ML19224A504
| ML19224A504 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/09/1979 |
| From: | Lengel R Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19224A502 | List: |
| References | |
| MOR-790131, NUDOCS 7902220071 | |
| Download: ML19224A504 (4) | |
Text
'.j., k~
OPERATING DATA REPORT Docket No.
50-320 Date 2/ 9/79 R. A.
Lengel Completed By OPERATING STATUS Telephone 921-05d1 1.
Unit Name:
Three Mile Island 2.
Reporting Period:
January 1979 3
Licensed Thermal Power (!Nt):
2772 9Ul h.
Nameplate Rating (Gross M'de):
5 Design Electrical Rating (Net INe):
906 6.
Max. Dependable Capacity (Gross 'Ge): 930 7
Max. Dependable Capacity (Net M'Je):
8.
If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:
NA 9
Power Level to which Restricted. If Any (Net !Ge):
NA 10.
Reasons for Restrictions, If Any:
tm huu ut m 10 DAu.
CWOIULATIVE Thh 7hh 760 11.
Hours in Reporting Period 12.
No. of Hours Reactor was Critical 336.6 336.6 M, 6 407.h 407.4 h07.h 33 Reactor Reserve Shutdown Huurs lb.
Hours Generator On-Line 319.8 319.8 3hh.8 0.0 0.0 0.0 15 Urrit Reserve-Shutdown Hours 16.
Cross Thermal Energy Generated (!NH) 730h88 T30h88 787032 17 Gross Elect. Energy Generated (!GH) 251662 251662 271h61 18.
Net Electrical Energ,f Generated (!GH) 2319769 2319769 250685 43.0 h3.0 hh.8 19 Unit Service Factor 43.0 43.0 hh.8 20.
Unit Availability Factor 21.
Unit Capacity Factor dising MDC Net) 35.h 1s.h
,q,
22.
Unit Capacity Factor (Using DER Net) 3h.h 3h.h 37.2 57 7 57 7 55.8 23 Unit Forced Outage Rate 2h.
Shutdowns Scheduled Cver Next 6 Months (Type, Date, and Duration of Each):
25 If Shut Down at End of Repor t Period, Estimated Date of Startup; 26.
Jnits In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY 3/9/78 3/28/78 3/15/78 h/21/78 INITIAL ELECTRICITY
_l?/ W 78 12/30/78 C0!YZRCIAL OPERATION erg P
7 9 0 2 2 2 o e ~/ /
AVERAGE DAILY UNIT PO'4ER LEVEL
. g.
Docket No, 50-320 Unit TMI-2 2/ 8 /79 Date Completed By R. A. Lengel 921-6581 Telephone MOImi Janti try DAY AVERAGE DAILY P0'JER LEVEL DAY AVERAGE DAILY POWER LEVEL
(!Ge-Net )
(!Ge-Net )
1 757*
17
-9 2
262 18
-5 3
779 19
-5 h
820 20
-5 5
800 21
-5
-8 6
823 22
-8 7
826 23 8
82h 2h
-8
-8 c.
771 25
-8 13 500 26
-8 11 6h6 27 12 829 28
-9
-10 13 827 29
-32 14 28'9 30 15
-32 31 99 16
-13
- NOTE: Negative numbers indicate that more energy was used by the unit than was generated by it, and are included for your information only.
- t) 4 -10
U'iIT SHUTD0' alls AND F0WER REDUCTIONS Docket No.
50-320 J',
Unit Name Unit 2 REPORT MONTH uanuary y
Date 2/9/79 Completed By R. A. Lengel Telephone 921-6531 5
U l
c-No.
Date Type og g
S g
System Component Cause and Corrective Code b Code 5 Action to ae o
o en oo 2 o a
e%
o Cu L3 g
g3o g,g Prevent Recurrence fYE SE#
r !i o.c o
~a ta ca a ca =
Turbine taken oft line to repair hydraulic 1
1/2/79 F 11.5 A
N/A leak on GV-1 i
1 2
1/9/79 F 0
Decreased power to 60% to try and locate / repair condenser leaks 3
1/lk/79 F h12.7 A
1 Unit shutdown repair leaking primary valves while startup Reactor tripped on low pressure
. outage. continued to repair atmospheric dump bellows.
b' O.1
- 4 nj t
I 2 eason:
3
" Exhibit G - Instructions 1: Forc ed F
R Method:
S: Scheduled A-Equipment Failure (Exp3 'n}
"P # "
" I ""
1-Manu al B-Maintenance or Test U
2-Manual Scran.
Event Report (LER) File C-Re fueling 3-Autccatic Scram.
(
~ 6)
D-Regulatory Restrictica h-Other (Explain)
E-Operator Training & Licensee Examination F-Administrative G-Operational Error (Explain)
Exhibit 1 - Sane Source H-Other (Explain)
t-SUD'.ARY OF MOUTHLY OPERATING EXPERIENCE TMI Unit 2 entered the menth operating at 83% power.
At 1950 on January 1 a leak was discovered in the Electro-Hydraulic Control (EHC) system at governor valvt #1.
The turbine was removed from service at 0605 to repair the leak.
The unit returned to ser71ce at 1736 and power escalation to 90% commenced.
On January 5 at 0957 rod 6-12 dropped due to a blown fuse and the ICS auto-matica11y ran the unit back to 58% power.
Rod 6-12 was latched and realigned and power was returned to 90%.
On January 9 power was reduced to 60% to remove one side of t1 main condenser from service to find and repair a tube leak.
Power was returned to 90% on January 11.
On January 14, the turbine was removed' from. service to repair an EHC leak on
- valve #3 The reactor was shut down to repair body to bonnet leaks on ne....
several pressurizer instrumentation isolation valves.
The reactor was taken critical on January 15 Prior to placing the turbine in service, there was a loss of vacuum in the condenser.
The ICS automatically treasferred steam dumping from the condenser to the atmospheric dump valves.
The expansion joint bellcvs downstream of the dump valves ruptured. This vented steam to the control building area where the transformers for Buses 2-34 and 2 kh are located.
Power to the pressurizer heaters was lost and the reactor tripped from 18% power on lov pressure. The unit was subsequently cooled down to facilitate replacement of the atmospheric dump valve bellava and certain pres-surizer instrumentaticn isolation valves.
Plant fill commenced on January 18.
The unit returned to service on January 31 at lhhh and power escalation to 97% commenced.
SAFETY RELATED MAIL"I'EUAUCE Replaced expancion joint bellows assemblies for atmospheric dump valves fG-V3A/B.
a v-C
'f}