ML20137V536

Monthly Operating Rept for Nov 1985

ML20137V536
Person / Time
Site:	Oyster Creek
Issue date:	11/30/1985
From:	Fiedler P, Molnar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8602190606
Download: ML20137V536 (6)

Text

.

i MONTHLY 0 PIRATING REPORT - EVEMBER 1985 At the beginning of the report period, Oyster Creek was in cold shutdown.

On November 11, diesel generator No. 2 was declared inoperable due to failure of the electric governor.

Diesel genera tor No.

I was out -of-servi ce at the time for battery replacement.

On November 12, following completion of battery replacement, diesel generator No. I was returned to service.

On November 15, the electric governor was repaired and diesel generator No. 2 returned to service.

Following completion of outage work scope and surveillances, reactor startup commenced at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> m November 16, and criticality was achieved at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

A drywell inspection was performed at a reactor pressure of 1000 psig on the morning of November 17, during which a smil packing leak on min steam line valve V-25-23 was identified. Subsequent attempts to correct the leak by adjusting valve packing and backseating were unsuccessful.

A decision was mde to continue with plant startup and schedule repairs during the 1986 Refueling Qitage or next target of opportmity.

Reactor power was stbsequently increasad and

'A',

'B' and

'C' electromtic relief valves were successfu'( tes ted.

Primary containment inerting commenced, the reactor mode

,.41 tch placed in "RUN" and the genera tor placed on-l ine at 1526 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.80643e-4 months <br /> on November 18.

Power was increased to 360 We by the end of the day and mintained at that level to establish Xenon eauilibrium to accommodate core flux profile checks.

On the morning of Rvember 20, a generator trip occurred due to a current transformer (CT) failure which activated

'B' phase differential relay 87G.

Since reactor power was greater than 40%, an anticipatory scram occurred.

The failed CT was subsequently replaced with an installed spare.

Reactor startup commenced at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br /> on November 23, and cri ticality was achieved at 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />.

'Ihe reactor mode switch was placed in "RUN" a t 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br /> m Novmber 24 and the generator placed on-line at 0352 hours0.00407 days <br />0.0978 hours <br />5.820106e-4 weeks <br />1.33936e-4 months <br />.

Plant load of 500 We was achieved by the end of the da y.

On November 25, power was increased to 635 We, limited by second stage steam reheaters being out-of-service.

The reheaters were out-of-service due to a fail ed diaphragm in air-operated pressure regulating valve PRV-2.

On November 26, RE22B ma in steam line high flow sensor failed surveillance testing due to a faulty micro-switch.

In accordance with Technical Specifications, a reactor shutdown commenced at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> with plant load at 636 We, Plant shutdown was terminated at 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br /> following switch replacement and completion of required testing.

On November 27, the air-operated pressure regulating valve diaphragm was replaced and second stage steam reheaters returned to service.

Power was subsequently increased to approximtely 650 We and mintained for the balance of the report period.

21j0 Og p 9

542g

Oyeter Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - November, 1985 Name of Facility: Oyster Creek Station #1

Scheduled date for next refueling shutdown: April 12, 1986 Scheduled.date for restart following refueling: October 12, 1986 Will refueling or. resumption of' operation thereafter require.a Technical Specification change or other license amendment?

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

April, 1986 Importent 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 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 = 1204 (c) in the dry storage 4

=

(d) in temporary storage 204

=

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 'o toe spent fuel pool assuming the present licensed capacity:

Reracking of the fuel pool is in progress. Four 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:

November, 1985 3.

UTILITY CONTACT:

JOSEPH R. MOLNAR 609-971-4699 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.

P0 DER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): NONE 11.

REASON FOR RESTRICTION, IF ANY: NONE MONTH YEAR CUMULATIVE 12.

REPORT PERIOD HRS 720.0 8016.0 139729.0 13.

HOURS RX CRITICAL 258.5 6118.5 91746.4 14.

RX RESERVE SHTDWN HRS 0.0 0.0 469.7 15.

HRS GENERATOR ON-LINE 205.6 5838.4 89375.1 16.

UT RESERVE SHTDWN HRS 423.4 753.1 755.8 17.

GROSS THERM ENER (MWH) 368700 10324140 147586469 18.

GROSS ELEC ENER (MWH) 114210 3471180 49854175 19.

NET ELEC ENER (MWH) 106210 3326239 47888804 20.

UT SERVICE FACTOR 28.6 72.8 64.0 21.

UT AVAIL FACTOR 87.4 82.2 64.5 22.

UT CAP FACTOR (MDC NET) 23.8 66.9 55.3 23.

UT CAP FACTOR (DER NET) 22.7 63.8 52.7 24.

UT FORCED OUTAGE RATE 30.7 19.6 10.4 25.

FORCED OUTAGE HRS 91.0 1424.5 10375.6 26.

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

Refueling, April 12, 1986, 6 months 27.

IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A

.6 AVERAGE DAILY POWER LEVEL NET MWe DOCKET #........

50-219 UNIT.......... 0yster Creek #1 REPORT DATE....... DECEMBER 04, 1985 COMPILED BY....... WILLIAM J. EMRICH, J r.

TELEPHONE f...... 609-971-4637 MONTH: NOVEMBER, 1985 DAY MW DAY MW 1.

0 16.

0 2.

0 17.

0 3.

0 18, 75 4.

0 19.

336 5.

0 20, 130 6.

0 21.

0 7.

0 22.

0 8.

0 23.

0 9.

0 24.

358 10.

0 25.

572 11.

0 26.

591

.12.

0 27.

617 13.

0 28.

625 14.

0 29.

625 15.

0 30.

626

50-219 DOCKETNO.

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Ovstor emok DATE Novertber 1985 OMP b- (i

- REPORT MONTil N*r 1985 E

m E,

Cause & Corrective

.$"E "g

I Licensee 3

3g5 Event u'8 Action lo No-Date

{

3 ij H

g3 E 5

jig Report #

No fu Prevent Recurrence O

41 10/19/ 85 S

733.5 B

1 N/A ZZ ZZZZZZ 10M Maintenance Outage 42 11/20/85 F

115.0 A

3 N/A ZZ ZZZZZZ Anticipatory reactor scram due to a generator trip. Generator trip causei by current differential relay 87G actuating when the "B" phase current transformer failed.

r i

2 3

4 t

F: Forced Reason:

Method:

Exhibit G. instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Dasa B-Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG.

D-Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & Ucense Examination F. Administrative 5

Goperational Error (Explain)

Exhibit 1 - Same Source (9/77)

Il Other (Explain)

/'

/

e.

GPU Nuclear Corporation Nuclear

'ergr388 Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

Director December 13, 1985 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) 971-4643.

Very truly yours, IL Pe

. Fiedler Vice President and Director Oyster Creek P8F:KB: dam (0170A)

Enclosuras cc: Director (10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I i

U.S. Nuclear Regulatory Commission i

631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.

Bethesda, MD 20014 NRC Resident Inspector I

Oyster Creek Nuclear Generating Station i

GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation