ML20141A502

Monthly Operating Rept for May 1997 for Oyster Creek Nuclear Generating Station

ML20141A502
Person / Time
Site:	Oyster Creek
Issue date:	05/31/1997
From:	Dougher J, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2183, NUDOCS 9706230039
Download: ML20141A502 (7)

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l GPU Nuclear, Inc.

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U S. Route #9 South NUCLEAR Post Office Box 388 Forked Nyer, NJ 08731-0388 Tel 609-9714000 I

Jtme 16,1997 6730-97-2183 i

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report - May,1997 i

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, r

h Michael B. Roche Vice President & Director p

Oyster Creek MBR/BDeM/gl Enclosures I

cc:

Administrator, Region I (2 copies)

. NRC Project Manager g

i NRC Resident Inspector I

^

9706230039 970531 PDR ADOCK 05000219 R

PDR 000021

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MONTHLY OPERATING REPORT Licensee Event Reports - May 1997 j

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I-LER 97-005 was filed on May 8,1997.

On April 8,1997 it was identified that the most recent Standby Liquid Control System (SLCS) sodium pentaborate solution Boron-10 (B-10) enrichment surveillance determining the B-10 enrichment solution results were not received within 30 days of sampling. Technical Specification Section 4.2.E.5 states, "If not received within 30 days, notify NRC (within 7 j

days) of plans to obtain test results." This notification was not made.-

The cause of this event was determined to be an inadequate procedure in that Technical Specification requirements were not included in permanent plant documents.

The safety significance of this event is considered minimal. When the results were received, the B-10 enrichment atom percent was within specification. Therefore, the SLCS was capable j

of performing its intended function at all times.

Corrective actions include revising appropriate plant documents to reflect the Technical Specification requirement.

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LER 97-006 was filed on May 19,1997.

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On April 19,1997, control rod scram time testing was performed on a reference sample of seven control rods for Scram Solenoid Pilot Valve (SSPV) performance monitoring based on BWR Owners' Group recommendations. The tests revealed that the 5% scram j

insertion times had increased over previous tests, and the average 5% insertion time for these seven rods exceeded complete core average Technical Specification time limit. The reactor was shutdown to address the degraded performance.

The apparent root cause of this event was the sticking of the Viton A diaphragms in the SSPVs.

The safety significance of this event was determined to be minimal, because the small delay in 5% insertion time has a negligible effect on design basis accident and transient analyses.

While the reactor was shutdown, the diaphragms for all SSPVs were replaced with a new Viton 515 A-B material designed to prevent the sticking experienced with Viton A.

Subsequent scram time tests have shown a marked imprcvement in 5% insenion time.

An evaluation will be performed to determine the need for a new test program on the

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SSPVs.

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i AVERAGE DAILY POWER LEVEL NET MWe

~ Docket Number :

50-219 l

Unit:

Oyster Creek #1 Report Date:

June 5,1997 L

Compiled By:

John D. Dougher Telephone Number:

(609) 971-2130 l

l Month: May,1997 l

DAY MW DAY MW 1

0 16 625 2

0' 17 631 3

0-18 633 4

0 19 629 5

53 20 631 6

143 21 634 7

307 22 629 8

624 23 637 9

632 24 632 l

10 635 25 631 L

l 11 635 26 630 12 632 27 633 13 631 28 634 14 632 29 632 15 631 30-630 31 629 C

,L.-.,

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l, OPERATING DATA REPORT OPERATING STATUS l

1. Docket:

50-219

2. Reporting Period:

May,1997

3. Utility

Contact:

John D. Dougher (609) 971-2130 4.

Licensed Thermal Power (MWt):

1930

5. Nameplate Rating (Gross MWe):

68 7.5 x 0.8 = 550 l

6. Design Electrical Rating (Net MWe):

650 l

7. Maximum Dependable Capacity (Gross MWe):

641 l

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

12. Report Period Hours 744.0 3623.0 240527.0

13. Hours Rx Critical 675.5 3371.4 164960.2 l

14. Rx Reserve Shutdown Hours 0.0 0.0 918.2 l

15. Hours Generator On-Line 633.2 3326.5 161244.3

16. Ut Reserve Shutdown Hours 0.0 0.0 0.0 i

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17. Gross Thermal Energy (MWh) 1158485 6273826 280187907 1

18. Gross Electric Eenergy (MWh) 390278 2148592 94077859

19. Net Electric Energy (MWh) 374941 2070272 90278838

20. Ut Service Factor 85.1 91.8 67.0 j

21. Ut Availa' ole Factor 85.1 91.8 67.0-l

22. Ut Capacity Factor (MDC Net) 81.4 92.3 61.2

23. Ut tapacity Factor (DER Net) 77.5 87.9 57.7 l

24. Ut Forced Outage Rate 14.9 8.2 9.8 f

25. Forced Outage Hours 110.8 296.6 17433.9

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

None i

27. If Currently Shutdown, Estimated Startup Date:

N/A 4

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a Oyster Creek Station #1 Docket No. 50-219 l.

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Refueline Informntion - Mnv 1997 i

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l Name of Facility:

Oyster Creek Station #1 j

Scheduled date for refueling shutdown:

September 1998 i

f Scheduled date for restart following refueling:

October 1998 j

Will refueling or resumption of operation thereatler require a No Technical Specification change or other license amendment?

I Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, i

unreviewed design or performance analysis methods, significant changes in fuel design, new operating j

procedures:

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

NRC.

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

=

(b) in the spent fuel storage pool 2236

=

(c) in new fuel storage vault 8

=

j 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 Present Licensed Capacity: 2645 i

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

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

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-219 UNIT NAME:

Ovster Creek DATE:

May I3.1997 COMPLETED BY: David M. Ecan TELEPHONE:

609/971 4 318 REPORT MONTH: June 9.1997 TYPE METHOD OF SIRDTING CORRECTIVE ACTIONS / COMMENTS No.

DATE F: Forced DURATION REASON DOWNTHE REACTOR OR S: Scheduled (hours)

(1)

REDUCING POWER (2) 3 970423 F

i10.8 a

1 Plant manually shutdown per Tech Specs due to failure of CRD Scram Time Test. Plant returned to service on May 5,1997 at 14:46.

SUMMARY

(1) REASON (2) METHOD a.

Equipment Failure (Explain) c.

Operator Training & Lic Exam 1.

Manual b.

Maintenance or Test f.

Administrative 2.

Manual Scram c.

Refueling g.

Operational Error (Explain) 3.

Automatic Scram d.

Regulatory Restriction h.

Other (Explain) 4.

Other (Explain)

Summary May,1997 i

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At the beginning of May, Oyster Creek was completing work from its second unscheduled 1

outage in Cycle 16 (16U2). The plant shutdown on April 23,1997, when it failed to meet the j

technical specifiestion requirements for control rod scram time testing. 16U2 ended on May 5, 1997, at 1446 following repairs and preliminary testing of the CRDs. The plant returned to full q

power on May 3.1937, following successful scram time testing of the control rods. The plant generated 390,278 MWh net electric, which was 81.4% ofits MDC rated capacity.

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