ML20080U006

Monthly Operating Rept for Jan 1984

ML20080U006
Person / Time
Site:	Oyster Creek
Issue date:	01/31/1984
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8403020128
Download: ML20080U006 (8)

Text

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MONTHLY OPERATIONS REPORT JANUARY Throughout the report period, the Oyster Creek Station remained shutdown for the current refueling / maintenance outage.

The reactor vessel remains defueled.

Control rod drive (CRD) replacement and CRD blade shuffle / replacement was completed during the report period.

Also, underwater CCTV inspection and debris removal below the core plate was completed.

Presently, LPRM nuclear instrumentation replacement is in progress.

Emergency diesel generator No. 1, along with Standby Gas Treatment System No. 1, was returned to an operable status on January 22, 1984 after cable replacement and the annual diesel inspection.

Pultiple problems were encountered during testing of the diesel generator.

Corrective maintenance was performed to resolve the problems.

The Operations Department is periodically testing diesel generator No. I to insure its reliability prior to re leasing diesel generator No. 2 for its annual inspection.

Presently, diesel generator No.

2 is scheduled to be released for. maintenance on February 1,1984.

The new HFA relay installation was completed on both Reactor Protection Systems.

The Operations Department experienced numerous pressure control problems with the Reactor Building heating, ventilation and cooling system due to the _ degraded condition of the dampers in the building's supply and exhaust fans.

Failure of the steam heating coils for the Re ac to r, Turbine and Office Building supply fans are also causing temperature problems in these buildings.

The M&C Department is presently attempting to make repairs to the heating system.

On January 6,

1984, while returning "B"

waste sample tank to the hotwells, a valving error (i.e.,

the hotwell isolation valves were closed) caused damage to the expansion - joints on the suction of the condensate pumps.

The expansion joints will be replaced later in this outage.

On Ja nuary 8,

1984, control rod olade 26-31 was inadv::rtently dropped after cell fuel support casting reassembly was completed.

When the fuel s upport casting tool was raised to the area of the upper grid, the operator noticed that the control rod blade was hung up on the tool.

The operator started to lower the tool to reinsert the blade.

Subsequently, the blade was lowered to the point where the velocity limitor had just entered the guide tube when the blade slipped off the tool and fell into the guide tube.

A detailed inspection of the blade and guide tube was performed with the plant's underwater CCTV.

No evidence of damage to the control rod blade sheath, velocity limiter, or the guide tube was observed.-

The seal on "B"

fuel pool pump was replaced.

At the end of the report period, repairs to the-pump's check valves was in progress.

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Monthly Optrat'icns hle'p3rt Page 2

.The plant experienced numerous start problems with service water pump 1-2.

_ Initially, the problem was beli.eved to be a trip-latch adjustment problem on the pump's b reaker.

However, further investigation revealed the problem to be the overloads on the breaker being set too low.

Repairs 'were 'in progress on fire diesel pump 1-2 at the_end of the report

period after, relief valve replacement was completed.

Some minor discrepancies vere identified (flange leaks, RPM and run tim? meter malfunction) et the end of the relief velve replacement job.

Testing of the pump will be performed when the repairs c.re completed.

Fuel pool ' inventory and restorage ' of equipnent in the fuel pool in pre parationi f or installation of the new spent fuel storage racks is in-progres s.

The ' reactor steam dryer weld repair was completed.

Air compressor 1-2 remains' out of service dae to the lack of gasket material required. to resssemble the. compressor.

Gasket material is on order.

The compressor was-initially taken out of service on January 4, 1984 'due to low interstage pressure problems..

Condensate transfer pump 1-1 is inoperable due to a leaky pump seal.

Transfer of alarms.to the' new Control Room alarm panels was completed in Januery.

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De following Licensee Event Reports were submitted during January 1984:

Reportable Occurrence No.'50-219/83-24/01T-

' On December 20,-1983, during a review of the torque' switch setpoints of the~Limitorque motor operated valves at Oyster Creek, it was discovered that

the'setpoints on many motor operated valves had been set lower than the enufacturer's data. che apparent 'cause of this occurrence is attributed to Llacklof sufficient' knowledge.concerning setpoint design basis and how the-setpoints affect safety system functioning.

Innediate corrective action was

. initiated to investigate the design basis of each valve operator in different systems.~

- %e following' corrective actions on isolation' and safety-related valves

. ill be initiated prior'to startup:-

w 1.

Complet! ion of: the actual design basis investigation 2.

Determining the appropriate torque switch setpoints 3.- Resetting.the torque switch setpoints on'all applicable valves

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4. : Issue administrative controls to eliminate recurrence of this incident A follow up report will.be issued upon coupletion of the investigation.

