ML20034H587

Monthly Operating Rept for Feb 1993 for Oyster Creek Nuclear Generating Station

ML20034H587
Person / Time
Site:	Oyster Creek
Issue date:	02/28/1993
From:	J. J. Barton, Egan D, Krall J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-93-2077, NUDOCS 9303190044
Download: ML20034H587 (7)

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GPU Nuclear Corporation "

b7,,, a Nuclear m a a r see Forked River, New Jersey 08731-05881 609 971-4000-

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Writer's Direct Dial Number 6 C321-93-2077--

March 11,- 1993 '

O.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555

Subject:

Dyster Creek Nuclear Generating Station Docket No. 50-219 Monthly' Operating Report In accordance with the Oyster Creek Nuclear Generating Station Operating tidense No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Brenda DeMerchant, Oyster Creek -

Licensing Engineer at (609) 971-4642.

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J. 1. Barton V'gejPresident and Director yf%r Creek-JJB/BDEM: jc-

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Administrator, Region 1 -

Senior NRC' Resident Inspector Dyster Creek NRC Project Manager il 9303190044 930228 C

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MONTHLY OPERATING REPORT FEBRUARY.1993 Oyster Creek entered February in the final-stage _of the 14th refueling outage. The plant commenced reactor startup'on 2/14/93 at 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> and achieved criticality at 1324 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.03782e-4 months <br />. The 14th operating cycle for_0yster Creek commenced at 0708 hours0.00819 days <br />0.197 hours <br />0.00117 weeks <br />2.69394e-4 months <br /> on 2/16/93, when the generator was synchronized to the grid following turbine testing. _ Full power operation was attained at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on 2/19/93. The plant maintained full power operation through the end of the reporting ' period.

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tiONTHLY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of February, 1993:

LER 93-002 On January 25, 1993 at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, plant personnel discovered that reactor l

metal temperature was above 212 degrees F without Primary Containment in effect, without Isolation Condensers operable, without Containment Spray / Emergency Service Water operable, with only one system of the Core Spray operable, and without a Shift Technical Advisor stationed. The plant was shut.

down for a refueling outage at the time. Reactor water level had been lowered in accordance with a temporary procedure change which did not provide for sufficient forced circulation to cool the reactor.

The cause of the. event was personnelerrorinimproperimplementationoftechnicalguidanceand!

subsequent reviews prior to implementation which did not recognize the error.

The event had safety significance in that reactor temperature exceeded 212 degrees F for several hours without detection.

Immediate corrective action was taken to reduce reactor coolant temperature and cancel the temporary procedure change.

Future corrective actions include: revising the Shutoown Cooling operating procedure, reviewing the effectiveness of safety review of temporary procedure changes, discussion with personnel involved with the procedure change, and training of procedure reviewers.

LER 93-003 A full reactor scram was initiated while performing system lineups to return the Control Rod Drive system to its normal configuration after a Primary Containment integrated leak rate test on January 30, 1993, at 1258 hours0.0146 days <br />0.349 hours <br />0.00208 weeks <br />4.78669e-4 months <br />..-The plant was shut down for a refueling outage at the time. The cause of the i

1 occurrence was an inadequate procedure. The order in which the procedure steps were written led the operator to remove the Scram Discharge Volume (SDV) high water level scram bypass signal while there was still a high water _ level in the SDV. The next step instructed the operator to open.the vent and drain valves, which would remove the water from the volume. The order of these steps should have been reversed. This event has no safety significance since the scram functioned as required and represented only an unnecessary challenge to the equipment.

Immediate corrective action was taken to bypass the scram signal, drain the SDV, and reset the scram.

The bypass switch was returned to normal. The Primary Containment integrated leak rate test procedure will be revised as necessary to prevent this event from recurring.

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Oyster Creek Station #'l Docket No. 50-219' 4'

REFUELING INFORMATION - FEBRUARY, 1993 Name of Facility:

Oyster Creek Stat'ca #1 Scheduled date for next refueling shutdowns currently projected for October, 1994 Scheduled date for restart following refueling: Currently projected for January, '1995 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

No 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 1.

