ML20090J153

Monthly Operating Rept for June 1984

ML20090J153
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1984
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8407270419
Download: ML20090J153 (9)

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MONTHLY OPERATIONS REPORT JUNE 1984 te Throughout the report period, Oyster Creek Station remained shutdown for current _ Maintenance'and_ Refueling, i

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. Replacement of the.IRMs/SRMs started and continued throughout the report period.

To.date, IRMs 12, 14,.15, 16 and 18 have been completed.

The major problem experienced with the task is removal of the dry tubes.

The IRM/SRM dry tubes are the originally installed equipment.

Ove r the years, crud has collected in the in-core housing and this is thought to be the major contributor of interference - problems experienced during dry tube removal.

Therefore, cutting of the dry tubes prior to removal is necessary due to the -inability to remove the dry tube by "detenting" the upper grid plunger.

In addition, a considerable amount of time was spent

-on the removal of'SRM 22.

Special tooling had to be fabricated before it i-could be - removed.

Furthermore, a positive _ seal on the replacement dry tube back seat could not be initially obtained.

The new dry tube was successfully replaced on July 5, 1984 The' - top - section of IRM 18 (approximately 18 inches), including the plunger assembly, was discovered missing when this tube was removed (IRM L

18 was one of the IRMs which had a 3600 circumferential crack in its dry tube).

The missing piece was located on. a nearby fuel support

-casting.

The spring; for the plunger. assembly was removed, but the remaining section - remained on the fuel support casting and: will be

removed at the first opportunity.

Replacement of the remaining IRMs/SRMs is the priority task.

In L addition to this work, LPRMs 36-33 and 36-17

-were - replaced during i.nis teport period.

Diesel Generator,, No. 2 was returned' to an operable ~ status on June 5,-

1984. The Diesel Generator was out of service due to a governor actuator 1

. pro blem.'

At the end of the report ' period, the torus. was filled and functional

testing of Core Spray System I was in progress.

When completed, Core l

Spray.- System II'will be released for pump -impeller ' lock nut' inspection..

Fire Diesel Pump 1-1 was inoperable for an extended period of time- (June -

20 to ' July 1).;. The fire. pump was initially taken out of service' for vendor inspection.

However,. upon-te' sting, the pump 'did not meet acceptance criteria for.' discharge ~ pressure.- The problem was traced to a

' faulty pump auto-vent valve which was' repaired.

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Dilution pump No. 2 ran satisfactorily during its 24-hour test run using the recently = installed 90 micron filters with the Fire Water System supplying-flow to the pump-seals.. The system is still unable to operate without use of the Fire Water System.' Additional meetings are being held with the various departments involved in the project to develop a. course of action to resolve the problems.

At the end of the report period the circulating water system tunnel was being prepared for t flooding. The circulating water system is required to support the RBCCW System outage scheduled for early July.

The Operations Department is venting, tiising and performing interference checks on selected CRD's as plant conditions permit.

Testing of the plants' electrical power distribution cables in the turbine building continued throughout the report period.

Replacement of the cable run to "lC" feedwater pump is in progress.

Weld repairs to No. 1-1 RBCCW heat exchanger were completed.

Also, a small leak was identified and repaired (tube plugged) on "A" fuel pool heat exchanger.

It is suspected that the leak was such that the tube leaked only during ' normal operation (when higher differential pressure across the' bundle was established) thus making - it difficult to detect during test conditions.

Air compressor 1-1 was taken out of operation twice during the report period; once for an _ oil change and' once due to an oil - leak.

Air compressor No. 1-2 was out of service twice during the report period;

.once for an oil ~ change and once due to an unloading problem.

M&C was

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working on the unloading problem at the end of the report period.

Air compressor No. 1-3 was removed from service four - different times ' during the report period to support instrument. calibration,. preventive maintenance and to repair oil leaks.

"B" liquid poison pump was declared inoperable for a seven day period due to excess vibration.

Plant Engineering. was requested to take vibration readings and evaluate the data.-

It was determined that the pump was not vibrating excessively and was returned to service.

Weld repairs to the isolation condenser. piping continued throughout the report period, i

The i HFA relay. fogging' ' problem is still'_being investigated by' Plant Engineering.

Testing / analysis of the relays is in progress by. Various.

company' departments and the relay. vendor - (GE).

