ML20141H744

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

ML20141H744
Person / Time
Site:	Oyster Creek
Issue date:	04/30/1997
From:	Dougher J, Egan D, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2149, NUDOCS 9705270107
Download: ML20141H744 (7)

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l GPU Nuclear. inc.

( U.S. Route #9 South NUCLEAR Pon OHun Box 388 Forked River, NJ 08731-0388 Tel 609 9714000 May 15, 1997 6730-97-2149 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 - April,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 truly yours, Ur Michael B. Roche Vice President & Director /

Oyster Creek MBR/BDeM/gl M Enclosures cc: Administrator, Region I(2 copies)

NRC Project Manager NRC Resident inspector I 9705270107 970430 "

l PDR ADOCK 05000219 R PDR i .

i Summarv ,

I April 1997 t

i There were two significant shutdowns or power reductions during April 1997. First, power was  !

reduced to 30% on April 19 to perform the quanerly Main Steam Isolation Valve full closure test. i Second, on April 23 a technical specification shutdown was completed after failure of control rod i scram time testing. The plant generated 324,919 MWh net electric, which was 73.0% ofits MDC j

rated capacity.

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MONTHLY OPERATING REPORT Licensee Event Reports- April 1997 LER 97-003 was filed April 10,1997 -

i On March 11,1997, while post maintenance testing was in progress on torus spray valve V-21-18, operations personnel identified that the pressure suppression function of primaiy containment had been inadvertently degraded. By opening valve V-21-18, a flow path was i created from the drywell to the torus airspace which would have bypassed the suppression i pool in the event a loss ofcoolant accident (I,0CA) occuned. This could result in inadequate steam suppression from the drywell and over-pressurization of the torus. The condition existed for a total of about ten minutes, therefore, exposure to the risk was minimal. The cause of this event has been determined to be an inadequate safety review of the change of PM 9441M from an outage task to an on-line task. This resulted in inadequate precautions in thejob order and maintenance procedures that controlled the evolution. Upon discovery, shift supervisors notified affected operations personnel that when a torus spray valve is cycled, the associated test valve must be closed. A process will be developed and implemented to allow review of work activities and preparation of i switching orders by operations personnel other than the on-shift control room staff. The process for revising PMs will be reviewed and revised to address potential impacts on performing a PM when the plant is in a different mode than specified.

LER 97-004 was filed April 25,1997 During a detailed review of motor operated valves for periodic verification in response to Generic Letter 96-05, it was discovered that reactor water cleanup valve V-16-2 was being used to fill and vent the cleanup system while the reactor is at power and operating {

pressure. If V-16-2 is open and the downstream pipe were to break, V-16-2 would be i required to close against normal reactor operating pressure. j Delta pressure (delta p) calculations for V-16-2 did not address this event. Therefore, the i valve was not set up to close against reactor pressure of 1020 psig. This oversight is attributed to personnel error in that the prior review missed the use of valve V-16-2 during l power operation.

L . V-16-2 was declared inoperable and deactivated in the closed position to prevent it from i being opened with reactor pressure greater than 125 psig. All engineers will be informed I

of this event and the importance ofdesign "erificatEn through required reading of this LER.

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011$ATING DATA REPORT OPERATING STATUS

, 1.' Docket: 50-219

2. Reponing Period: April,1997

3. Utility

Contact:

John D. Dougher (609) 971- 2130

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 j 8. Maximum Dependable Capacity (Net MWe): 619 i

9. If changes occur above since last repon, give reasons: None

10. Power Level to Which Restricted, if Any (Net MWe): None j 11. Reason for Restriction, If Any: None 4

MONTH YEAR CUMULATIVE

12. Report Period Hours 719.0 2879.0 239783.0

13. Hours Rx Critical 535.9 2695.9 164284.7

14. Rx Reserve Shutdown Hours 0.0 0.0 918.2

15. Hours Generator On-Line 533.3 2693.3 160611.0

16. Ut Reserve Shutdown Hours 0.0 0.0 0.0

17. Gross Thermal Energy (MWh) 989069 5115341 279029422

18. Gross Electric Eenergy ( Wh) 338075 1758314 93687581 i 19. Net Electric Energy (MWh) 324919 1695331 89903897

20. Ut Service Factor 74.2 93.5 67.0 j i

21. Ut Available Factor 74.2 93.5 67.0

22. Ut Capacity Factor (MDC Net) 73.0 95.1 61.1 3 )

]- 23. Ut Capacity Factor (DER Net) 69.5 90.6 57.7

! 24. Ut Forced Outage Rate 25.8 6.5 9.7 j 25. Forced Outage Hours 185.8 185.8 17323.1

26. Shutdowns Scheduled Over Next 6 Months (Type,Date, Duration): None

27. If Currently Shutdown, Estimated Startup Date: May 1,1997

1 Oyster Creek Station #1 1

Docket No. 50-219 Refueline Information - April 1997 l'

j Name of Facility: Oyster Creek Station #1 l Scheduled date for refueling shutdown: September 1998 Scheduled date for restart following refueling: October 1998 l

3 Will refueling or resumption of operation thereafter require a No 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:

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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 =

2236 (c) in new fuel storage vault = 8 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: 2645 1 .

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

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

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. 1 AVERAGE DAILY POWER LEVEL NET MWe l

Docket Number : 50-219 Unit: Oyster Creek #1 ,

Report Date: May 8,1997 - l Compiled By: John D. Dougher.

Telephone Number: (609) 971- 2130  !

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Month: April,,1997 i DAY MW DAY MW l

1 638 16 637 2 641 17 635 l 3 642 18 604 4 638 19 339 h 5 638 20 534 6 639 21 629 f

7 637 22 572 8 640 23 7

9 640 24 0 10 639 25 0 11 639 26 0 12- 638 27 0 13 641 28 0 14 639 29 0

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l 15 639 30 0

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.. t UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-219 .

UNIT NAME: Ovster Creek [

DATE: May 13.1997 COMPLETED BY: Dasid M. Esan TELEPHONE- 609/971-4818 {

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I REPORT MONTH: April.1997 TYPE METHOD OF SHUTTING CORRECTIVE ACTIONS / COMMENTS. [

No. DATE F: Forced DURATION REASON DOWN THE REACTOR OR S: Scheduled (hours) (1) REDUCING POWER (2) ,

0 I 'I 2 970419 S b Po. .r reduced to 30% for MSIV Full Closure Test. .

t 3 970423 F 185.8 a 1 Plant manually shutdown per Tech Specs due to i failure of CRD Scram Time Test. -

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SUMMARY

(1) REASON (2) METHOD

a. Equipment Failure (Explain) c. OperatorTraining & Lic Exam 1. Manual i

b. Maintenance orTest f. Administrative 2. Manum Scram  !

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

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

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