ML19261F358

Monthly Operating Rept for June 1978

ML19261F358
Person / Time
Site:	Three Mile Island
Issue date:	07/13/1978
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19261F357	List: ML19261F356 ML19261F358
References
NUDOCS 7910250819
Download: ML19261F358 (5)

Text

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AVERAGE DAILY UNIT PCWER LEVEL Docket No. 50-280 Unit "NI-1 Date 7-13 78

• U* "

• Completed By ,

Telephone (215) 929-3601 Ext. 169 MONUI Jtme 1978 D1 AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

{MWe-Net) (Kie-Net)

, 76h 17 78h 2 763 18 77h 3 771 19 773 h 776 20 777 5

772 21 732 6 777 22 -21 _

7 770 23 -13 8 76h 2h -10 g TTh 25 -10 10 779 26 -10 11 687 27 -2h 12 612 28 -33 13 781 29 -33 1h 678 30 -19 789 31 15 16 IOI iAB2 100 7810250

/af g

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PERATING DATA REPORT eket No. 50-289 Late I-13-I Completed By D. G. Mitchell OPERATING STATUS Telephone {215 ) o20-3601 Ext.;(

l. Unit Name: Three Mile Island Unit 1

2. Reporting Period: ha m? A 3 Licensed Thermal Power (MWt): 2515

k. Nameplate Rating (Gross MWe): 871 5 Design Electrical Rating (Net MWe): 019

6. Max. D-cendable Capacity (Gross MWe): Sh0 7 Max. Dependable Capacity (Net MWe): 792

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 fer Restrictions, If Any:

"his Menth Yr.-To-Oate Cumulative 720 h2be 33.552

11. Hours in Reporting Period

12. No. of Hours Reactor was Critical 513.5 3128.5 26186.8 0 0 838.5

13. Reactor Reserve Shutdown Hours 5 " '9 lb. Hours Generator On-Line 25639.h V O O 15 Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 12hh178 7273h22 62666987 17 Grcss Elect. Energy Generated (MWH) h05151 2h06011 20809833

18. Net Electrical Energy Generated (MWH) ,evoc6 22h3822 19562221 70.3 70.0 10.4 19 Unit Service Factor Unit Availability Facter 10 3 70.0 76.h 20.

21. Unit Capacity Factor (Using MDC Net) 66.1 65.2 73.6

22. Unit Capacity Factor (Using DER Net) 63.9 63.1 71.2

23. Unit Forced Outsge Rate A9 I 6.6 5.7 2h. Shutdevns Scheduled Over Next 6 Months (Type, Date, and Duration of Zach):

25 If Shut Down at End of Report Period, Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation): FCRECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION __

\482 \D\

UNIT CHUTDOWN3 AND POWER REDUCTIONS Docket No. 50-289 June Unit Name TMI-1 REPORT MONTil Date T 78 Completed By D. G. Mitchell Telephone 929-3601 Ext.169 (215)-AC y e No. Date Type l $3 cv 8 D System Component Cause and Corrective h { $ eg gj' Code D Code 5 Action to Prevent Recurrence nm g ggo g g d5E UET s tie n ii md 7 6-11-78 F 0 A Repair block orifice on feedwater pump 8 6-lh-78 F 0 A LER #78/20 CRDRVE Dropped 7 Group 3 control rods due to a shorted diode in the DC Hold Seccadary Power Supply 9 6-22-78 F 213.5 A Failure of the #2 seal on Reactor Coolant Pump 10

/

1F: Forced 2Reason: 3gggg " Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manu al #E

• B-Maintenance or Test 2-Manual Scram.

A C-Refueling Event Report (LER) File O '

3-Automatic Scram. ( ~ 6)

N D-Regulatory Restriction h-Other (Explain)

E-Operator Training & Licensee Examination

. F-Administrative S G-Operational Error (ExpInin) Exhibit 1 - Same Source N , H-Other (Explain)

s

. . h TMI-1 OPERATING SUS!ARY JUNS 1979 Unit Performance The Unit operated at essentially 1005 power except for the reducticns described below.

Sirnificant Pcver Reductions Cn 6-11-78, the Unit reduced to 955 power for approximately hear to perform the scheduled physics testing. Approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after returning to 1005 pcVer en 6-11-78, a severe gasket steam leak develcped on FE-7 (FW-PlA Flev No::le) forcing the Unit down to 75% power. The gasket was replaced and the Unit escalated back to 100% power in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

On 6-lh-78 while at 100% pcVer, 7 of the 9 Group 3 Centrol Rods dropped forcing the Unit down to 30% power. Surveillance testing of the CREM power supply breakers was being performed at the time and because of an undetected low voltage condition in the redundant power scurce to the CRDMs, =c=entary in-terruption (in accordance with the surveillance procedure) of the normal CPSM holding pcVer caused the rods to drop. The two rods in Grcup 3 which re-

=ained latched were driven to the bottc= of the core and then the entire group 3 was withdrawn to their normal 100% vithdrawn position. The Unit returned to 1005 power within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the rods dropped.

On 6-21-78 the Unit was shutdevn and cooled down to repair the #2 and #3 seals en the "C" reactor coolant pu=p. Evaluation of this seal failure in-dicates incorrect installa; ion of the #2 seal during the 1978 Refueling Outage caused a chip out of the #3 seal to lodge between the #2 seal faces, thus causing the failure. Both the #2 and #3 seals have been replaced. On the heatup frc= this outage, a RC-71 (Pressurizer Spray Valve) bcdy to bonnet valve leak vas discovered and the heatup delayed in order to nake repairs.

The Unit was placed back on line June 30, 1978. We achieved 1005 pcver en July 2 and have remained there except for (1) 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and (1) h hour period at 90% as required by syste=.

Major Safety Related Maintenance While operating at 1005 power on June 21, 1978, RC-Plc #1 seal leak off vent to zero (0) gallons per =inute, RC-Plc #2 seal back pressure alar =ed, the Reactor Ccolant drain tank level increased, and the -akeup tank level decreased.

The sy=ptces listed above indicated a proble vith RC-Plc. Preparations were made to take the unit off line and repair RC-PlC. On June 21/22, 1978, the plant was shutdown for repairs en RC-P1C. The Reacter Ccclant Syste= vas depressurized and drained to permit disassembly of RC-Plc. The repair verk included:

1) Installation of seal removal rails

2) Uncoupling of motor frc= pump

3) Removal / Inspection of the #3 seal and the #2 seal h) Replacement of damaged parts *

5) Installation of the #2 seal and the #3 seal

6) Installation of the =ctor to pu=p coupling 1482 103

m Inspection cf the #2 and the #3 seals revealed that the #3 seal graphite ring was cracked. Chips were located under the #2 seal. These chips prevented the

1. 2 seal frem seating properly. Upon cenpletien of the F.C-Plc work, the unit was returned to service.

6 1482 104