GE will be. providing. a test procedure' suitable for testing the presently installed relays.

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The following Licensee Event Reports were submitted during June 1984:

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. Licensee Event Report No. 50-219/84-008 s.

While performing Local. Power Range. Monitc (LPRM) rerlacement work during the. outage, operators visually noticed that the dry tube associated 'with Intermediate Range Monitor (IRM) 12 appeared to be bent

. near the upper core' grid.

An underwater TV camera inspection performed on the dry tube in February.1984 showed a significant amount of cracking in.the top' portion i of l tube.

Detai1ed inspection conducted by the QA i

Department revealed - that a total of seven (7) IRM and one (1) SRM ~ dry tubes were _ cracked.., Replacement of these dry tubes will be completed prior to start-up from the present refueling outage.

r Licensee Event Report No. 50-219/84-010 For an undete'rmined number of iterations the fuel pool gates may have 1

been moved over irradiated fuel bundles in the fuel pool.

This violates the Technical-Specifications requiring that no object in excess of the weight of one fuel assembly (approximately 485 lbs.) be moved over stored irradiated fuel.

The handling. procedure for the fuel pool gates will be revised to prevent lifting the gates above irradiated fuel.

Licensee Event Report No. 50-219/84-011 l

Both trains of the Standby -Gas Treatment System were rendered inoperable for nine (9) minutes while performing preventive maintenance on a circuit breaker.

A modification is in progress to eliminate the

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problem of the -inlet and-outlet valves for both trains failing open on 1.

loss of air when the circuit breaker is racked out for maintenance.

Licensee Event-Report No. 50-219/84-014 The test of the Reactor Low Level Instrumentation was not performed within the time period ~ required by Technical Specifications.

The event-4

- is n attributed to personnel error.

The involved personnel have been

-instructed. on their responsibilities as outlined in the' procedure which implements the surveillance test program, j,

Licensee Event Report No. 50-219/84-013 7

Post indicating valve V-9-12 which branches off the fourteen -inch

- Fire Water Main was damaged by a maintenance vehicle.

This resulted in a

- loss of the Fire Suppression Water System. :Immediate actions consisted of isolating the line 'which contained the damaged valve, testing the

. redundant Fire' Protection Water System for operability, and aligning the redundant ' system to1 supply : the underground loop which _ feeds the Fire-Suppressioni Water KSystem. ~ As

-a. result of this ~ incident 'all post

- < indicating valves--in similar high traffic areas were inspected for adequate physical protection.

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Licensee Event Report No. 50-219/84-12 During a scheduled load test on Emergency Diesel Generator No.

1 (EDG-1), a diesel fuel oil day tank low level alarm for unit one was received in the Control Room.

Subsequent investigation revealed that the diesel - fuel oil transfer. pump control switch for EDG-1 was in the OFF position. 'In the OFF position, fuel oil is not automatically transferred to the diesel day tank f rom the main fuel storage tank.

This resulted in EDG-1 being considered inoperable.

Since EDG-2 was out of service for governor repairs, both Emergency Diesel Generators were simultaneously inoperable. Future solutions to be implemented include incorporation of a check of the transfer pump control switch position into the plant tour sheets and installing 'a keylock control on the transfer pump control switch for each Emergency Diesel Generator to prevent repositioning without the Group Shift Supervisor's concurrence.

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r UNITSIIUIDOWNS AND POWER REDUCTIONS NO.'

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UNITNAME Ovster Creek DATE _ 7 /9 / 84 June 1984 COMPLETED BY.

n-naran REPORT 510NTII TELEPIlONE 971-4640

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Cause & Correctise No.

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OQ 31 2-11-83 S

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

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F: Ferced Reason:

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Method:

Exhibit G. tastructions S: Scheduied A Equipment Failure (Explain) 1-Manu21 for Prep 2 ration of Dat:

B. Maintenance or Test 2 Manual Scram-EntrySheets fer Licen ce C-Refueling 3-Automatic Scram-Event Report (LER) Fife (NUREG-D Regulatory Restricriun 4 Other(Explain) 0161) i

. E-OperatorTraining& Ucense Exandnation F-Administrative 5

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Coperatiena! Error (ExplJka)

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4-OPERATING DATA REPORT OPERATING STATUS l

1.-

DOCKET:

50-219 2.

