ML20086K132

Monthly Operating Rept for June 1995 for Oyster Creek Nuclear Generating Station

ML20086K132
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1995
From:	J. J. Barton, Edelmann P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-95-2190, NUDOCS 9507200024
Download: ML20086K132 (5)

Text

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l ENuclear a"=sr*"

Route 9 South Forked River New Jersey 08731-0388 l 609 971-4000 Writer's Direct Dial Number:

C321-95-2190 31erre 12,1995 aly i

U.S. Nuclear Regulatory Commission  ;

A'ITN: Document Control Desk Washington, D.C. 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 hionthly Operating Report - June,1995 In accordance with the Oyster Creek Nuclear Genemting Station Opemting License No.

DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gray book infonnation) for the Oyster Creek Nuclear Generating Station. j If you should have any questions, please contact Brenda Dehlerchant, Oyster Creek  !

Licensing Engineer at (609) 971-4642.

Sincerely, J. a1on I O -

resident and Director l yster Creek JJB/BDEht: jc Attachment cc: Administmtor, Region 1 Senior NRC Resident Inspector Oyster Crvek NRC Project hianager (C:\wpsl\demercha\MOR RPT.jun) 9507200024 950630 PDR ADOCK 05000219 R PDR GPU Nuclear Corporation is a subsidiary of the General Public Utihties Corporation ((G I/n

MONTHLY OPERATING REPORT LICENSEE EVENT RE10RTS The following Licensee Event Reports were submitted during the month of June,1995: i LER 95-002 Unsupervised Core Alteration Due to Personnel Errors in Decision Making On November 6,1994, with 19 fuel bundles loaded in the core, refueling was internipted to correct a faulty fuel handling Grapple Engaged indication. After repairs were completed, at approximately 1257 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.782885e-4 months <br />, fuel bundle LYL-510 was raised about 6 inches from its fully seated location in the core as part of ensuring the problem had been corrected. A Senior Reactor Operator was not present to supervise the fuel movement as required by Technical Specifications. The incident was not reported until six months later since personnel did not recognize that the activity was inconsistent with Technical Specifications.

The cause of the event was due to personnel error in decision making which led to an unsupervised core alteration.

The safety significance is minimal. The fuel bundle location and orientation was not altered.

Corrective actions will include reviewing the roles and responsibilities for personnel involved with refueling opemtions and subsequently revising procedures, plans, and testing requirements related to refueling operations. Appropriate personnel will be trained on these changes.

LER 95-003 Technical Specification Required Surveillance Missed Due to Insufficient Administrative Controls A review of surveillance records conducted on May 31,1995 revealed that the six month drywell airlock leak rate test which was due on August 17, 1993, was not conducted until September 29,1993. The delay was attributed to inappropriately applying the 25%

surveillance intenal extension which cannot be added to containment pressure testing. The root cause of the inappropriate application of the inten'al extension was detennined to be insufficient administrative controls to ensure compliance with the Technical Specifications.

The safety significance of the delayed surveillance was determined to be minimal as the surveillance which was perfonned on September 29.1994 verified that the leak rate of the airkick penetration was acceptable. Corrective action was taken to specifically state that the 25% extension which may be applied to other surveillances does not apply to the airlock leak rate test.

Oyster Creek Station #1 Docket Ne 50 219 REFUELING INFORMATION JUNE,1995 Name of Facility: Dyster Creek Station #1 Scheduled date for next refueling shutdown:

September,1996 Scheduled date for restart following refueling: Currently projected for November,1996 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 l

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 cors - 560 (b) in the spent fuel storage pool = 2048 (c)in dry storage = 24 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or la planned, in number of fuel assemblies:

Present Licensed Capacity: 2645 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Full core discharge capacity to the spent fuel pool will be available through the 1998 refueling outage.

(p:Mocs-95\$414-95\opiata.cor\ report:19)

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[- OPERATiliG DATA REPORT t.

OPERATING STATUS 1.- DdCKET: 50 219

2. REPORTING PERIOD: Jun-95

3. UTILITY CONTACT: PAUL EDELMANN (609-9714097)

4. LICENSED THERMAL POWER IMWt): 1930

5. NAMEPLATE RATING (GROSS MWe): 887.5 x 0.8 = 550 E. DESIGN ELECTRICAL RATING INET MWe): 850

7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 641

8. MAXIMUM DEPENDABLE CANCITY INET MWe): 819

9. IF CHANGES OCCUR AB0VE SINCE LAST REPORT, GIVE REASONS:

NONE

10. POWER LEVEL TO WHICH RESTRICTED,IF ANY (WET MWe):

NONE

11. REASON FOR RESTRICTION,IF ANY:

NONE MONTH YEAR CUMULATIVE

12. REPORT PERIOD HOURS 720.0 4343.0 223703.0 i

13. HOURS RX CRITICAL 720.0 4343.0 150143.7

14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2

15. HR$ GENERATOR ON LINE 720.0 4343.0 148842.1

16. UT RESERVE SHTDWN HRS O.0 0.0 0.0

17. GROSS THERM ENERGY (MWM) 1388448 8179708 252703412

18. GROSS ELEC ENERGY (MWH) 464157 2781974 84808265

19. NET ELEC ENERGY (MWH) 447364 2682960 81358047

20. UT SERVICE FACTOR 100.0 100.0 85.8

21. UT AVAll FACTOR 100.0 100.0 85.8

22. UT CAP FACTOR (MDC NET) 100.4 99.8 59.3

23. UT CAP FACTOR (DER NET) 95.5 95.0 58.0

24. UT FORCED OUTAGE RATE 0.0 0.0 10.0 I

25. FORCED OUTAGE HR$ 0.0 0.0 16289.8

26. SHUTDOWNS SCHEDULED OVER NEXT 8 MONTHS (TYPE, DATE, DURATIONt.

NONE

27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE: NIA (pMocs-95\$414-95\opdata.cor\ report 2 !)

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