ML20112J743

Monthly Operating Rept for May 1996 for Oyster Creek Nuclear Generating Station

ML20112J743
Person / Time
Site:	Oyster Creek
Issue date:	05/31/1996
From:	Edelmann P, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-96-2199, NUDOCS 9606210035
Download: ML20112J743 (7)

Text

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. > ,, GPU Nuclear Corporatum g ggf Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

June 14, 1996 6730-96-2199 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Oyster Creek Nuclear Generating Station Docket IW 50-219 Monthly Og: rating Report - May,1996 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.

4 If you should have any questions, please contact Ms. Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.

Very truly yours, Michael B. Roche Vice President & Director Oyster Creek MBR/BDeM/gl Enclosures cc: Administrator, Region I (2 copies)

NRC Project Manager NRC Resident inspector 9606210035 960531 /

PDR ADOCK 05000219 R PM 1 GPU Nuclear Corporation is a subsidiary of General Public Utikties Corporation

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SUMMARY

MAY, 1996 I

Oyster Creek went on line at 1426 on May 1 following the 15U4 outage. The plant operated at full load for the remainder of May with minor power reductions for control rod drive flow swaps and CRD/HCU testing.

During the month, the plant generated 445,240 MWh net electric which was 96.7% of its MDC rated capacity.

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LICENSEE EVENT REPORTS SUBMITTED DURING M AY 1996 i

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l LER 96-003 On April 9,1996, at approximately 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, with the plant operating at 100% power, it j was determined that certain 4160 VAC Emergency Electrical Bus Grid Undervoltage relay contacts were not functionally tested as required by plant Technical Speci6 cation Table 4.1-21, items 28 a & b. These instrument channels were declared inoperable and a 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> plant shutdown was commenced in accordance with Technical Speci6 cation 3.0. A.

l On April 10,1996, at approximately 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br />, with the plant operating at 100% power, it was determined that certain Air Ejector Off-Gas (AEOG) line high radiation isolation relay contacts were not functionally tested as required by plant Technical Specification Table 4.1-1, item 15. These instrument channels were declared inoperable and a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> I

time clock was entered in accordance with Technical Specification Table 3.1-1, item I.

Required contact testing was performed for both instrument functions to ful611 Technical i Speci6 cation surveillance requirements. In both cases, contact operability was verified and the respective Technical Specification actions were terminated.

The root cause of these events was inadequate testing procedures.

The safety consequences of these events was minimal. The instrument channels were declared inoperable solely due to incomplete surveillance testing and were fully functional throughout the event, except while each was andergoing testing in accordance with corrective actions. This event is being reported pursuant to 10 CFR 50.73 (a)(2)(i) due to a deviation from plant Technical Specifications.

LER 96-004 On 04/09/96, during leak testing of the Containment Spray System Heat Exchanger 1-1 tubes, the 1-2 heat exchanger thermal relief valve was found in the open position, causing approximately 100 gallons of torus water to leak onto the Reactor Bldg. 23 Ft. Elevation.

This temporarily created an open path between the primary and secondary containments.

The root cause of this event was determined to be accidental valve mispositioning during disassembly and cleaning of the containment spray heat exchanger. A contributory cause was determined to be the installation of thermal relief valves with manual lift levers.

Immediate corrective action was taken to isolate the leak. The leak test of the heat exchanger tubes was reperformed which verified V-21-22 was actually closed. A reemphasis of the need to exercise care when working close to plant equipment was conducted with the personnel invokd in this maintenance activity.

Long term corrective actions include: 1) the removal of the manual lift levers from the thermal relief valves, and,2) performing an evaluation on the practicality of relocating the thermal relief valves.

OPERATING DATA REPORT OPERATING STATUS i

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1. DOCKET: 50-219 l

2. REPORTING PERIOD: May-96

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 l

7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 641

8. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 619 l

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 MONTH YEAR CUMULATIVE

12. REPORT PERIOD HOURS 744.0 3647.0 231767.0 1 1

13. HOURS RX CRITICAL 744.0 3511.6 157844.5 i

14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2  :

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15 ' HRS GENERATOR ON-LINE 729.6 3455.6 154266.3 l

16. UT RESERVE SHTDWN HRS 0.0 0.0 0.0  :

17. GROSS THERM ENERGY (MWH) 1372325 6429538 266949031

18. GROSS ELEC ENERGY (MWH) 462114 2186006 89603581

! 19. NET ELEC ENERGY (MWH) 445240 2106232 85975397

20. UT SERVICE FACTOR 98.1 94.8 66.6

21. UT AVAllFACTOR 98.1 94.8 66.6

22. UT CAP FACTOR (MDC NET) 96.7 93.3 60.5

23. UT CAP FACTOR (DER NET) 92.1 88.8 57.1

24. UT FORCED OUTAGE RATE 1.9 5.2 9.8 j

25. FORCED OUTAGE HR8 14.4 191.4 16729.6 )

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

, 16-R OUTAGE; SEPTEMBER 7,1996; 45 DAYS 1

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

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l Oyster Creek Station #1 Docket No. 50-219 Refueling Information - May.1996 Name of Facility: - Oyster Creek Station #1 Scheduled date for next refueling shutdown: September,1996 -

i 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 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 j by the NRC. [

The Number of fuel assemblies: (a) in the core = 560 (b) in the spent fuel storage pool = 2128 (c) in the new fuel storage vault = 25 (d) in on-site fuel receipt process = 92 l The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity L

that has been requested or is planned, in number of fuel assemblies:

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Present Licensed Capacity

2645 4

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

Full core discharge capacity to the spent fuel pool will be lost after the 1996 refueling outage.

AVERAGE DAILY POWER LEVEL NET MWe DOCKET # . . . . . . . 50-219 UNIT . . . . . . . . . . . Oyster Creek #1 REPORT DATE . . . . . 6/6/96 COMPILED BY. . . . . . . Paul G. Edelmann TELEPHONE #. . . . . . . (609) 971- 4097 Month: May,1996 DAY MW DAY MW 1 77 16 628 2 391 17 632 3 532 18 630 4 631 19 626 i 5 631 20 627 6 632 21 621 f 7 633 22 619 8 632 23 620 9 631 24 618 622 10 631 25 11 625 26 624 12 628 27 626 l

13 632 28 620 14 632 29 631 15 630 30 622 31 617

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UNIT SHUTDOWNS AND POWER REDUCTIONS

• DOCKET NO: 50-219 UNIT NAME: Ovster Creek DATE: June 12. 1996 COMPLT'D BY: David M. Ecan TELEPHONE: 609/971-4818 REPORT MONTH: May 1996 rreu unruoo er snurrras comascrivs acrzess/cr===wrs so. nars r: rerned nomarrow amason (11 pauw run anacrom on 3: scheduled thours) mEDUCING PoemR (2) 4 04/26/96 r 14.4 b/g 1/3 operators umanually shutdown the reactor to retrieve a broken steams Packing Exhauster condenser flapper valve lodged in front of the condensate flow orifice.

An autementic scram on low remoter water level occurred during the subsequent startup. The root cause of this event has been determined to be a failure of the Cao to aggressively control reactor water level in the control band during the start-up using station operating procedures. The scram occarred prior to the turbine going on line (100 reactor power).

SUMMARY

(1) REASON (2) METHOD

a. Equipment Failure (Explain) e. 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)

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