REPORTING PERIOD:

June, 1984 3.

- WILITY CONTACT:

JOSEPH R. MOLNAR 609-971-4699 4.

LICENSED THERMAL POWER ( W t):

1930 5.

NAMEPLATE RATING-(GROSS W e):

687.5 X 0.8 = 550

~6.

DESIGN ELECTRICAL RATING (NET W e):

650 7.

MAXIMN DEPENDABLE CAPACITY (GROSS We):

650 8.

MAXIMlN DEPENDABLE CAPACITY (NET We):

620 9.

IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

NONE 10.

POWER LEVEL 10 WHICH RESTRIGED, IF ANY (NET We): N/A 11.

REASON FOR RESTRICTION, IF ANY: N/A MONTH YEAR CLMJLATIVE 12.

REPORT PERIOD HRS 720.0 4368.0 127296.0 13.

HOURS RX CRITICAL 0.0 0.0 84623.9 4

14.

RX RESERVE SHTDWN 1RS 0.0 0.0 468.2 1

15.

IRS GENERATOR ON-LINE 0.0 0.0 82693.8 16.

UT RESERVE SHTDWN IRS '

O.0 0.0 0.0 17.

GROSS 'DIERM ENER (WH) 0 0

136224729 18.

GROSS ELEC ENER (W H) 0 0

46056905 19.

NET ELEC ENER (WH)~

-2250

-11982 44273701 20.

UT SERVICE FAC1DR

'0.0 0.0 65.0-21.

W AVAIL FACOR 0.0 0.0 65.0 22.

UT CAP FAC10R (MDC NET) 0.0

-0.4 56.1 23.

UT CAP FACTOR (DER NET) 0.0

-0.4 53.5 24.

W R)RCED OWAGE RATE -

0.0 U.0 9.7

.25.

FORCED OWAGE IRS 0.0 0.0 8916.8 26.-

SHUTDOWNS SCHEDULED OVER NEXT 6 M0MHS (TYPE, DATE, DURATION): N/A f

27.

IF CURREELY SIUTDOWN ESTIMATED STARTUP TIME:

8/7/84 p

AVERAGE DAILY POWER LEVEL NET MWe DOCKET #..........50-219 UNIT..........

0yster Creek #1 REPORT DATE....... JULY 03, 1984 00MPILED BY....... DONALD V. NOTIGAN TELEP10NE #...... 609-971-4695 MONTH JUNE, 1984 DAY g

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Oyster Crack Station #1 D:ckat No. 50-219 REFUELING INFORMATION - June, 1984 y

Name of Facility: Oyster Creek Station #1 Scheduled 'date for next refueling shutdown: Presently shutdown for Refueling

< Scheduled ~date for restart following refueling: 8/07/84 Will refueling or resumption of operation thereaf ter require a Technical

. Specification change or other license amendment?

NONE.

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

~information:

1. Amendment #7 to NEDO '.4195:

G.E. Reload Analysis incorporating LOCA analysis. (5/30/84)

2. Technical Specif3 ation Change Request 119 for Scram Discharge Instrusaut Velame System Modification. (5/15/84)

3. Submittal for SEP Topic "ECCS Actuation" dated 6/4/84.

4. Submittal for maintenance dredging of the Circulating Water Intake Structure dated 6/4/84.

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:

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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'.

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

The number of fuel assemblies (a) in the core i

503

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(b) in the spent fuel storage pool = 1037 l

The present licensed spent ' fuel pool storage capacity and the size of any increase in licensed storage capacity that luus been requested or is planned, in number of fuel assemblies:

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Present:

1,800 Planned:

2,600 The projected date of the last ' refueling that can be discharged to the spent 4

fuel pool assuming the present licensed capacity:

Full core offload capability will be lost af ter the 1985 outage. Batch 4

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discharge capability will be lost af ter the 1987 outage. Expanded spent fuel pool ^ rack capacity (2,600) is scheduled for _1984..

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GPU Nuclear Corporation

'] NggIgf Post Office Box 388 Route 9 South l

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

July 16, 1984 Director Office of Management Information e

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. Drew Holland at (609) 971-4643.

Very truly yours, f$ K s

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Petd B'. Fledler Vice President and Director Oyster Creek PBF: dam 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 Forked River, NJ 08731 A

a-4 GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation

.