ML20137C377

Monthly Operating Rept for Feb 1997 for Ocnpp

ML20137C377
Person / Time
Site:	Oyster Creek
Issue date:	02/28/1997
From:	Dougher J, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2080, NUDOCS 9703240237
Download: ML20137C377 (7)

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GPU Nuclear, lnc.

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U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River, NJ 06731-0388 Tel 609-9714000 l

March 17, 1997 6730-97-2080 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219 i

Monthly Operating Report - February,1997 In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1, 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 Ms. Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.

Very tmly yours, i

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b Michael B. Roche i

Vice President & Director Oyster Creek MBR/BDeM/gl Enclosures i

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Administrator, Region I (2 copies)

NRC Project Manager NRC Resident Ins or g@

9703240237 970228 I

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SUMMARY

FEBRUARY.1997 2

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I There were no significant shutdowns or power reductions during Febmary 1997. During the month, the plant generated 427,125 MWh net electric which was 102.7% ofits MDC rated capacity, i

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j MONTHLY OPERATING REPORT Licensee Event Reports - February.1997 8

LER 97-001 was filed Januaiv 31.1997 i

On January 3,1997, during a review as requested by Generic Letter (GL) 96-06, Assurance of l

Equipment Operability and Containment Integrity During Design Basis Accident Conditions, seven penetrations in five systems did not meet the requirements as described in GL 96-06. Under 4

the postulated conditions contained in GL 96-06, these seven penetrations are only required for containment integrity. An analysis was performed of each penetration while isolated. The analysis modeled the effects on internal fluid and piping in response to an external ambient temperature increase. The results revealed that although the piping did not meet the design requirements, the postulated pressures did not exceed ASME Section III, Appendix F criteria for j

piping. Additionally, the potential effects on the respective isolation valves were considered. A i

catastrophic failure of the valves is not considered credible. Therefore containment integrity for the penetration was maintained and the safety significance of this discovery is considered minimal.

i The cause for this condition was that previous analyses were performed without using the more conservative assumptions described in GL 96-06. Operability determinations were performed and d

further evaluations are ongoing to determine the need for mcdifications or procedural revisions.

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I OPERATING DATA REPORT OPERATING STATUS

l. Docket:

50-219

2. Reporting Period:

Febmary,1997

3. Utility

Contact:

John D. Dougher (609) 971-2130

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4. Licensed Thermal Power (MWt):

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):

641

8. Maximum Dependable Capacity (Net MWe):

619 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 Any:

None i

MONTH YEAR CUMULATIVE l

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12. Report Period Hours 672.0 1416.0 238320.0 l

13. Hours Rx Critical 672.0 1416.0 163004.8 l

14. Rx Reserve Shutdown Hours 0.0 0.0 918.2

15. Hours Generator On-Line 672.0 1416.0 159333.8

16. Ut Reserve Shutdown Hours 0.0 0.0 0.0 1

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17. Gross Thermal Energy (MWh) 1285370 2700972 276615053

18. Gross Electric Eenergy (MWh) 442438 929938 92859205 i

19. Net Electric Energy (MWh) 427125 897474 89106040

20. Ut Service Factor 100.0 100.0 66.9 s.

21. Ut Available Factor 100.0 100.0 66.9

22. Ut Capacity Factor (MDC Net) 102.7 102.4 61.0 i

23. Ut Capacity Factor (DER Net) 97.8 97.5 57.5

24. Ut Forced Outage Rate 0.0 0.0 9.7 '

25. Forced Outage Hours' O.0 0.0 17137.4

26. Shutdowns Scheduled Over Next 6 Months (Type,Date, Duration):

None

27. If Currently Shutdown, Estimated Startup Date:

N/A.

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Oyster' Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - FEBRUARY.1997 Name ofFacility:

Oyster Creek Station #1 L Scheduled date for refueling shutdown:

September 1998 Scheduled date for restart following refueling:

October 1998 Will refueling or resumption of operation thereafter require No a Technical Specification change or other license

. amendment?

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-i

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

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(b) in the spent fuel storage pool 2236

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(c) in new fuel storage vault 8

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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 number of fuel assemblies:

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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:

i Full core discharge capacity to the spent fuel pool was lost after the 1996 refueling outage.

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AVERAGE DAILY POWER LEVEL NET MWe Docket Number :

50-219 Unit:

Oyster Creek #1 Report Date:

March 7,1997 Compiled By:

John D. Dougher Telephone Number:

(609) 971-2130 Month: February,1997 DAY MW DAY MW l.

643 16 629 2

649 17 632

.3 634 18 631 4'

641 19 632 5

640 20 630 j

6 643 21' 631 7

640 22 638 8

641 23 641 9

642 24 640 10 642 25 641 11 638 26 640 12 595 27 639 13 625 28 638 14 628 15 633 o

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UNIT SHUTDOWNS AND POWER REDUCTIONS l

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f DOCKET NO:

50-219 UNIT NAME:

Oyster Creek DATE:

March 12.1997 i

COMPLETED BY: David M. Esan TELEPHONE:

609/971-4818 REPORT MONTH. February.1997 l

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TYPE METHOD OF SHUITING CORRECTIVE ACTIONS / COMMENTS No.

DATE' F: Forced DURATION REASON DOWN THE REACTOR OR j

S: Scheduled :

(hours)

(1)

REDUCING POWER (2)

There were no significant shutdowns or power

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rhianc during this reporting penod.

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SUMMARY

. (1) REASON (2) METHOD a.

Equipment Failure (Explain)

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Operator Training & Lic Exam'.

1.

Manual b.

Maintenance or Test f.

Ads-deinsetive 2.

Manual Scram c.

Refueling.

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Operational Error (Explain) 3.

Automatic Scram d.

Regulatory Restriction h.

Other (Explain) 4.

Other (Explain) f f

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