ML20212L902

Monthly Operating Rept for Oct 1986

ML20212L902
Person / Time
Site:	Oyster Creek
Issue date:	10/31/1986
From:	Baran R, Fiedler P, Notigan D GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8701290426
Download: ML20212L902 (8)

Text

r MONIHLY OPERATING REPORT - OCIDBER 1986 Throughout the report period, Oyster Creek remained shutdown for the Cycle 11 Refueling / Maintenance / Modifications Outage.

At the beginning of the report period, the vessel head was "in place" and the vessel flange and head were heated to 1000F in support of head bolt torquing.

Tensioning of the head bolts and installation of the reactor head mirror insulation was completed on October 7.

On October 9, following completion of reactor heat-up, in-service leakage testing of the vessel and associated pressure boundaries comenced.

At 500 psig reactor pressure, a successful preliminary inspection of eauipment within the drywell was performed.

The in-service leakage pressure was reached at approximately 7:00 p.m.

Inspections performed revealed the vessel head inner seal and the lower flange on

'A' recirculation pump to be leaking.

The reactor remained pressurized until October 12 to conduct control rod drive scran testing and excess flow check valve (EFCV) testing.

During EFCV testing, three (3) full reactor scram signals were experienced due to procedure deficiencies.

The procedural problems were resolved and EFCV testing was completed.

The reactor head was removed (October 14) and inspections revealed that a seal retainer clip had become dislodged during head installation which was believed to have been the cause of head seal leakage.

The seal seating surface and the vessel and head flanges were inspected and determined to be satisfactory.

Both the inner and outer seals were replaced and the reactor head was set "in place" on October 15.

The lover flange bolts on 'A' recirculation pump were adjusted in an attempt to correct the flange gasket leak.

Following completion of leak repairs and vessel reassembly, a second in-service leakage test was performed on October 20.

Inspections revealed evidence of a small leak past the inner reactor head seal and the 'A' reactor recirculation pump flange gasket.

The effects of leakage from the reactor head seal and recirc pump flange were evaluated by Plant Engincering and Technical Functions.

The evaluation included review of Technical criteria of the seals with the reactor manufacturer.

Subsequent to the evaluation, a management decision was made that no additional repairs would be made to the inner reactor head seal or recirc pump flange.

In the case of the reactor head, the evaluation concluded i

that the outer seal will function to assure system integrity and plant safety will not be compromised.

The dryve]1 head was installed on October 22 and preparations were completed for the Primary Containment Integrated Leak Rate Test (PCIIRT).

Containment pressurization was completed on October 26.

Several small leaks were identified and corrected.

The PCIIRT was satisfactorily completed on October 29.

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e' MONTHLY ~ OPERATING REPORT-0CTOBER 1986 The following Licensee Event Reports were submitted during the month of October 1986:

Licensee Event Report 50-219/86-021 - Six Nuclear Safety Related (NSR) systems were determined not to satisfy the seismic design bases of the plant (ANSI B31.1), during the performance of the computer analyses to support the 1985/1986 efforts in response to IE Bulletins 79-02 and 79-14.

These findings have previously been individually discussed with Region I of the USNRC.

All NSR systems currently, as a minimum, satisfy ASME III operability limits.

GPU Nuclear has committed to having all systems within the scope of IEB 79-02 and -

79-14 meet ASME III operability limits prior to restart from the refueling outage llR, and meet the original design bases (ANSI B31.1) prior to restart from refueling outage 12R.

Licensee Event Report 50-219/86-024 - As a result of reanalysis, loads calculated for primary containment piping penetrations in the Isolation l

Condenser System, due to a postulated high energy line break in the process 1

piping within the penetrations exceed designed limits.

The potential loss of containment integrity is not in accordance with the plant's original design basis.

This condition is considered to be reportable in accordance with

' 10CFR50.73(a)(2)(ii)B.

The condition has been existent since original plant design and construction.

It was determined reportable on September 11, 1986.

A modification to limit penetration stress levels, due to a postulated high energy line break, to within Code allowables is planned for the next (Cycle 12R) refueling outage.

Operation during the next Cycle (Cycle 11) is justified by a combination of low pipe failure probability concurrent with very limited isolation condenser operation and leak-before-break analysis.

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Licensee Event Report 50-219/86-025 - On September 14,1986 at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br /> the "B" 4160V electrical bus was inadvertently grounded resulting in actuation i

of several engineered safety features including Diesel Generator 2 (DG-2).

When the electrical distribution system was restored, DG-2 tripped sooner than expected.

An operability test was performed on the diesel.

During the operability test a DISABLED alarm was received, resulting in DG-2 being declared inoperable for over 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

A dirty alarm contact was discovered and repaired.

During this time both Standby Gas Treatment Systems were l

considered inoperable. The loss of "B" 4160V bus also resulted in the loss of both operating instrument air compressors.

The subsequent loss of instrument l

air allowed the Control Rod Drive scram valves to drift open, which resulted in a Scram Discharge Volume hi-hi level scram.

The cause of the event has l

been determined to be personnel error in closing a ground breaker which grounded the line side of a 4160V unit substation during megger testing of a Circulating Water Pump motor.

Immediate corrective actions were taken to restore the plant to normal conditions.

Future corrective actions will l

include a check-off sheet to control ground breakers, technician training on l

ground breakers, and possible purchase of ground breakers that will close only onto the load side.

