ML20078K263

Monthly Operating Rept for Aug 1983

ML20078K263
Person / Time
Site:	Oyster Creek
Issue date:	09/06/1983
From:	Baran R, Fiedler P, Molnar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8310190031
Download: ML20078K263 (8)

Text

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MONrHLY OPERATIONS REPORT AUGUST 1983 At the beginning of the report period, the Oyster Creek Station remained shutdown for the 1983 Refueling / Maintenance Outage.

Diesel generator No. 1 tripped during a fast start test. Diesel generator No. 2 was taken out of service to check for the same problem.

Both diesel generators were simultaneously out of service for a one day period. In order to meet secondary containment requirements of Oyster Creek Technical Specifications (loss of Standby Gas Treatment System redundant standby power supply), no work was allowed in and around the spant fuel pool while both diesel generators were out of service. The NRC was notified of this condition.

Thirty-seven (37) fuel bundles were relocated in the spent fuel pool in preparation for receiving new fuel in early September.

Tripping of the Reactor Protecton System motor generator (MG) set output breaker, which was identified as a breaker problem, has been resolved.

The instantaneous overcurrent trip element setpoint drifted low such that the breaker was tripping on MG set starting current.

The plant continued to experience problems with the air compressors.

Leaking relief valves and unloading problems were identified as the main causes for the air compressors being out of se:vice on numerous occasions in August. Plant Engineering / Materiel Management investigated and, as a result, are ordering a new type of relief valve for the air compressors.

In order to reduce unnecessary radwaste water processing, a plan was developed and implemented to operate the Condensate Transfer System to the Control Rod Drives (CRD) intermittently, and as required to support radwaste processing. With Plant Engineering concurrence, condensate transfer to the CRD drives is operated for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period at 10 day intervals. This is sufficient to keep the CRD drive seals wet and reduces the demand on radwaste processing by approximately 13,000 gallons per day.

Additionally, the following items were considered noteworthy:

j 1.

Reactor Building Closed Cooling Water (RBCCW) Pump 1-1 was out of service numerous times during the report period due to breaker problems.

2.

Fire diesel pump 1-1 was temporarily inoperable to correct a vibration problem.

3.

Due to a failure of the power feed lines to the dilution pumps, a punp trip occurred. Power cable repairs were completed within three (3) days.

4.

The SRM/IRM drive mechanisms were repaired (new shafts installed).

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Unit Substation "lAl" was out of service for a ten hour period due to failure of the undervoltage coil in breaker "1A1M".

6. -

"B" condensate pump tripped due to a ground fault. Plant Engineering is evaluating the problem.

7.

Modification to the reactor mode switch was completed. A scram signal will no longer be generated when transferring from the

" Shutdown" position to the " Refuel" position.

8.

A leak in the RBCCW System was identified at the 1-3 drywell fan / cooler. The component has been tagged out for repairs.

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. The following Licensee Event Report was submitted during August 1983:

Reportable Occurrence No. 50-219/83-17/OlP:

On August 16, 1983, Diesel Generator (DG) No. 1 tripped during a fast start test. DG No. 1 was then declared inoperable. After a thorough review of the test data, it was determined on August 26, 1983 that DG No. 2 might have the potential for the same problem. At that time, DG No. 2 wcs also taken out of service and appropriate measures were taken to ensure that Technical Specification requirements regarding secondary containment were met. Both DGs were returned to service on August 27, 1983 following corrective action.

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. M Exhibit G. Instructions 4L F: Foeced Reason:..

Method:

S orPteparationc(Data S: Scheduled A Equipment Failure (Explain) i-Manual f

B-Maintenance orTest 2 Manual Scram.

Entry Sheets for Licensee C Refeeling.

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Event Report (LER)Fde(NUREG.

D Regulatony Restaktion 4 Osher(Explain) 0161)

E4perator Training & Ucense Examination 1

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G-Operational Esrut(Explain)

Exhibit I.Same Source (9/77) flother (Explain) l l

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e AVERAGE DAILY POER LEVEL NET We DOCKET 4........ 50-219 UNIT........... Oyster Creek #1 REPORT DATE.......SEPffMER 02, 1983 ONPILED BY-....... JOSEPH R. IOLNAR TELEPHONE #...... 609-971-4699 MONfH AUGUSf,1983 DAY IW DAY W

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OPERATING DATA REPORP OPERATING STATUS 1.

