ML20069L440

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

ML20069L440
Person / Time
Site:	Oyster Creek
Issue date:	05/31/1994
From:	J. J. Barton, Egan D, Krall J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-94-2102, NUDOCS 9406200017
Download: ML20069L440 (7)

Text

. , , ,

GPU Nuclear Corporation 0,,. - Nuclear o

en:r388 Forked River, New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number: (

1 C321-94-2102 June 14, 1994 l

U.S. Nuclear Regulatory Commission '

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

1

Subject:

Oyster Creek Nuclear Generating Station ,

Docket No. 50-219 l Monthly Operating Report - May,1994 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 information) for the Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.

Sincerely, I

'\QCD ^

f MP J. . B rton ice resident and Director Oyster Creek JJB/BDEM: jc Attachment (MOR-RPT.MAY) cc: Administrator, Region i Senior NRC Resident Inspector Oyster Creek NRC Project Manager 9406200017 940531 4

{DR ADOCK 05000219 PDR

[h ' I

/

I GPU Nuclear Corporation is a subsidiary of General Pubhc Ubblies Corporabon l

2Ccau

e s

SUMMARY

MAY,1994 Oyster Creek entered May at full power operation. On May 22 at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />, the plant commenced a technical specification shutdown due to failure of the 'B' Control Rod Drive pump discharge stop check valve, V-15-10. The generator was taken off line at 1832 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97076e-4 months <br />. Following sepairs, the plant went back on line at 1603 on May 26. On May 31 at 1332 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.06826e-4 months <br /> while operating at full power, an autcmatic reactor scram occurred on a turbine-generator trip due to JCP&L work in the switchyard inadvertently actuating a generator protective relay. The plant renained in shutdown mode for the renainder of the reporting period.

The plant generated 393,364 net megawatt hours electric and attained a MDC net capacity factor of 86.7%

for the month.

4 I

MONTIILY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of May,1994:

LER 94-003 On 04/05/94 at 1550 hrs. a turbine trip and reactor scram occurred due to high reactor water level. The cause of the event was the GFJMAC Propontional amplifier, (ID-23J), which provides a density correction signal to both A& B steam flow signals. This resulted in a false high steam flow signal which resulted in the feedwater control system increasing feedwater flow to the mactor which caused reactor water level to increase. When water level mached the high level turbine trip setpoint of 175", the turbine tripped and a reactor scmm occurred as designed. The faulty electronics modules were replaced and the feedwater flow control system was returned to operational status.

LER 94-004 Calculations performed as part of the Generic Letter 89-10 Motor-Operated Valve (MOV)

Program for the Isolation Condenser System (ICS) DC-powered isolation valves determined that the voltage available at the motor operator combined with the dynamic blowdown conditions existing during ICS high energy line break (HELB) isolation would produce valve closure times greater than the design condition of 60 seconds identified in the Final Safety Analysis Report (FSAR) Section 6.3.2.5 and Table 6.2-12. The mot cause of this condition was the reevaluation of the design capabilities of the motor-opemted valves as a result of the Generic Letter 89-10 program recommendations.

The safety significance is considered to be minimal since the calculated valve stroke times for the subject valves meet the design criteria for establishing isolation times for high energy line breaks (HELB). These criteria are defined in Oyster Creek Technical Specification Section 4.5 Basis and Oyster Cmek FSAR Section 6.3.2.5.

The 60 second isolation design time requirement in the FSAR will be revised for these valves, in conjunction with the results of the ongoing Oyster Creek Generic Letter 89-10 MOV Program.

i j . . Oyster Creek Static" #1 j Docket No. 50-219 l -

1  !

REFUELING INFORMATION - MAY, 1994 l

Name of Facility: Oyster Creek-Station #1 l

Scheduled date for next refueling shutdown: Currently projected for l 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? l 1

No l l

l Important licensing considerations associated with refueling, e.g., new or 1 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 (b) in the spent fuel storage pool = 1962 (c) in dry storage - 8 l 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:

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 pool assuming the present licensed capacity: i 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.

NRC_RPT.WPD/123

.- . . ~ . . . . . .- ~ .- _

l l .

l-

. AVERAGE DAILY POWER LEVEL ,

NET MWe DOCKET #. . . . . . . . .50-219 UNIT. . . OYSTER CREEK #1 RF1' ORT DATE. . . . . 06-06-94 l

COMPILED BY . . . . . JIM KRALL l

l TELEPHONE # . . . . . .609-971-4115 l

MONTH: MAY, 1994 DAY My DAY MM

1. 619 16, 617

! 2. 622 17. 623 i

3. 621 18. 622

-4. 623 19. ii24

5. 625 20, 626 l 6. 626 21. 625 '

1 l 7. 625 22, 421 I 1

8. 625 23. O

! 9 624 24. 0

10. 624 25. 0 l

11. 622 26. 101

12. 620 27. 609

13. 625 28. 619 l 14. 625 29. 618 15, 621 30. 615

31. 343 l

l

[

f

! NRC_RPT.WPD/124 l

l l__ _ _ _ _ _ __ __ ._ _ _ _ - -

._ 4__ . . _ . _ . _ . . _ _ . ._ _ - - . ~ _ . _. __ _. _._ . . . . . _ ,

l l

r . . . .

l

. OPERATING DATA REPORT  ;

OPERATING STATUS l

1. DOCKET:, 50-219 l

2. REPDRTING PERIOD: 5/94 l 1

3. UTILITY CONTACT: JIM KRALL (609)971-4115

4. LICENSED THERMAL POWER (MWt): 1930 ,

1

5. NAMEPLATE RATING (GROSS MWe) : 687.5 x 0.8 = 550 j

6. DESIGN ELECTRICAL RATING (NET MWe)- 650

7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe) ; 632 l

8. MAXIMUM DEPENDABLE CAPACITY (NET MWe); 610

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

NONS

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

NONE l

11. REASON FOR RESTRICTION, IF ANY:

NONE I

MONTH YEAR CUMULATIVE

12. REPORT PERIOD HOURS 744.0 'C23.0 214223.0 i l

13. HOURS RX CRITICAL 658.0 3367.6 .142966.6 14 ., RX RESERVE SHUTDOWN O.S 0.0 0.0 918.2

15. MRS GENERATOR ON-LINE 640.0 3323.0 139524.7

16. UT RESERVE SHTDWN HRS 0.0 0.0 C.0

17. GROSS THERM ENERGY (MWH) 1224305 6262276 239375653

18. GROSS ELEC ENERGY (MWH) 409169 2105840 80350154

19. NET ELEC ENERGY (MWH) 393364 2026000 77073714

20. UT SERVICE FACTOR 86.0 91.7 65.1

21. UT AVAIL FACTOR 86.0 91.7 65.1 .

I

22. UT CAP FACTOR (MDC NET) 86.7 91.7 58.7 1

23. UT CAP FACTOR (DER NET) 81.3 86.0 55.4 l

24. UT FORCED OUTAGE RATE 14.0 8.3 10.4

25. FORCED OUTAGE HRS 104.0 300.0 16257.3 l

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

i 15-R OUTAGE, SEPTEMBER 10, 1994, 55 - 65 DAYS

27. IF CURRENTL'. SFUTDOWN, ESTIMATED STARTUP DATE:

6/2/94 NRC_RPT.WPD/125

l UNIT SHUTDOWNS AND POWER REDUCTIONS i

l DOCKET NO: 50-219 UNIT NAME: Oyster Creek DATE: June 06. 1994 COMPLT'D BY: David M. Ecan TELEPHONE: 971-4818 REPORT MONTH: May 1994 TYPE METHOD OF SHUTTING CORRECTIVE No. DATE F: Forced DUE.ATION REASON (1) DOWN THE REACTOR OR ACTIONS / COMMENTS S: Scheduled (hours) REDUCING POWER (2) 4 940522 F 93.5 a 1 The reactor was manually shutdown due to failure of

'B' Control Rod Drive Pump stop check valve to prevent reverse flow.

5 940531 F 10.5 a 3 Automatic Reactor SCRAM on turbine-generator trip due to JCP&L work in switchyard inadvertently actuating a generator protective relay.

SUMMARY

(1) REASON (2) METHOD

a. Equipnent Failure (Explain) e. Operator Training & Lic Exam 1. Manual

b. Maintenance or Test f. Adninistrative 2. Manual Scram

c. Refueling g. Operational Error (Explain) 3. Automatic Scram

d. Regulatory Restriction h. other (Explain) 4. Other (Explain)

- _ . _ . _ . - - - . _ _ _ _ _ _ _ _ . _ _ _ - - - _ - _ - . . _ - - _ _ - _ - - . - - _ - _ _ ..