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MONTHLY OPERATING REPORT - OCTOBER 1986 Licensee Ev:nt Raport - Page 2 Licensee Event Report 50-219/86-027 On September 30, 1986 at approximately 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />, secondary containment isolated and the Standby Gas Treatment System initiated when an area radiation monitor power supply was inadvertently grounded during a surveillance.

At the time of the event, the plant was in a refueling outage with the reactor subcritical and the mode switch locked in REFUEL. The grounded power supply was replaced with a spare which spiked at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />, causing another secondary containment isolation and Standby Gas Treatment System initiation.

The original power supply was reinstalled after repairs were completed.

The apparent cause of the occurrence was personnel error, compounded by a design deficiency. Other than an unnecessary challenge to an engineered safety feature, this event had no safety significance.

Corrective action will be as follows:

(1) repair and test the spare power supply that spiked; (2) review the APRM power supply calibration and test procedure for adequacy; (3) issue this LER as required reading for all Instrun:entation and Controls personnel; and (4) consideration of a design improvement for the test contacts of this and similar power supplies.

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Oyster Creek Station il Docket No. 50-219 REFUELING INFORMATION - OCIOBER,1986 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Currently in Cycle 11 Refueling Outage Scheduled date for restart following refueling: November 21, 1986 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes Scheduled date(s) for submitting proposed licensing action and supporting information:

Submitted June 17, 1986 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 by the NRC. New operating procedures, if necessary, will be submitted at a later date.

2. Exxon Fuel Assenblies - no major changes have been made nor are there any anticipated.

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

=

(b) in the spent fuel storage pool = 1392 (c) in dry storage 20

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

Reracking of the fuel pool is in progress. Six (6) out of ten (10) racks have been installed to date. When reracking is completed, discharge capacity to the spent fuel pool will be available until 1990 refueling outage.

1619B

OPERATING DATA REPORT OPERATING STATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD.

OCIOBER, 1986 3.

UTILITY CONfACT:

DONALD V. NOTIGAN 609-971-4695 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):

650 8.

MAXIMUM DEPENDABLE CAPACITY (NET MWe):

620 9.

IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

NONE

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

N/A

11. REASON FOR RESTRICTION, IF ANY:

NONE MOtTfH YEAR CUMULATIVE

12. REPORT PERIOD HRS 745.0 7296.0 147769.0 4

13. HOURS RX CRITICAL 0.0 2311.5 94758.9

14. RX RESERVE SHTDWN HRS 0.0 448.5 918.2

15. HRS GENERA'IOR ON-LINE 0.0 2273.9 92333.0

16. UT RESERVE SHTDWN HRS 0.0 452.8 1208.6

17. GROSS THERM ENER (MWH) 0 4074338 152951807

18. GROSS ELEC ENER (MWH) 0 1371480 51662165

19. NET ELEC ENER (MWH)

-3373 1304164 49612765

20. Ur SERVICE FACTOR 0.0 31.2 62.5

21. UT AVAIL FACIOR 0.0 37.4 63.3

22. UT CAP FACIOR (MDC NET) 0.0 28.8 54.2

23. UT CAP FAC1ER (DER NET) 0.0 27.5 51.7

24. UT FORCED OUTAGE RATE 0.0 6.3 10.3

25. FORCED OUPAGE HRS 0.0 152.3 10587.9

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

N/A

27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: November 21, 1986 1965B

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4-AVERAGE DAILY POWER LEVEL NET MWe DOCKET 4........ 50-219

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UNIT............ OYSTER CREEK #1 REPORT DATE....... NOVEMBER 3,' 1986 i

COMPILED BY....... DONALD V. NOfICAN TELEPHONE #...... 609-971-4695 MotfrH OCTOBER,1986 DAY MW DAY MW 1.

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UNITSiluTDOWNS AND POWER REDUCTIONS TN f oyster Creek DATE october, 1986 REPORTA10NHI October, 1986 COMP D BY 5

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F: Forced Reason:

Method:

Exhibit G-Instsections S: Scheduled A-Equipment Failure (Explain) l-blanual for Preparation of Dasa B Maintenance of Test 244anual Scrase.

Entry Sheets for Licensee C-Refu: ling 3-Automatic Scram.

Event Report (LER) File (NUREG-i D-Regulatusy Restalction 4 Other (Explain) 0161)

E-Operatus Training a Ucense Examination F-Administrative 5

Exhibit I-Same Source G Operational F: os tExplaia)

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GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

Director November 18, 1986 Office of Management Information U.S. Nuclear Regulatory Comission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly 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 Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Mr. Joseph D. Kowalski, Oyster Creek Licensing Manager at (609)971-4643.

ry t 21y urs j

h Peter B. F e r

Vi e Presi.de t and Director O ster Cre PBF:BP: dam (0841A)

Enclosures l

cc: Director (10) i Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Washington, DC 20555 Dr. Thomas E. Murley, Administrator l

Region I l

U.S. Nuclear Regulatory Comission 631 Park Avenue l

King of Prussia, PA 19406 l

Mr. Jack N. Dolohew, Jr.

U.S. Nuclear Ragulatory Comission 7920 Norfolk Avenue, Phi'llips Bldg.

l Bethesda, MD 20014 NRC Resident Inspector i

l Oyster Creek Nuclear Generating Station

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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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