile Ti Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
I February 17, 1979 3
Scheduled date for restart following refueling:
March 16, 1978 h.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
If answer is yes, what, in general, 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?
Yes The Proposed Technical Specifications for Cycle 5 provide changes in the core protection safety limits, radial local peak valves quadrant power tilt limits, power bnbilance limits, boron requirements, control rod position limits, and APSR limits. Many of these new limits should be bounding for future cycles.
5 Scheduled date(s) for submitting proposed licensing action and supporting u1 formation :
Technical Specification Change Request No. 86 was submitted December 28, 1978.
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 T.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 160 m
\\
e o
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).