ML20135B468

Monthly Operating Rept for June 1985

ML20135B468
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1985
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8509110066
Download: ML20135B468 (7)

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MON 111LY OPERATING REPORT - JUNE 1985 At the beginning of the report period, Oyster Creek was operating at 640 We.

Power was maintained between 635 and 650 We with load restricted by core thermal (MAPUKR) and condensate header pressure limitations.

On June 10, power was decreased to 610 We to reduce Feedpump motor stator temperatures.

Power was increased to approximately 640 We late that_ day after a maximin allowable operating temperature was established by Plant Fngineering.

On June 12 the Electric Pressure Regulator (EPR) failed causing No. I turbine bypass valve to open.

Reduction of steam pressure resulted in automatic closure of Main Steam Isolation Valves (MSIVs) which caused a j

reactor scram.

1 Following completion of repairs and surveillances, reactor startup commenced on June 17; criticality was achieved on Jtme 18.

Containment inerting connenced on June 19.

Power was increased and the reactor mode switch placed in "Run".

-'Ihe plant operated at 447 We until the evening of June 21, to establish xenon equilibrium to accommodate core flux profile checks. Power was maintained between 630 and 650 We for the balance of the report p6Flod, with load being restricted by intake temperature and its effect on condenser vacuum.

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8509110066 950630 PDR ADOCK 05000219 R

PDR 0202g

Monthly Operating R; port The following Licensee Event Reports were submitted during the month of June 1985:

Licensee Event Report 50-219/85-009 - As the result of an electrical load study performed for Oyster Creek, it has been determined that 480 Vcit Unit Substation (USSS) 1 A2 or 1B2 my be overloaded during a loss of coolant accident with offsite power available and concurrent loss of one Unit Substation.

The cause of this deficiency has been determined to be a design problem, and the fact that the impact of plant modifications on bus loadings was not evaluated for this particular set of conditions.

Corrective actions are planned to install fans to increase transformer capacity and install an overcurrent alarm for the buses.

Licensee Event Report 50-219/85-010 - Following a check of IRM setpoints, it was discovered that several upscale and downscale setpoints had exceeded Technical Specifications limts.

A new refueling IRM alignment 9rocedure will be developed and a test device modification to enhance setpo.nt testing is being evaluated.

Licensee Event Report 50-219/85-011 - During routine surveillance test, 3 out of 4 isolation condenser automatic actuation pressure sensors tripped at values greater than specified in Technical Specifications.

The sensors in question were reset to trip within desired setpoint limits.

d.

i OPERATING DATA REPORT g '.

OPERATING STATUS 1

1.

DOCKET:

50-219 2.

REPORTING PERIOD:

June 1985

)

i 3.

UTILITY CONTACT:

JOSEPH R. MOLNAR 609-371-4699 4.

LICENSED THERMAL POWER (MWt):

1930 i

5.

NAMEPLATE RATING (GROSS MWe):

687.5 X 0.8 = 550 j

6.

DESIGN ELECTRICAL RATING (NET MWe):

650 1

7.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

650-l' 8.

MAXIMUM DEPENDABLE CAPACITY (NET MWe):

620 1

l 9.

IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

NONE 5

i 10.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): N/A f

11.

REASON FOR RESTRICTION, IF ANY:

NONE MONTH YEAR CUMULATIVE i

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12.

REPORT PERIOD HRS 720.0 4344.0 136057.0 I

13.

HOURS RX CRITICAL 583.1 3548.1 89176.0 1

14.

RX RESERVE SHTDWN HRS 0.0 0.0 469.7 i

15.

HRS GENERATOR ON-LINE 549.8 3372.5 86909.2

[

16.

UT RESERVE SHTDWN HRS 0.0 19.6 22.3 j

i 17.

GROSS THERM ENER (MWE) 1025000 5881940 143144269 t

s.

18.

GROSS ELEC ENER (MNE) 340150 2001860 48384855 i

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19.

NET ELEC ENER (MWH) 326233 1920938 46483503 i

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UT SERVICE FACTOR 76.4 77.6 63.9 i

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21.

UT AVAIL FACTOR 76.4 78.1 63.9.

22.

UT CAP FACTOR (MDC NET) 73.1 71.3 55.1 l

23.

UT CAP FACTOR (DER NET) 69.7 68.0 52.6 t

24.

UT FORCED OUTAGE RATE 23.6 22.0 10.2 i

170.2 951.9

. 9903.0

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FORCED OUTAGE HRS l

26.

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

f j

j OCTOBER 1,1985 - (1 month)

I 27.

IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:

N/A s

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I AVERAGE DAILY POW 8R LEVEL NET MWe 1

DOCKET 4........

50p219

.Oy,ter Creek il,

'j UNIT..

s REPORT DATE.

. JULY 0 3, 1985 i

COMPILED BY.......WIhIAMJ.EMRICH,JR.

TELEPHONE $...... 609-971-4637 4

MONTH JUNE, 1985 i

DAY MW DAY MW 1.

619 16.

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2.

616 17.

0l, l.

3.

613 18.

0' 1

113f l

4.

615 19.

1 5.

619 20.

439 I

6.

624 21.

496}

1 I

7.

622 22.

606l

• l 8.

617 4.J.

608 3

i 9.

620 24.

610f i

1 10.

611 25.

614 3

l 11.

604 26.

621l 12.

244 27.

625 l t

i 13.

0 28.

627',

14.

0 29, 627 15.

0 30.

622l l

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l Oyctor Crock Staticn $1 Dockst Ns. 50-219 l

REFUELING INFORMATION - June, 1985 Name of Facility: Oyster Creek Station il Scheduled date for next refueling shutdown:

April 12, 1986 Scheduled date for restart following refueling: October 13, 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:

December, 1985 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 1

analysis methods have been approved by the NRC.

New operating procedures, if necessary, will be submitted at a later date.

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

=

(b) in the spent fuel storage pool = 1193 (c) in dry storage 4

=

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: 2,600 The projected date of the last refueling that can be discharges to the spent fuel pool assuming the present licensed capacity:

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

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OPU Nuclear Corporation Nuclear 288 Forked River, New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:

July 12, 1985 Director Office of Management Information U.S. Nuclear Regulatory Commission 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. Drew Holland at (609) 9/1-4643.

ry truly ours,

/

P B. Fiedle

( President and Director 1

yt er Creek PDF:KB: dam (0170A)

Enclosures cc: Director (10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station

,.pA 9{.

Forked River, NJ 08731 GPU Nuclear Corporabon is a subsidiary of the General Put)hc Ubbties Corporation

.