ML20076C574

Monthly Operating Rept for June 1991 for Oyster Creek Nuclear Generating Station

ML20076C574
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1991
From:	J. J. Barton, Sedar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-91-2192, NUDOCS 9107220245
Download: ML20076C574 (7)

Text

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OPU Nuclear Corporation d

D L UCIOBr R'1 ;t?388 fc.thed ther. New Jersey 08731 0388 009 971 4000 Wr,ter's DJoct D a! Numbe',

C321-91-2192 July 12,1991 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C.

20555 Dear Sirs Subjects Oyster Creek Nuclear Generating StatAon Docket No. 50-219 Menthly Operating Report 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 Oynter Creek Huclear Generating Etation.

If you should have any questione, please contact Dranda DeMerchant, Oyster Creek Licensing Engineer et (609) 971-4642.

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B r on V: President and Director ster Creek

/BDM jr Enclosures ces Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager (MOR) 9107220245 910630 PDR (4 DOCK 05000219 j

n PDR f ( e GPU Nucler.t Corporaton is a subsdary of Genera' PutAc Utat;e Corporation

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MONTHLY OPERATING REPORT - JUNE 1991 At the beginning of the report period, Oyster Creek was shutdown for the 13R outage. The RPV Hydrostatic Test was completed on June 3, 1991.

Shutdown Margin Testing was completed on June 25, 1991.

Preparations-for plant startup were completed and the reactor startup commenced at 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br /> on June 25, 1991.

The reactor achieved criticality at 1937 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.370285e-4 months <br /> on the same day. On June 26, 1991, at 0723 hours0.00837 days <br />0.201 hours <br />0.0012 weeks <br />2.751015e-4 months <br />, power ascension was halted to evaluate main condenser vacuum concerns. At 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br /> on the same day, the decision was made to recommence power ascension.

On June 27, 1991, while maintaining reactor pressure at 1000 peig, the drywell was entered for a planned inspection as part of the power ascension plan. No discrepancies were noted. The drywell was subsequently secured and inerting of the primary containment was commenced at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br /> on June 27, 1991.

l The reactor mode switch was placed in RUN at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on Jane 27, 1991. The main generator was placed on line at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> on June 28, 1991. At the end of the. report period, the plant was operating at 70% reactor power with a gross-generator output of 407 MWo.

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MONTHLY OPERATING REPORT JUNE 1991 The following Licensee Event Reports were submitted during the month of June, 1991:

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OPERATING DATA REPORT OPERATING STATUS

1. DOCKET:

50-219

2. REPORTING-PERIOD:

6/91

3. UTILITY CONTACT:

JOHN SEDAR (609)971-4698

4. LICENSED THERMAL POWER (MWt):

1930

5. NAMEPLATE RATING (GROSS MWe):

687.5x0.8=550

6. DESIGN ELECTRICAL RATING (NET MWe):

650

7. MAXIMUM DEPENDADLE CAPACITY (GROSS MWe):

647

8. MAXIMUM DEPENDADLE CAPACITY (NET MWe):

620

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

NONE

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

NONE

11. REASON FOR RESTRICTION, IF ANY:

NONE MOtO' XEh8 CUMULATIVE

12. REPORT PERIOD HOURS 720.0-4343.0 188639.0 a

13. HOURS RX CRITICAL 124.3 1235.3 120300.5

14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 68.8 1178.0 117091.0

16. UT RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THERM ENERGY (MWH) 73032 2172120 197067076

18. GROSS ELEC ENERGY (HWH) 17130 724160 66330083

19. NET ELEC ENERGY (MWH) 12286 682384 63642416

20. UT SERVICE FACTOR 9.6 27.1 62.1 21.'UT AVAIL FACTOR 9.6 27.1 62.7

22. UT CAP FACTOR (MDC NET) 2.8 2b.3 54.4

23. UT CAP FACTOR (DER NET) 2.6 24.2 51.9

24. UT FORCED OUTAGE RATE 0.0 0.0 11.5

25. FORCED OUTA0X HRS 0.0 0.0 15270.0

26. SHUTDOWNS SCHEDULED OVER i4 EXT 6 MONTHS (TYPE, DATE, DURATION):

NONE

7. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE

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NRC_RPT.WPD/18

AVERAGE DAILY POWER LEVEL NET MWe DOCKET #..

. 50219 UNIT.

. OYSTER CRE}.K #1 REPORT DATE.

JULY 8, 1991 COMPILED BY

. JOHN H. SEDAR TELEPHONE #.

.609-971-4698 HONTH:

JUNE, 1991 M

M M

W 1.

0 16.

0 2.

0 17.

0 3.

0 18.

0 4.

0 19.

0 5.

0 20.

0 6.

0 21.

0 7.

0 22.

0 8.

0 23.

0 9.

0 24.

0 10.

0 25.

0 11.

0 26.

0 12.

0 27.

0 13.

0 28.

96 14.

0 29.

276 15.

0 30, 29, NRC_RPT.WPD/17 l

s Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - JUNE, 1991 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:

Novec.ber 27, 1992 Scheduled date for restart following refueling:

February 9, 1993 Will-refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes Technical Specification change Request 180 was submitted to the NRC on 5-07-90.

This submittal was made in accordance with GL 88-16 to incorporate cycle specific parameters in a core operating limits report.

Important licensing cor.siderations associated with refueling, e.g.,

new or different fuel design or suppl. er, unrevieved design or performance analysis methods, significant changes in fuel design, new operating procedures Fuel design and 1.

General Electric Fuel Assemblies performance analysis methods have been approved by the NRC.

2.

Exxon Fuel Assemblies - No major changes have been made nor are there any anticipated.

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

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(b) in the spent fuel storage pool = 1708

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(c) in dry storage 44

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1 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity tnat has been requested or is planned, in number of fuel assemblies:

Present Licensed Capacity:

2600 The projected date of the last refueling that can be discharged to the opent' fuel pool assuming the present licensed capacity:

The reracking of the fuel pool is now complete.

All ten (10)

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racks are now installed.

Discharge capacity to the spent fuel pool will be available through the 1994 refueling outage.

NRC_RPT.WPD/16 I

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-219 UNIT NAME Ovster Creak DATE July, 1991 i

COMPLETED BY T. Corcoran TELEPHONE 971-4986 REPORT MONTH June, 1991 t

4 TYPE METHOD OF SHUTTING Fx Forced DURATION DOWN THE REACTOR OR NO..

DATE St Scheduled (Fours)

REASON (1)

REDUCING POWER (2)

CORREC1IVE ACTIONS / COMMENTS 104 910216 S

651.3 C

1 Shutdown for 13R Refueling Outage i

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105 910628 S

O.9 B

1 Turbine Overspeed Test and Calibration.

9-(Procedure 625.4.001) 3 s

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Summary (1) REASON (2) METHOD t

a.

- Equipreent Failure (Explain) e.

Operator Training & License Exam 1.

Manual I

b.

Maintenance or Test f.

Administrative 2.

Manual Scram q

~L c.

Refueling g.

Operational Error (Explain) 3.

Automatic Scram d.-

Regulatory Restriction h.

Other (Explain) 4.

Other (Explain) f I

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