ML20044B344

Monthly Operating Rept for June 1990 for Oyster Creek Nuclear Generating Station

ML20044B344
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1990
From:	Baran R, Fitzpatrick E, Sedar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007180367
Download: ML20044B344 (7)

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GPU Nuclear Corporation N

g' Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971 4000 g

Writer's Direct Dial Nurnber:

July 12,1990 U.S.1 Nuclear Regulatory Commission ATTN Document Control Desk 4

Washington,.D.C.

20555

Dear Sir:

-Subjects Oyster' Creek Nuclear Generating Station Docket No. 50-219

' Monthly. Operating Report In accordance with the Oyster Creek Nuclear Generating Station LOperating. License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2); copies of the Monthly Operating Data (gray book information) for tho' Oyster Creek Nuclear Generating Station.

If you should.have,any questions, please contact Brenda DeMarchant,;

Oyster-Creek-Licensing Engineer at (609) 971-4642.

uly yours,

Very 4

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%.tzpktick E

Vice President-and Director a

Oyster Creek

.-EEF:BDEM:jc (MOR)

N Enclosures tcca iMr. Thomas Martin,' Administrator.

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' Region I U.S. Nuclear Regulatory Commission 475~Allendale Road King of Prussia,.PA-19406-

'Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Washington,EDC~-20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station l

9007180367 900h30 PDR ADOCK 05000219

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HONTHLY OPERATING REPORT - JUNC 1990 h.

At the beginning of June, Oyster creek was operating at a grvss generator load of 656 MWe and increasing power gradually.

Full power was achieved on June 1.

On June 9, gross generator load was reduced to 383 MWe to clean "A" condensate pump lube oil cooler and replace brushes on

'D' reactor recirculating water pump motor generator set.- Full power was achieved on June 10.

On June 21, in order to-reduce the radiation field, power was reduced to 316 MWe during-replacement of the 1-2 auxiliary flash tank pump motor. Following

. repair, power was increased to 91% and stabilized while a problem with the j

reactor manual control system was corrected.

Full power was achieved on June i

22.

On' June 25, a reactor scram occurred due to low condenser vacuum caused by a tripped condenser backwash outlet valve. The plant remained shutdown for

.I' maintenance through the end of June.

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>ol MONTHLY OPERATING REPORT JUNE, 1990 The following Licensee Event Report was submitted during the month of June, 1990s.

-LER 90-06:

Individual components Exceed TS Max Test Interval Due to j

Personnel ErgpI l

'1

' on May 9, 1990, the Group Shift Supervisor and the Shift Technical Advisor removed the cleanup System losses from the plant heat balance calculation while the cleanup System was out j

16 of service.- On May 11, 1990 the cleanup System was placed back into service without the 7.84 megawatt loss added into the heat-j balance-calculation.- For t's next nine and one half hours the 1

average power level exceeded the Licensed limit by approximately 1.64 megawatts. The safety significance of-this event is minimal.

as the power level during this event averaged 100.08%. -This-power'1evel would have a negligible impact on the results of-transient or accident analyses.

Furthermore, there were ampla margins to. operating limits for the Critical Power' Ratio and' Average Planar Linear Heat Generation. Rate.

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q The cause of this occurrence is personnel error.. This activity was not controlled by plant procedures and the individuals.

involved:did'not ensure adequate controls were established to control-the-evolution.

Procedure changes will be made to-ensure that the computer inputs.

to.the heat balance are adequately controlled.

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OPERATIN3 DATA REPORT 3

' OPERATING STATUS

.1.-

DOCKET:

50-219 2.

REPORTING PERIOD:

06/90 3.

UTILITY CONTACT: JOHN SEDAR 609-971-4698 4.

LICENSED THERMAL POWER (HWt):

1930 5.-

NAMEPLATE RATING (GROSS MWe):

687.5 X 0.8 = 550 6.

DESIGN ELECTRICAL RATING (NET MWe):

650 7.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

642 8.

MAXIMUM DEPENDABLE CAPACITY (NET MWe):

620 9.

IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

NONE 10.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):

None 11.

REASON FOR RESTRICTION, IF 6NY:

None MONTH X1hg CUMULATIyg 12.

REPORT PERIOD HRS 720.0 4343.0 179879.0

- 13. ' HOURS RX CRITICAL 582.3 3465.8 114726.4 14.

