ML19332C042

Monthly Operating Rept for Oct 1989 for TMI-1

ML19332C042
Person / Time
Site:	Crane
Issue date:	10/31/1989
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-89-2129, NUDOCS 8911220240
Download: ML19332C042 (6)

Text

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Post Offico Box 480 Route 441 South Middletown. Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

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November 15, 1989 C311-89-2129 i

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i U. S. Nuclear Regulatory Commission.

Attna Document Control Desk

. Washington, D.C.

20555 j

~ Dear Sir

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Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 l

Docket No. 50-289 Monthly Operating Report October 1989 t

Enclosed are two copies of the October 1989 Monthly Op".7 ting Report for Three-Mile Island Nuclear Station, Unit 1.

Sincerely, 1

D.1 i 1 Vice President & Director, TMI-1 l

IIDH/WGB:spb cci ; W.' Russell, USNRC F. Young, USNRC Attachments' 8911220240 891031 PDR ADOCK 05000289 R

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3 GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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OPERATIONS

SUMMARY

4 OCTOBER 1989 l

The plant entered the month operating at 100% power producing approximately 870 Mwe. An inadvertent ES actuation on October 30th, resulted in a manual power reduction of less than 5%. The plant was returned to 100% power within two hours.

MAJOR SAFETY RELATED MAINTENANCE During the month of October, the following major maintenance activities were performed on safety-related equipment:

Miscellaneous Waste Evaporator Feed Pump WDL-p-20 Failure of the motor on the Miscellaneous Waste Evaporator Feed Pump (WDL-P-20) was cause for replacing the pump-during the month of October. Upon completion of the job, the pump tested saticfactorily and was returned to service.

Waste Transfer Pump WDL-p-7B Waste Transfer Pump (WDL-P-7B) was removed from service because of what was thought to be excessive mechanical seal leakage. During the disassembly of the pump, a crack was found in the pump casing cradle. pump repairs will continue into November.

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OPERATING DATA REPORT 10 3k~bf D

E COMPLETED BY, C. W. Smyth 7y TELEPHONE (717) 9a8-8551 e

.. OPERATING STATUS 1 NOTES 1

,,jl. UNIT NAME:

THREE MILC ISLAND UNIT 1.1 1

2.4 REPORTING PERIOD:

OCTOBER-,1989. l l

32' LICENSED THERMAL POWER (MWT):

2568.

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'4. NAMEPLATE RATING (GROSS MWE):

~871.

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Tj. DESIGN ELECTRICAL RATING (NET MWE):

819. I i

<O.-MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

856. I 1

7. MAXIMUM DEPENDABLE CAPACITY.(NET MWE):

800. I i

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Ok IF CHANGES UCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

' O.. POWER ' LEVEL TO WHICH RESTRICTED, _ IF ANY (NET MWE)'

10. REASONS FOR. RESTRICTIONS, IF ANY:

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THIS MONTH YR-TO-DATE' CUMMULATIVE-

' 114 HOURS.IN REFORTING PERIOD 745.

'7296.

132937.;

s-L126; NUMBER OFtHOURS' REACTOR UAS CRITICAL 745.0 7296.0:

60577.41

13. REACTOR RESERVE > SHUTDOWN HOURS 10.0 0.0 1960.0" 114, HOURS' GENERATOR ~ON-LINE' 745.0 7296.0 59578.0

.O.O O.0 0.0-515.JUNIT-RESERV2 SHUTDOWN HOURS.

!!O!'LGROSS THERMAL ENERGY GENERATED (MWH) 1906894.

18699149.

146058254.

17# GROSS ELECTRICAL ENERGY GENERATED (MWH) 1656167.

6414411.

49008796.

1. 10a NET-ELECTRICAL ENERGY GENERATED (MWH) 621029.

6068945.

46038655.

19.JUNIT SERVICE FACTOR 100.0 100.0

~44.6 120. UNIT AVAILABILITY. FACTOR--

100.0 100.0 44.8 21'. UNIT CAPACITY FACTOR (USING MDC NET) 103.2 102.9 44.2

! :22.: UNIT CAPACITY FACTOR (USING DER NET) 101.8 101.6 42.3 123. UNIT FORCED OUTAGE 4 RATE O.O O.0 50.3 l'^ 24. ' SHUTDOWNS SCHEDULED OUER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH 8R Refueling Outage 1/5/90 - 3/5/90

25. IF SHUT DOWN-AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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DOCKET NO.

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THI-1 DATE o 10-31-89

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- COMPLETED BY c. w. smyth T

TELEPHONE-(717) 948 8551 s-.

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'.NONTH:' OCTOBER'

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REFUELING INFORMATION REQUEST I

1.

Name of Facility:

Three M*1e Island Nuclear Station. Unit 1

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Scheduled date for next refueling shutdown:

January 5, 1990 (8R)

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Scheduled date for restart following refueling: March 5, 1990 (8R) 4.-

' vill 1 refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

No If answer is yes, in general, what will these be?

If answer is no, has the reload fuel design and co e configuration been reviewed by your Plant Safety R8 view Comunittee to determine whether any unreviewed safety questions are asscciated with the core reload (Ref. 10 CFR Section 50.59)7 No l

l-If no such review has taken place, who,i is it scheduled?

December 1, 1989 I

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Scheduled date(s) for submitting proposed licensing action and supporting information.

6.

Important licensing considerations associated with refueling, e.g. new or different fuel-design or supplier, unreviewed design or performance l.

analysis methods, significant changes ir fusi design, new operating l

. procedures:

None 7.

The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 177 (b) 360 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:

i The present licensed capacity is 752.

Planning to increase licensed capacity through fuel pool raracking is in process.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1M1 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

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