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Reportable Occurrence No. 50-219/83-25/03L L n December'1, 1983,Lduring a review of the' plant' procedures, six (6) 0 maintenance and two.(2) surveillance procedures were identified as not adequately addressing the Technical Specification requirement that each time

' an instrument line is returned to service after any condition which could have produced a pressure or flow disturbance in that-line,othe open position of the flow check valve in that line shall be verified. - 'Ihe cause of this occurrence ri is attributed to the failure to include instructions in the procedures which would insure verification of proper post-maintenance operation. - As corrective a

action,Lall. excess; flow check valve affected by the deficient procedures will

- be verified open prior-to returning the associated systems to service;

. deficient procedures will.be revised to meet Technical Specification

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UNITSilUTDOWNS AND POWER REDUCI1ONS I

O lyster Creek.

DATE-2/1/ "

REPORTMONTil January 1984.

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1 N/A ZZ-ZZZZZZ Start of the 1983 Refueling and Maintenance Outage.

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F: Fo.ced Reason:

Method:

Exhibit G. instructions S: Scheduled A Equipment Failure (Explain) 1 Manual

-l for Preparation of Data B Maintenance of Test 2 Manual Scram.

Entry Sheets for I.icensee C Refueling 3-Autematic Scram.

Event Repoet (1.ER) File (NUREG-D-Regulatoey Restaktion 4-Othet (Explain) 0161)

I E-OperatorTraining& Ucens. Izandnation j

F-Adtr/nistrative 5

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G4prational Error (Explain)

(9/U) llother(Explain)

Exhibit I-Same Source

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OPPJtATING DATA REP 0lff OPERATING STATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD:

January, 1984 3.

UTILITY CONTACT:

JOSEPH R. MOLNAR 609-971-4699 4.

LICENSED THERMAL POWER (MWt):

1930 5.

NAMEPLATE RATING ('ROSS MWe):

687.5 X 0.8 = 550 G

G.

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 'IO WHICH RESTRICTED, IF ANY (NET We): N/A 11.

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

REPORT PCRIOD HRS 744.0 744.0 123672.0 13.

HOURS RX CRITICAL 0.0 0.0 84623.9 14.

RX RESERVE SHTDWN HRS 0.0 0.0 468.2 15.

HRS GENERA'IOR ON-LINE 0.0 0.0 82693.8 16.

UT RESERVE SHTDWN HRS 0.0 0.0 0.0 17.

GROSS THERM ENER (MWE) 0.0 0.0 136224729 18.

GROSS ELEC ENER (MWH) 0.0 0.0 46056905

-19.-

NET ELEC ENER (MWH)

-1991

-1991 44283692

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20.

UT SERVICE FAC'IOR 0.0 0.0 66.9 21.

UT AVAIL PAC'IUR 0.0 0.0 6G.9 22.

UT CAP FAC'IOR (MDC NET) 0.0

-0.4 57.8 23.

'Fr CAP FAC'IOR (DER NET) 0.0

-0.4 55.1 24.

UT FORCED OUTAGE RATE 0.0 0.0 9.7 25.

FORCED OUTAGB HRS 0.0 0.0 8916.8 26.

SHUTDOWS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION): WA 27.

IF CURRENTLY SHITfDOWN ESTIMATED STARTUP TIME:

4/29/84

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e AVERAGE DAILY POWER LEVEL NET MWe DOCKET f........

50-219 UNIT..

.0yster Creex #1 REPORT DATE....... FEBRUARY 6, 1984 COMPILED BY

.-..... DONALD V. NOTIGAN TELEP110NE !......

609-971-4695 MONTil JANUARY,1984 DAY MW DAY MW 1.

0 16.

0 2.

0 17.

0 3.

0 18.

0 4.

0 19.

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0 20.

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0 22.

0 8.

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0 9.

0 24.

0 10.

0 25.

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Dyster Creek Station #1 Dockat No. 50-219 REFUELING INFOR.4ATION - January,1984 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:

Presently shutdown for Refueling Scheduled date for restart following refueling:

April 29, 1984 Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?

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

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

October 28, 1983 - The final supplement to the reload analysis, delineating the specific core configuration for Cycle 10 operation, was submitted.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysio methods, significant changes in fuel design, new operating procedures:

1. General Electric Puel 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 0

=

(b) in the spent fuel storage pool = 1375 Tho '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 assembites:

Present:

1,800 Planned:

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

Full-core of fload capability will be lost af ter the 1985 outage.

Ba tch discharge capability will be lost af ter the 1987 outage.

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

e

GPU Nuclear Corporation Nuclear

gen:;388 ForkedRiver NewJersey08731-0388 609 971-4000 Writer's Direct DialNumber:

February 10, 1984 Director Office of Managemerit Information U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Oyster Creck 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, Y.V., )

)(Wl.

eter B. Fiedler ice President an rector Oyster Creek PBF:PFC: dam Enclosures cc: Director '10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission l

Washington, D.C.

20555 Regional Administrator (1)

Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station I

f Forked River, NJ 08731 GPU Nuclear Corporation is L subsidiary of the General Public Utilities Corporation t