DOCKET:

50-219 2.

PEPOREING PERIOD:

August, 1983 3.

UfILITY CONTACT:

JOSEPH R. MOIRAR 609-971-4699 4.

LICENSED THERMAL POWEiR (MWt):

1930 5.

NAMEPIATE RATING (GROSS Mie):

687.5 X 0.8 = 550 6.

DESIGN ELECTRICAL RATING (NET MWe):

650 7.

MAXIME DEPENDABLE CAPACITY (GROSS M4e):

650 8.

MAXIMUM DEPENDABLE CAPACITY (NET Mie):

620 9.

IF GANGES OCCUR ABOVE SINCE LAST REPORE, GIVE REASONS:

NONE 10.

POWER LEVEL 'IO WHIGI RESTRICIED, IF ANY (NEf M9e) :

N/A 11.

REASON EOR RESTRICTION, IF ANY:

WA MONTH YEAR CLMULATIVE 12.

REPORP PERIOD HRS 744.0 5,831.0 119,999.0 13.

HOURS RX CRITICAL 0.0 1,009.6 84,622.8 14.

RX RESERVE SIffDW HRS 0.0 0.0 468.2 15.

HRS GENERATOR ON-LINE 0.0 1,007.8 82,693.6 16.

UI RESERVE SHTDW HRS 0.0 0.0 0.0 17.

GROSS 'IHERM ENER (M*I) 0.0 853,300.0 136,224,730.5 18.

GROSS ELEC ENER (MWH) 0.0 244,630.0 46,056,905.0 19.

NET ELEC ENER (M41)

-1,484.0 212,044.0 44,292,572.0 20.

Uf SERVICE FACIOR 0.0 17.3 68.9 21.

UT AVAIL FACIOR 0.0 17.3 68.9 22.

Uf CAP FACIOR (MCD NET) 0.0 5.9 59.5 23.

Ur CAP FACIOR (DER NET) 0.0 5.6 56.8 24.

Uf EORCED OUTAGE RATE 0.0 0.0 9.7 25.

EORCED OUfAGE HRS 0.0 0.0 8,916.8 26.

SHUIDON4S SCHEDULED OVER NEXT 6 MNfHS (TYPE, DATE, DURATION): WA 27.

IF CURRENTLY SHUIDOWN ESTIMATED STARPUP TIME:

01/12/84

Oyster Crask Station #1 Docket No.50-21o REFUELING INFORMATION - August, 1983 Name of Facility:

Oyster Creek Station #1 Scheduled date for next refueling shutdown: Presently shutdown for Refueling Scheduled date for restart following refueling: January 12, 1984 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

T,:chnical Specification Change Reauest No. 96 was submitted on August 31, 1982 for incorporation of GE fuel assemblies into the Cycle 10 core.

Scheduled date(s) for submitting proposed licensing action and supporting in fo rma t i'on:

Oct.1,1983 - The final supplement to the reload analysis, delineating the specific core configuration for Cycle 10 operation, will be submitt.ed.

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

2.

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

l The number of fuel assemblles (a) in the core o

L (b) in the spent fuel storage pool -

1341 l

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, l

in number of fuel assemblies:

Present: 1,800 Planned: 2,600 i

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present 1icensed capacity:

The Spring 1987 Outage.*

• NOTE: This is for a normal refueling. Full core off-load, however, can only be accommodated through about 1983 or 1984 with 1,800 t

l licensed locations.

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1 GPU Nuclear g

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P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:

September 16, 1983 Director Office of Management Information U.S. Nuclear Regulatory Commission Washington, D.C.

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. Michael Laggart at (609) 971-4643.

Very truly yours, O

Petsr B. Fiedler Vice President and Director Oyster Creek PBF:PFC: dam Enclosures cc: Director (10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Regional Administrator (1)

Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 I

NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 GPU Nuclear is a part of the General Pubhc Utihties System

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