ML20092M668

Monthly Operating Rept for May 1984

ML20092M668
Person / Time
Site:	Oyster Creek
Issue date:	05/31/1984
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8407020343
Download: ML20092M668 (10)

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i MONTHLY OPERATIONS REPORT MAY 1984 I

Throughout the report period, the Oyster Creek Station remained shutdown for the Maintenance' and Refueling Outage.

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Channeling of the reactor fuel was completed on May 1,

1984 with f

refueling - of the' reactor restarting late the same day.

Refueling continued until May 13, 1984 at which time a black and white pattern was i

reached and refueling was stopped to install channel clips on 77 new fuel assemblies.

Refueling of the. reactor recomenced and was completed l

on May 22,1984 except for those fuel assemblies (62) which were not loaded into the core to support SRM/IRM dry tube replacement.

Various

' delays in the l refueling process were experienced during. the report period.

They consisted of:

nuclear instrumentation problems (SRH23),

failure of "B" Control Rod Drive (CRD) pump (oil cooler leak), IRM range i

switch relay failure, rod block problems with the bridge track switch and CRD hydraulic control units; and problems with the Refuel Bridge j

communication system.

Some time was also spent removing debris from the t

? reactor.

At the end of the report period, fuel moves were in progress

~ to support LPRM replacement.

There is a total of five (5) LPRMs left to be replaced.

At the end of the report period, preparation was in progress to replace l

all. IRM/SRM dry tubes.. This task has been contracted out to General Electric Company. Work is expected to start the first week in June.

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' On May 28, Emergency Diesel Generator No. 2 was declared - inoperable after it failed to start during routine testing.

The problem was traced to; the actuator ' on the Diesel Generator governor.

The governor replacement.was in progress.~ at' the end of the ' report period.

Standby l

Gas Treatment System No. 2 is also considered - out of service due to Diesel Generator No. 2 being inoperable.

i CRD pump "A" was returned to an operable status on May 16, 1984 after an overhaul and corrective maintenance was performed on it due to an oil leak and failed thrust bearing.

Corrective maintenance on "B" CRD pump was also performed due to an oil cooler leak.. Maintenance on "B"

CRD pump'-caused some delays in the refueling activities as mentioned above since "A" pump was already out of service.

Fire diesel pump No. 2 was out of service from May 15,1984 to May 21, 1984 to. repair a leakL in its cooling system radiator.

An oil leak on fire diesel pump No.1 was also repaired during the report period.

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. Air compressor No, I was out of service three ' times during the report

. period for oil leaks, -interstage relief valve problems and instrument calibrations.

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,' Monthly Operations Rtport Page 2 "A" condensate pump was returned to an operable status and realignment of the condensate pump suction header was completed.

Replacement of the expansion joints on the suction of the condensate pumps is currently in progress.

"B" pump has been completed.while work on "A"

and "C"

pumps I

continues.

The plant is experiencing problems isolating the "A" and "C" pumps.

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Alignment and calibration of the turbine control system continued during the report period.

Approximately 2000 gallons of lube oil was added to i

the turbine lube oil tank.

No. I and 3 turbine oil lift pumps were replaced.

The overhaul of 1-3 dilution pump was completed.

At the end of the i

report period, a 24-hour test run of the pump remained to be perfomed.

I This test run was started on June 1 and June 2,1984 at which time the i

pump tripped on low seal water fl ow.

The trip problem is being l

investigated.

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i No. leaks could be found in either of -the fuel pool heat exchangers as testing continued to identify the source of the suspected tube leak.

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Both heat exchangers were isolated and inspected for leaks a number of i

times.

The system is presently being monitored while the Maintenance j

and Operations Departments - discuss other possible methods that may be i

used to identify the source of the leak.

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Service water. pump No. 2 discharge bell was weld repaired, and upon placing the pump back in service, a small leak was noted.

New discharge bells. arrived on site for both pumps at the end of the' report period.

l The new pump bells will be installed in the near future.

i' Weld repair of Reactor Building Closed Cooling Water (RBCCW) heat exchanger-1-1 was in progress at the end of the report period.

i Installation of the nitrogen layup system for the feedwater heaters was completed.

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Cask shipments of CRD blades continued during the report period.

On i

June 3,1984, the third cask left the site.

The NRC annual plant emergency drill was held on' May 10, 1984.

The subsequent critique identified a number of items that will ba addressed. -0verall, performance for the drill was satisfactory.

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- Torus paint heat curing started on May 17, 1984 but had to be secured on May 19 due to the inability of the heat cure system to maintain proper differential temperatures between the torus shell and columns.

t Additional heat. trace equipment was installed and heat curing of the torus restarted on June 1,1984.

l Testing of the ~ plant's electrical distribution system in the Turbine f

1 Building continued during the report period.

A defined repair scope is ir the process of being developed by Plant Engineering.

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,' Monthly' 0perations Report Page 3 New "HFA" relays are expected to arrive on site some time in June.

The existing reles which were replaced earlier in the outage are suspect i

due to an oil leaching problem.

Repairs and analysis of the isolation condenser piping continued during

. the report period.

t Repairs to the drywell cooling system continued during the report period.

New cages and fan shafts need to be installed.

The fans were rebuilt earlier in the outage but their condition has deteriorated to

- the extent that extensive.repai rs are again required.

Technical Functions is investigating the reason for.the premature degradation.

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'. Mo'nthly Operations Report Page 4 The following Licensee Event Reports were submitted during May 1984:

Licensee Event Report No. 50-219/84-004 On April 21, 1984, a contractor found that both the inner and outer doors of the 23'6" elevation airlock of the reactor building were open at the same time.

This is in violation of the Technical Specifications, which require that at;least one airlock door be closed at all times to maintain secondary. containment integrity.

The doors were closed immediately after they were found open to restore secondary containment integrity.

The apparent cause of occurrence is attributed to either improper or unauthorized use of the electro-mechanical interlock override switch or to the simultaneous opening of both doors which l

results in both doors being held open.

Corrective actions include an increased emphasis, through training and procedures, on the importance of maintaining at least one airlock door closed at all times.

l Licensee Event Report No. 50-219/84-005 l

t The shell side of both Isolation Condensers (NE01-A, NE01-B) was hydrolazed and coated to protect against corrosion.

As part of i

post-maintenance

testing, the tube side of the condensers was hydrostatically tesced to verify tube integrity.

On March 22, 1984, during the hydro test on Isolation Condenser NE01-A, a leak was noticed near an insulated elbow on the condensate piping, downstream of the condenser.

The insulation was removed and the wel d was examined ultrasonically, which pinpointed the existence of a through wall crack approximately 5 inctes long.

The indications are that the failure may be attributed to Intergranular Stress Corrosion Cracking.

j The entire Isolation Condenser System is being inspected to determine the integrity of the remaining weld joints.

Only then can a l

program be developed to fomulate the corrective action required.

Licensing Event Report 50-219/84-006 As a result of blast clearing Torus structure components during the 1983 refueling / maintenance outage, areas of corrosion pitting were i

uncovered, evaluated and repaired where necessary.

In addition, missing fillet welds on two (2) of twenty (20) ring girders were found, as were missing fillet welds on ring girder flange to web reinforcing plates.

All missing welds were repaired.

The detennination of the repairs required, and the performance of the repairs, were in compliance with i

ASME Code Requirements, and all other applicable requirements including Mark I Containment Program requirements.

This report was considered a i

voluntary report.

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Monthly Operaticns Report Page 5 i

i Licensee Event Report No. 50-219/84-007 On April 2,

1984, Diesel Generator No. 1 (DG-1) was declared I

inoperable. as a result of a ' failure to fast start during a monthly surveillance.

Since DG-1 is the emergency power supply for Standby Gas Treatment System No.1 (SGTS-1), SGTS-1 was also declared inoperable.

Technical' Specifications require that the redundant SGTS train be i

demonstrated, operable within two (2) hours.

SGTS-2 was not tested, however, until the completion of a ten (10) hour wait period that was i

necessary to prevent degradation of the filter trains from the fumes from painting work in the torus.

Torus painting was stopped when the e

requirement to test SGTS-2 was established, and SGTS-2 was tested after the ten -(10) hour wait period.

A change to the Technical. Specifications will be investigated to detennine whether the restrictive requirements regarding normal and emergency power supplies (in the Shutdown and Refuel modes) can be eased or clarified.

The procedural requirement to r

wait ten (10) hours prior to operating a SGTS train for testing, after

. termination of painting activities, will be changed when a test is

. required to comply with an LCO.

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i UNITSIIUIDOWNS AND FOWER REDUCTIONS -

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- -DATE 6-4-84

!REPORTMONTIg May 19 84 -

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$3 "g ~-

Y3 Licensee Eg gg Cause & Corrective No.

