ML20072G209

Monthly Operating Rept for Jul 1994 for Oyster Creek Nuclear Generating Station

ML20072G209
Person / Time
Site:	Oyster Creek
Issue date:	07/31/1994
From:	J. J. Barton, Edelmann P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-94-2130, NUDOCS 9408240235
Download: ML20072G209 (7)

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GPU Nuclear Corporation

. - Nuclear = "tr 88 Forked River. New Jersey 08731-0388 l

609 971-4000 Writer's Direct Dial Number: j 1

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C321-94-2130 August 11, 1994 U.S. Nuclear Regulatory Commission A rrN: Document Control Desk Washington, D.C. 20555

Dear Sir:

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Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 j Monthly Operating Report - July,1994 l In accordance with the Oyster Creek Nuclear Generating Station Operating 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. I If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.

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Sincerely,

~ f J. uton i

,. . ; s., Vice President and Director l n 1

Oyster Creek JJB/BDEM: jc Attachment (MOR RPT. JULY) l cc: Administmtor, Region 1 Senior NRC Resident Inspector l Oyster Creek NRC Project Manager 9400240235 940731 '

PDR ADOCK 05000219 i I p PDR I GPU Nuclear Corporation is a subsKtiaw of Generaf Puunc Uts.ttes Corporation I l

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SUMMARY

JULY, 1994 1

Oyster Creek entered July operating at full power. On July 5, an Unusual Event l was declared and a 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> technical specification required shutdown commenced I due to both Emergency Service Water Systems being declared inoperable due to i heavy mussel fouling of the systems' heat exchangers. The plant returned to full  !

load at 0750 on July 6 following heat exchanger cleaning. On July 8 through July )

10, July 13, and July 20, the plant reduced load for significant periods to '

maintain the environmental permit discharge temperature limit (Toisen,,ce< 106 F) .

On July 21 at 2200, plant load was reduced to 1220 MWth due to high reactor water sulfate concentrations. Load was not returned to full power until July 23 at ,

0530, when the Reactor Water Clean-Up System was returned to service following  !

maintenance and after sulfate concentrations dropped below 20 ppb. On July 24, I power was reduced due to the environmental permit discharge temperature limit.

On July 25, power was reduced to repair the 'A' high pressure heater tube side relief valve, V-4-85, which was leaking. The plant returned to full load at 0645 on July 26. On July 27, power was limited to core thermal limits (90% MAPLHGR) due to Core Spray System II being out of service for electrical maintenance. The plant returned to full load at 0720 the same day, but reduced power later in the day due to environmental permit discharge temperature limits. The environmental discharge temperature limit was again load limiting from 1620 on July 30 to 0308 on July 31. The plant ended the month at full load.

The plant generated 422,441 net megawatt-hours electric and attained a MDC net 1 capacity factor of 93.1% for the month.  !

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MONTIILY OPERATING REPOIG' LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of July,1994:

LER 94-008 On June 19, 1994, while perfonning an Electromatic Relief Valve (EMRV) Pressure Sensor surveillance, the as-found trip setpoints for the high pressure relief function on two EMRVs j were above that specified in the Technical Specifications. The cause of this occurrence has 1 been attributed to setpoint repeatability and instrument drift. The design setpoint repeatability I allows the as-found value to be within 2.5 psig of the Technical Specification limit. . Previous l surveillance records indicate that these instruments can drift due to changing plant and ambient  !

conditions.

This occurrence is considered to have minimal safety significance as the automatic depressurizarion function of the EMRVs is not affected by these pressure switches, all five EMRVs would have actuated to relieve pressure, the Isolation Condenser System and turbine bypass valves were fully operable, and manual operation of the valves was not affected.

Additionally, a recent Technical Specification Change request was submitted demonstrating that an increase in the EMRV setpoints of 15 psig would have no impact on safety. The pressure switches were adjusted to actuate within the Technical Specification limit.

1.ER 94-009 As a result of design reviews for modifications to be implemented during the 15R refueling outage, an existing design deficiency was identified. A single failure of either of two terminal blocks, one located in each non-vital 4160 volt switchgear I A and IB, could render the automatic initiation of both Emergency Diesel Generator Systems inoperable. The safety significance of this single failure mode is considered to be minimal based upon the very low probability of occurrence of this postulated single failure and the fact that the activation of the Appendix 'R' Local Shutdown Panel would have isolated the single failure and allowed the operators to take manual control of Emergency Diesel Generator number 2.

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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - JULY, 1994 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Currently projected for September 10, 1994 Scheduled date for restart following refueling: Currently projected for November 14, 1994 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 4

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 = 2040 (c) in dry storage = 32 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 l number of fuel assemblies:

Present Licensed Capacity: 2600 Planned Increase in Licensed Storage Capacity: 45 The actual fuel storage capacity of the spent fuel pool is 2645 assemblies.

The projected date of the last refueling that can be discharged to the spent fuel j l

pool assuming the present licensed capacity:

Based on a projected reload of 172 bundles, full core discharge capacity to the spent fuel pool will be lost after the 1994 refueling outage.

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. AVERAGE DAILY POWER LEVEL NET MWe DOCKET #. . . . . . . .50-219 UNIT. . . . . . OYSTER CREEK #1 REPORT DATE, . . . . 08-05-94 COMPILED BY . . . . . . PAUL G. EDELMANN TELEPHONE # . . . .609-971-4097 MONTH: JULY, 1994 DhX MW DAY MW

1. 600 16. 597 2, 591 17 593

3. 599 18, 594

4. 603 19. 593 ,

5. 517 20. 555

6. 528 21. 502

7. 592 22, 378

8. 55G 23, 537

9. 525 24, 582

10. 566 25. 540

11. 599 26. 555

12. 599 27. 577

13. 588 28. 588

14. 596 29. 600

15. 597 30. 567 1

31, 595 i 4

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. OPERATING DATA REPORT OPERATING STATUS

1. DOCKET: 50-219

2. REPORTING PERIOD: 7/94

'3 . UTILITY CONTACT: PAUL G. EDELMANN (609-971-4097)

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)* 632

8. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 610

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 )

12. REPORT PERIOD HOURS 744.0 5087.0 215687.0 13 HOURS RX CRITICAL 744.0 4808.0 144407.0

14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 744.0 4754.6 140956.3

16. UT RESERVE SHTDWN HRS 0.0 0.0 0.0

17. GROSS THERM ENERGY (MWH) 1370688 8947432 242060809

18. GROSS ELEC ENERGY (MWH) 439666 2971769 81216083

19. NET ELEC ENERGY (MWH) 422441 2858090 77905804

20. UT SERVICE FACTOR 100.0 93.5 65.4

21. UT AVAIL FACTOR 100.0 93.5 65.4

22. UT CAP FACTOR (MDC NET) 93.1 92.1 58.9

23. UT CAP FACTOR (DER NET) 87.4 86.4 55.6

24. UT FORCED OUTAGE RATE 0.0 6.5 10.4

25. FORCED OUTAGE HRS 0,0 332.5 16289.8

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

15-R OUTAGE, SEPTEMBER 10, 1994, 65 DAYS

27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE: N/A

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