RX RESERVE SHTDWN HRS-0.0 0.0 918.2 15.

HRS GENERATOR ON-LINE 582.3 3358.3 111590.1;

-16.

UT RESERVE SHTDWN HRS 0.0 0.0=

1208.6 17.-

GROSS l THERM ENER (HWH)-

1103254 5840120 187113179 18.

GROSS-ELEC ENER (MWH) 364390.

1931610 63054350 19.

NET ELEC ENER (MWH) 349930 1851670 60506648 20.

UT SERVICE FACTOR 80.9 77.3 62.0 21.

UT AVAIL FACTOR 80.9

'<7.3 62.7

'22.

UT CAP' FACTOR-(MDC NET) 78.4 68.8 54.3 23.

.UT CAP-FACTOR.(DER NET) 74.8 65'6 51.7 24.

UT ' FORCED ' OUTAGE RA IE 19.1 18.6 12.0-25.-

FORCED-OUTAGE HRF 1$7.7 765.8 15175.9

-26.-

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):

NONE.

27.

IF CURRENTLY SHUTDOWN-ESTIMATED STARTUP DATE:

7/03/90 o

1619B/29 Q

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AVERAGE DAILY POWER LEVEL.

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NET MWe DOCKET #..-,.....

50219 UNIT.

. OYSTER CREEK #1-

"f" REPORT DATE.

. JULY 9, 1990 COMPILED BY.-.

. JOHN H. SEDAR TELEPHONE #...

.609-971-4698 MONT!!

JUNE, 1990' T

DAY E

-PAX E

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622 17.

614 2,

618 18.

612 3.

611 19 '.

609-4 '.

622 20.

609 5.:

618 21.

500

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6.

616 22.

578 7.-

617 23, 578 8.

! 616

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607'.

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'499

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152,

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615 26.

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616 27.

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619 28.

O Tp 13, 616 29.

0 14, 617 30.

0 15.

617

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Docket No.'50-219 L.

REFUELING INFORMATION - JUNE, 1990 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: January 11, 1991 pending necessary state approval.

Scheduled date for restart following refueling: May 19, 1991 L.

Will ~ refueling or resumption of operation thereafter regpire a Technical Specification change r, other license amendment?

Yes J -

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

I July 15, 1990

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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:

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General Electric Fuel Assemblies fuel design and performance analysis methods have been approved by.the NRC.

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Exxon Fuel Assemblies - no major changes have been made nor are -

I there any anticipated.

The number of fuel assemblies (a) in the core 560

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(b) in the spent fuel storage pool 11595

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(c) in dry storage 37

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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 b

numbercoftfuel assemblies:

Present licensed capacity:

2600 The projected date of the last refueling that can be discharged to tho spent

. fuel pool. assuming the present licensed capacity:

LReracking of the fuel pool is in progress.

Nine (9) out of ten (10) racks have~ been installed to date.

When reracking is completed,

i 7p discharge capacity to the spent fuel pool will be available until 1994 refueling outage, i

.i 1619B/27 m

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UNIT SEUTDOWNS AND POWER REDUCTIONS

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DOCKET NO.

50-219 UNIT MADE Ovetor Creek DATE-July. 1990 COBE'LETED BY R. Baran' TELEPHONE 971-4640 REPORT MONTE JUNE 1990 TYPE NETHOD OF SEUTTING F Forced DURATION DOWN THE REACTOR OR NO.

DATE S Scheduled.

(Bours)

REASON (1)

REDUCING PONER (2)

CORRECTIVE ACTIONS /COBSENTS 101 6/9 5

-0 B

1 Load reduction to clean

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h sate Pump Lube 011 Cooler Imad redaction to replace the 102 6/21 S

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1 sootor on the 1-2 Auxiliary Flash Tank Pump.

(ALARA concerns) 103 6/25 F

137.7 A

3 Automatic full scram due to main condenser loor vacuum. Loer vacuum caused by a loss of of circulating water when backwash valve V-3-18 failed to open during condenser backwashing.

SUMMARY

(1) REASON (2) METHOD A.-

Equipment Failure'(Explain)

E.

Operator Training & License Exam 1.

Manual B.

Maintenance or Test

.F-Administrative 2.

Manual Sc3Ea C.

Refueling 4.

Operational Error (Explain) 3.

Automatic Scram D.

Regulatory Restriction E.

Wher (alzplain)'

4.

Other (Explain)

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