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p,cvent Recurrence 6

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11400 C

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

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F: Fcrced Reasen:

Method:

Exhibit G -le.structions S: ScheduleJ A-Equipment Failure (Explain) 14fanu:1 for Preparation of Data i

B-Maintenance ciTest 2-Manual Scram.

Entry Sheets fer licensee C. Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regehrery Restric: ion 4-Other(Explain) 0161)

E-OperatorTraining& Ucense Examinatier F-Administrative -

5 Goperatiena! Error (Explain)

Exhibit 1 -S::ne Source (9f77)-

!!-Orher (Exp!ain)

OPERATING DATA REPORT OPERATING STATUS l.

DOCKET:

50-219 2.

REPORTING PERIOD:

hhy, 1984 3.

[TTILITY CONTACT:

JOSEPH R. MOLNAR 609-971-4699 4.

LICENSED THERMAL POWER (MWt):

1930 5.

NAMEPLATE RATING (GROSS MWe):

687.5 X 0.8 = 550 i

6.

DESIGN ELECTRICAL RATING (NET MWe):

650 l

7.

MAXIMLN DEPENDABLE CAPACITY (GROSS MWe):

650 8.

MAXIMIN DEPENDABLE CAPACITY (NET MWe):

620 9.

IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

NONE 10.

POWER LEVEL TO WHICH RESTRILTED, -IF ANY (NET MWe): N/A 11.

REASON FOR RES'IRICTION, IF ANY: NONE

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MONE YEAR CUMULATIVE 12.

REPORT PERIOD 1RS 744.0 3648.0 126576.0 13.

10URS RX CRITICAL 0.0 0.0 84623.9 1

14..

RX RESERVE SHTDWN 1RS 0.0 0.0 468.2 15.

IRS GENERA'IUR ON-LINE

-0.0 0.0 82693.8 16.

UT RESERVE SHTDWN FRS 0.0 0.0 0.0 17.

2 0SS EERM ENER (MWH) 0.0 0.0 136224729

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20SS ELEC ENER (bMH) 0.0 0.0 46056905 19.

NET ELEC ENER.(MWH)

-2116

-9732 44275951 20.

UT SERVICE FAC'iDR 0.0 -

0.0 65.3 21.

-UT AVAIL FACTOR 0.0 0.0 65.3 22.

UT CAP FACTOR (MDC NET) 0.0

-0.4 56.4 23.

UT CAP. FACTOR (DER NET) 0.0

-0.4 53.8

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UT IORCED OITTAGE RATE 0.0 0.0 9.7 25.

FORCED OITTAGE IRS-0.0 0.0 8916.8 26.

SIIIIDOWNS SCHEDULED OVER NEXT 6 MONT16 (TYPE, DATE, DURATION): N/A 27.

IF CURRENTLY SIUTDOWN ESTIMATED STARTUP TIME:

8/07/84

.L AVERAGE DAILY POWIR LEVEL NET MWe DOCKET #..........50-219

. UNIT..........

0yster Creek #1 REPORT DATE....... JUNE 04, 1984 COMPILED BY....... DONALD V. NUTIGAN

- TELEPHONE #.......609-971-4695 MON 111 MAY,1984 DAY W

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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - May, 1984 Name of Facility: Oyster Creek Station #1

' Schedul'ed.date for next refueling shutdown: Presently shutdown for Refueling Scheduled date for restart following refueling:

8/07/84

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

r NONE Scheduled date(s) for submitting proposed licensing action and supporting

-information:

1. Amemdment #7 to NED0-24195:

G.E. Reload Analysis incorporating IDCA analysis.:(5/30/84)'

2.' Technical Specification Change Request 119 for Scram Discharge Instrument Volume System Modification. (5/15/84)

~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:

1. General ElectricL Fuel Assemblies -- fuel design and performance y 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

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there any anticipated.

1he ntsnber of fuel assemblies (a) in th'e core 492

=

(b) in the spent fuel storage pool = 1049

' 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, Lin' 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 fuel pool assuming the present licensed capacity:

- Full core offload capability will be ' lost after the 1985 outage. Batch discharge capability will be lost after the 1987 outage.

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

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GPU Nuclear Corporation NUCI88r

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

June 14, 1984 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 infonnation) 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, Peter B. Fiedler Vice President and Director Oyster Creek PBF: dam Enclosures cc: Director (10)

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

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 I*M Oyster Creek Nuclear Generating Station Forked River, NJ 08731 l

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

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