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

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

=

(b) in the spent fuel storage pool

= 1878 (c) in dry storage 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:

Present Licensed Capacity:

2600 The projected date of the last refueling that can be discharged to the spent fuel: pool

- assuming the present licensed capacity:

Based on a projected reload of 184 bundles,, full core discharge capacity to,thei spent fuel pool will be lost after the 15R refueling outage (January,.1995).

NRC_RPT.WPD/78

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AVERAGE DAILY POWER LEVEL rc NET MWe f!

' DOCKET #...

.50-219 UNIT.

. OYSTER CREEK #1-F

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REPORT DATE...

.1... 03-04-93:

s COMPILED BY.

. JIM KRALL TELEPHONE #......~.

609-971-4115 i

t, MONTH:

FEBRUARY, 1993 l

f RAI MH-DAY ME

.1.

0 16.

209 2.

0 17, 338 3.

O 18.

381 4.

O 19.

610'.

L 5.

0 20.

631 6.

0 21.

633 7.-

0 22.

633 I

P 8.

O-23.

633-

. i 9.

0 24.

633

. 10.

O 25.

L632 11.

0 26.

632 ll2.

0 27.

632 13.

0 28.

632 14.

0 15.

O NRC_RPT.WPD/79 u.

r OPERATING DATA REPORT

{

OPERATING' STATUS

1. DOCKET:

50-219 2.; REPORTING PERIOD -

02/93

{

3. UTILITY CONTACT :

JIM KRALL1(609)971-4115 4.' LICENSED THERMAL POWER (MWt):

1930

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5. NAMEPLATE RATING'(GROSS MWe):

687.5 x 0.8 = 550

6. DESIGN ELECTRICAL RATING (NET MWe):

650 7.' MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

632-

.)

8. MAXIMUM DEPENDABLE CAPACITY (NET MWe):.

610 p-

9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

f NONE

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY-(NET MWs):

NONE

11. EEASON FOR RESTRICTION, IF ANY:

5 NONE MONTH YEAR CUMULATIVE ~

12. REPORT PERIOD HOURS 672.0 1416.0 203256.0 l

13. HOURS RX' CRITICAL-346.6 346.6=

'132255.0.

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14. RX RESERVE SHUTDOWN HRS 0.0 0.0

.918.2

15. HRS GENERATOR ON-LINE' 310.4 310.4 128857.7

16. UT RESERVE SHTDWN HRS 0.0 0.0 1208.6-

17. GROSS THERM ENERGY (MWH).

546838 546838 219015473 3 8. GROSS ELEC ENERGY - (MWH) 180327

'180327 73576465

'19. NET ELEC ENERGY (MWH) 171229

-167837 70603353

20. UT SERVICE FACTOR' 46.2 21.9 63.4.

-21. UT AVAIL FACTOR.

46.2

-21.9 64.0:

22. UT CAP FACTOR (MDC NET) 41.8 19.4 56.1

23. UT CAP FACTOR (DER NET) 39.2 18.2 53.4

24. UT FORCED OUTAGE RATE O.0 0.0 11.0

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- 25. FORCED OUTAGE. HRS:

0.0-0.0 15957.3.

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

NONE

' 27. IF CURRENTLY. SHUTDOWN, ESTIMATED STARTUP DATE:

N/A' i

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UNIT EEL'TDOWNS ANJ F W ER REptt~tJONS DOCKET NO:

.$0-219 UN1T NAM 3 Oyster Creek DATE:

March 5.1993 COMPLT*D BT David Easn TELEPHONE:

609/971-451f REPORT' MONTE:

February 1993 TYPE METHOD OF SHUTTING CORRECTIVE

- No.

DATE Fr Forced DURATION REASON (1)

DOWN THE REACTOR OR ACTIONS / COMMENTS-5: Scheduled' (heurs)

REDUCING POWER (2) 124 921127 S

361.6 e

1 Completten of 14th refuelirig outage.

a

SUMMARY

- (1) REASON-

-(2) METHOD W $.

a.' Equipment Failure (Emplain) e.

Operator Training & Lie Exam

.1.' Manual 7 "~

- b.

Maintenance er Test

f.. Ad stnistrative 2.

Manual.Seram 4

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e.. Refueling s.

Operational Error-(Esplain) 3J Automatic Scram d.

Regulatory Restriction.

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.Other (Explain) 4.

Other (Emplain) o e.

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