ML19224A422
| ML19224A422 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1979 |
| From: | Lengel R Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19224A421 | List: |
| References | |
| NUDOCS 7901190115 | |
| Download: ML19224A422 (5) | |
Text
.,.
SU:OiARY OF MO:ITHLY OPERATING EXPERIENCE TMI init 2 returned to service following the screen outage and removal of oil from the condencate cyctem at 0312 on December 2.
The unit experienced a loss of feedvater at OL30 and the turbine was manually tripped.
Generator breakers were reclosed at 0609 and at 0720 the reactor tripped on low pressure during a recovery frca a loss of feedwater.
The unit returned to service at 15% at 1204. The reactor tripped on low pressure due to overfeeding. The trip was followed by an E.S. actuation and subsequent H.P. injection.
The overfeeding occurrel vhen the main feed-water block valves automatically opened with the downctream main feedwater regulating valves manually pinned open at the local air controllera.
The unit returned to service at 17h8 on December 3 and power escalation commenced. The unit achieved 90% reactor power at 215L on December h and the 90% power level testing continued.
The unit reduced power to 60% on December 12 in order to remove main feed pump 13 from service in order to repair a leak on the suction atrainer.
Power was further reduced to SST on December 13 due to high codium levels in the condens'.te cystem. It wis also discovered that main feed pump 1B had a mechanical interference und could not be rotated freely.
The unit was removed frer service at 0151 on December 16 to replace the impeller assembly in 1B cain feed pump.
The unit returrad to service Dccember 22 and power was increased to 50%.
On December 33 the unit achieved 97% power and testing continued.
On December 27 power was reduced to 65% and returned to 975 for trancient tecting.
At 1522 on December 28 main feed pump 1A was manually tripped in accordance with the test procedure. The feed pump was returned to cervice and power increased to 97%.
At 2318 the main turbina was manually tripped per the test procedure. The unit responded properly and ran Inck to 155 power. The unit was subsequently shut down to repair a number of steam leaks.
The unit returned to service December 29 and power was increased to hh%.
At 1100 hrs on December 30 the main turbine was removed from service in order to repe.ir a stean leak on the high pressure turbine. The turbine was returned to service at lh15 hra and power escalation began.
The unit achieved 80% reactor power at 2020 hra and commenced commercial operation at 2300 hra on December 30 at a net 765 MWe.
~
Wb 7901190 //5
Power was reduced to 75% at 0030 hrs. on December 31 pending verification of reactor coolant flow calculations. The unit returned to 82% power at 0630 hrs.
At this time plans are to maintain 82% power level until a second heater drain pump can be returned to service.
- E-r..r.,b) 9
OPERATING DATA REPORT Dockat No.
50-320
~
ste 1/15/79 Completed By R. A. Lengel CPERATING STATE Telephone M-WU1 1.
Unit Name: Three Mile Island Nuclear Sta., Unit 2 2.
Reporting Period:
December. 1078 3
Licensed Thermal Power (br4t):
2772 h.
Nameplate Rating (Gross Ffde):
961 5
Design Electrical Rating (Net MWe): _906 6.
Max. Dependable Capacity (Gross br4e): 930 7
Max. Dependable Capacity (Net 5fde):
880 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 ?fde):
10.
Reasons for Restrictions, If Any:
MONTd YR TO DATE CUICICLATIVE 7hh 6602 25 11.
Hours in Reporting Period 12.
No. of Hours Reactor vts Critical Shl.1 1753.3 25.0 13.
Reactor Reserve Shutdown Hours 202.9 323h.h 0.0 509.8 1298.0 25.0 lb.
Hours Generator On-Line 0.0 0.0 0.0 15 Unit Reserve Shutdown Hours 16.
Gross Thermal Energy Generated (!f4H) 1197696 2219379 565hh 17 Gross Elect. Energy Generated (hPJH) 383h26 727677 10700 18.
Net Electrical Energy Generated (!fld) 353051 576921 18716 19 Unit Service Factor 68.5 19.h 100,0 20.
Unit Availability Factor 68.5 19.h 00.0 21.
Unit Capacity Factor (Using MDC Net) 53.9
~
9.8 85.1 22.
Unit Capacity Factor (Using DER Net) 52 4 9.5 82.6 23 Unit Forced Outage Rate 31.h 76.7 0.0 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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 3/9/T8__
3/28/78 INITIAL ELECTRICITY 3/15/78 h/21/78 COMMERCIAL OPERATION 12/10/78 12/30/78
-oem Lt... I
r AVERArE DAILY U IIT PO'4ER LEVEL r
i Docket I!c.
50-320 Un.t TIII-2 1/15/T9 D f.tc Completer. By R. A. Lengel December, 1978
!40:mI DAY AVERAGE DAILY PJ4ER LEVEL DAY A'. FRAF,E DAILY PO'4ER LEVEL
(? rde-:let ) *
(!Ge-?iet )
-35 17
-36 1
2
-17 18
-27 3
ho 19
-27 h
600 20
-36 8h2 21
-36 5
6 8h7 22 257 7
830 23 708 8
838 2h 887 I
837 2c 896 o
838 26 891 10 88h 11 837 27 12 531 28 8h3 482 29
-32 13 1h h85 30 367 15 h85 31 748 16
-15
- Please I!ote:
.'!egative numbers indicate that more energy was used by the unit than was produced by it, and are included for your infor-nation only.
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U'iIT SHUTDOWNS AND POWER REDUCTIONS Docket No.
50-320 finit Name T'!I-2 REPORT MONTH December Date 1/15/79 Cenpleted By h
A-Lensel Telephone 921-b501 l
5 '2 Systen Conponent Cause and Corrective No.
Date Type m
-n C
c.
Code h Code 5 Action to O p o
o um oo ec a
Cb om a=
e e-o a
L Prevent Recurrence C +'.D C
Dw D
oeP U C G
CG
.C P G p 5 e o O F oM0
+4 > d y ca m awm lh 12/1/78 F
27.P A
3 Condensate booster pump tripped, tripping feed water punps 15 12/2/78 F
1.7 H
?
lost FW flow while shifting FWP Turbine 1A from auxiliary steam to main steam 16 12/2/78 F
h.8 G
3 Turbine tripped when condensate valve was ilsd-vertently positioned to the -Dill open position 17 12/2/78 F
28.3 3
OTSG "B" feed stopped due to F4-V-193 being fully closed 18 12/16/78 F
lh6 A
3 Turbine tripped due to loss of FW-P-lE 19 12/28/78 S
23.8 3
1 Physics testing lead rejecticn test 20 12/30/76 F
2.h B
iiigh pressure turbine syster steam leak u
1: Fo rc ed 2 eason:
3 xhibit G - Instruction:
F R
Methodi f"
S: Scheduled A-Equipment Failure (Explain) 1-Manu el
^
B-Maintenance or Test I
2-Manual Scram.
C-Re fu elin6y Event Report (LER) File (p
3-Automatic Scram.
(
~ 61'1 D-Regulatory Restriction b-Other (Explain) g.
E-Operator Training & Licensee Examination F-Adminis rative 5
'p G-Operational El ror (Explain)
Exhibit 1 - Same Source
[
H-Other (Explain)