ML20082B944

Monthly Operating Rept for Oct 1983

ML20082B944
Person / Time
Site:	Oyster Creek
Issue date:	10/31/1983
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8311210379
Download: ML20082B944 (8)

Text

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4 MONTHLY OPERATIONS REPORT October 1983 j

h roughout the report period the Oyster Creek station remained shutdown j

for the 1983 Refueling / Maintenance Outage.

i During the report period, the overhaul of reactor boundary valves-in the Recirculation System, Reactor Coolant Cleanup System, and Shutdown Cooling System was completed. We reactor head was removed and the reactor vessel was j

reflooded. %e Reactor Coolant Cleanup System was placed in service and once l

adequate water clarity was established the annulus shield blochs were l

removed. %e reactor cavity was flooded to a few feet above the reactor vessel flange on October 27th to identify the location of a cavity leak; y

however, the source of the leak was not identified. %e leak was not

}

significant enough to prevent delaying the flooding evolution, thus flooding l

of the reactor cavity was recommenced on October 29th and completed on October 31, 1983. Investigation into the cavity leak location will proceed when the cavity is drained again later in the outage.

CRD Pung "B" ~is currently out-of-service due to a bearing problem.

"A" CRD Pump was inoperable for a one day period due to an oiler problem.

i We plant continued to experience air compressor problems during the j-report period. Air compressor No. 1 'was out of service twice during the report period for a total of 16 days. ' Air Compressor No. 2 was inoperable once during the report period for two days. Air Compressor No. 3 was out of service four different times in October for a total of approximately four j

days. he major problems with the air compressors continue to be valve f

related. Air Conpressor No.1 also had piston seal ring problems.

i on October 12, 1983, the plant lost the entire "A" side of the' plant's electrical system due to a fault on emergency bus "1C".

me cause of the i

fault was traced to one of the cables running from bus "lC" to Diesel Generator No. 1.

Due to this malfunction, Diesel Generator No. l'will remain

^

inoperable until cable replacement is completed. %e cables from the bus to Diesel Generator No. 1 were disconnected and "lC" bus was returned to service H

on October 20, 1983. Cable was ordered.to complete the required cable replacement. Presently, the 'Iurbine Building, Reactor Building,.and Intake...

I i

Structure Motor Control Centers (lAl, lA2, lA3) are cross-tied to the "B" bus ~

l side of the plant's electrical system to facilitate maintenance:on electrical; breakers. Emergency bus "lC" is being supplied by startup transformer:"SA".-

i We condensate transfer system was returned to service after valve and 4

-line leak repairs were completed.

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. At the end of the report period, final preparat' ions were being made to start recirculation valve packing and recirculation pump seal replacement and the uncoupling of approximately 50 CRD's to support the CRD rebuild / replace effort.

'Ihe following items were also considered noteworthy:

1.

"D" Augmented Fuel Pool Pump was out of service on three different occasions during the report period due mainly to pump bearing problems.

"B" Fuel Pool Pump was inoperable for a one day period due to an electrical problem.

2.

Overhaul of Fire Diesel Pump No. I was completed. Presently overhauling Fire Diesel Pump No. 2.

3.

Service Water Pump No. I was inoperable for a one day period for breaker maintenance. Service Water Pump No. 2 was out-of-service twice during the report period, once for a megger check and once for repairs to its oiler solenoid valve. Currently, No. 2 Service Water Pump remains out-of-service for solenoid valve repairs.

4.

Plugging of RBCCW Heat Exchanger 1-1 was completed. Plugging of RBCCW Heat Exchanger 1-2 is in progress in conjunction with shell weld repairs.

5.

'Ine first two phases of torus sandblasting were completed. Personnel are currently performing NDE of the torur-Vent headers and shell to evaluate a pitting problem.

6.

Both fuel zone level instrumentation channels were made operable to support vessel flood.

7.

'Ihe Stack Gas Sample System isokinetic probe was reinstalled.

8.

The Stator Winding Cooling System was secured and drained for maintenance and inspection.

9.

Inspection / rebuild of MSIV NSO4A and NSO4B comenced. Reassembly of NSO4B started on October 22nd (no major problems with valve).

Inspection of MSIV NSO4A is in progress.

10.

A plant emergency drill was held on October 25, 1983.

b

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

Reportable Occurrence No. 50-219/83-20/03L:

On September 16, 1983, while performing undervoltage (W) trip time operability and trip bar actuation torque tests of 480 V switchgear breakers, service water pump 1-2 circuit breaker failed to trip when the W device was de-energized. This condition would have prevented the associated diesel generator load sequence timer from operating within the time limitation specified in the Technical Specifications had a loss of offsite power occurred. The cause was high torque on the W device trip shaft due to a burr on the latch surface of the trip latch. Complete preventive maintenance was performed on the breaker, the burr removed, and the breaker satisfactorily tested and returned to service.

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50-219 l

UNITSilUIDOWNS AND POWER REDUCVONS DOCKETNO.

UNITNAME Oyster creek DATE 11-1-83 REPORT &f 0NTil October 1983 COhfPLETED By R.

Baran TELEPilONE 971-4640 I

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=.c 3 Licensee E*

E4 Cause & Cosacclive c

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Date g

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.g g 5 Event u3 Adion to

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jis y Report

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}d Psevent Recurrence d

31 2-11-83 S

6288 C

1 N/A ZZ ZZZZZZ Start of'1983 Refuel / Maintenance outage t

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2. - -

3 4

F: Forced Reason:

hicthod:

Exhibit G-Instrucilons S: Scheduled A Equipment Failure (Explain) l blanual for Preparation of Data B hfaintenance or Test -

2 blanualScram.

Entry Sheets for Licensee C-Refueling-3 AutomaticScraan.

Event ReporI(LER) File (NUREG-D Regulatory Restriction 4Oher(Explain). '

0161) j E4perator Training & Ucense Esandnation

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F. Administrative 3

5 Coperaalonal Ensus (Explain)

Exhibis 1 -Same Sousee (9p?)

Il Other (Explain) g

OPERATING DATA REPORT OPERATING SfATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD:

October, 1983 3.

UfILITY CONTACT:

JOSEPH R. MOINAR 609-971-4699 4.

LICENSED THERMAL POWER (lWt):

1930 5.

NAMEPIATE RATING (GROSS We):

687.5 X 0.8 = 550 6.

DESIGN ELECTRICAL RATING (NET IWe):

650 7.

MAXIMLN DEPENDABLE CAPACITY (GROSS We):

650 8.

MAXIMLM DEPENDABLE CAPACITY (NET We):

620 9.

IF CHANGES OCCUR ABOVE SINCE IAST REPORE, GIVE REASONS:

NONE 10.

POWER LEVEL 'IO WHIG RESTRICTED, IF ANY (NE7f We):

11.

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

REPORP PERIOD HRS 745.0 7,296.0 121,464.0 13.

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

RX RESERVE SRfDW HRS 0.0 0.0 468.2 15.

HRS GENERA'lDR ON LINE 0.0 1,007.8 82,693.6 16.

UI RESERVE SHEDW HRS 0.0 0.0 0.0 17.

GROSS THERM ENER (1M1) 0.0 853,300.0 136,224,730.5 18.

GROSS EIEC ENER (MH) 0.0 244,630.0 46,056,905.0 19.

NET EIEC ENER (1W1)-

-1,730.0 208,853.0 44,289,381.0 20.

UT SERVICE FACIOR 0.0 13.8 68.1-21.

Uf AVAIL FACIOR 0.0-13.8' 68.1 22.

Uf CAP FACIVR (MCD NErf) 0.0 J4.6-58.8-23.-

Uf CAP FACIOR (DER NETP) 0.0 4.4 56.1-24.

Ur EDRCED OUTAGE RATE

-0.0 0.0 9.7

'25.

FORCED OUPAGE HRS 0.0

-0.0' 8,916.8 26.

SHUrDOWS SCHEDULED OVER NEXT 6 MONEHS (TYPE, DATE, DURATION):. N/A.

27.

IF CURRENfLY SHUIDOWN ESTIMNIED STARIUP TIME:

03/23/8'4 l

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AVERAGE DAILY POER LEVEL NET M4e DOCKFJP f........ 50-219 UNIT........... Oyster Creek #1 REPORP DATE.......NOVDEER 03, 1983 00MPILED BY....... JOSEPH R. MOLNAR TELEPIONE 9...... 609-971-4699 M0tml OCIOBER,1983 DAY g

DAY g

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.

0 14.

0 29.

0 15.

0 30.

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Oyster Creek Station il Docket No. 50-219 l

REFUELING INEDRMATION - October,1983 Name of Facility: Oyster Creek Station il l

1 Scheduled date for next refueling shutdown: Presently shutdown for Refueling i

Scheduled date for restart following refueling: March 23, 1984 l

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

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Technical Specification Change Request No. 96 was submitted on August 31, 1982 for incorporation of GE assenblies into the Cycle 10 core.

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

4 October 28, 1983 - W e final supplement to the reload analysis, i

delineating the specific core configuration for Cycle 10 operation, was submitted.

i 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 NBC. New operating j

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

1

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

.%e number of fuel assemblies (a) in the core 0

=

(b) in the spent fuel storage pool =.1375 h e present licensed spent fuel pool storage capacity and the size of any

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-increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present:

l'800 Planned:-

2,600 he projected date of the last refueling ~ that can be discharged to the spent fuel pool assuming the present licensed-capacity:

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Full core offload capability will be lost after the 1985 ' outage. Batch j

discharge capability will be' lost after the 1987 outage. Expanded i

spent fuel pool rack capacity (2,600) is scheduled for.1984. -

5

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:

November 15, 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.p stions, please contact Mr. Michael Laggart at (609) 971-4643.

Very truly yours, t

Pdter 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 h

Forked River, NJ 08731 h

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