ML20091K316

Monthly Operating Rept for Apr 1984

ML20091K316
Person / Time
Site:	Oyster Creek
Issue date:	04/30/1984
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8406070002
Download: ML20091K316 (9)

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JO i M0tfrHLY OPERATIONS-REPORT

' APRIL 1984 Throughout the report period, the Oyster Creek Station remained shutdown for the Maintenance and' Refueling Outage.

Refueling of the reactor -vessel core consnenced on April 15, 1984.

Refueling continued to. April 26, 1984, at which time channeling of thirty-three - fuel assemblies had to be completed.

Channeling of the fuel was completed on April 30, 1984 and refueling of the reactor restarted on May 1, 1984.

At the end of the report period a total of 104 fuel assemblies were loaded in the reactor core (18.5%). During the first half of April channel and clip installation on irradiated and new fuel bundles ' were the major activities in progress on the 119' level.

. Also, recoupling of 74 CRDs was completed. prior to the start of f-refueling the reactor.

i The start of reactor refueling was delayed by a number of problems, the major one being the resolution of a fast start problem with diesel generator No.

1.

The diesel generator experienced governor and relay problems from April 2, 1984 to April 14, 1984. We diesel generator was

- removed from service for testing and troubleshooting a number of times during this period until the fast start problems were corrected.

Testing of Cleanup System valves replaced ancVor repaired during the outage delayed placing the Cleanup System and CRD System in service the

'early part of April.

However, due to the problems encountered during

- this time period with diesel generator No.1, these activities did not delay refueling.

Other; delays encountered were due to SRM operability problems / rod block problems (hydraulic accumulator-switch problems) and manpower restrictions required by the refueling procedures and NRC regulations.

On April 15, 1984, a ' trip of substation breaker S-145 required securing

. the Cleanup and CRD Systems.

' Wis caused a short delay in the resumption of refueling the next morning.

The overhaul of both CRD pumps was completed during the report period.

"B" pung was completed on April 2,1984 and "A" pump on April 30, 1984.

A functional' test of "A" CRD pump is still outstanding.

The cleaning of all hotwells and replacement of the remaining expansion joints on the main condenser were completed during the report period.

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A tube leak in "B"

fuel pool heat exchanger still has not been identified.

The heat exchanger was taken out of service a number of times in an attempt to locate the leak. Each time it was placed back in service, an increase in RBCCW

' urge tank level was noted.

The M&C s

1 Department was still working to identify the leak sourc.e.

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8406070002 040430 PDR ADOCK 05000219 R

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' Monthly Operrtions Report Paga 2 Air coupressor No. 1 was out of service for both corrective and preventive maintenance on three different occasions during the report period (total out of service time approximately 13 days).

Air compressor 1-2 was out of service for a three (3) day period to repair an oil leak.. Air compressor 1-3 was inoperable for a one-day period for instrument calibration.

The prefilter and HEPA filters on Standby Gas Treatment System No. I were replaced.

'Ihe first cask shipment of spent CRD blades left the site on April 3, 1984. The empty cask was returned to the site the weekend of April 21, 1984.

A subsaluent cask shipment is pending the completion of reactor refueling (end of May).

Two cracked cells were discovered in the "B"

station battery system (125VDC). New batteries are on order.

Tne inspection of the isolation condenser piping continued during the report period. A repair scope is being developed by the Tech. Functions Division.

The MSIVs failed leak rate testing and Plant Engineering suspects the inboard valves are being unseated during the test causing the unacceptable results.

In an effort to ~ correct the problem, Plant Engineering is presently developing a method to flood the main steam lines between the inDoard valves and the main steam line plugs.

The leak rate test will be performed after flooding of the main steam lines is completed.

Feedwater string "C"

inlet valve V-2-9 still leaks after being repairect/ rebuilt twice during the outage.

Presently, no additional maintenance can be performed due to the Condensate System being in service (required for refueling).

.Both demineralized water transfer pumps and No. 2 service water pump remained out of service for corrective maintenance at the end of the report period.

The reactor sample line from "B" reactor recirculation loop is plugged.

Plant Engineering is tasked to determine the maximum hydro pressure that can be applied to unplug the line.

To date, all attempts to unplug the line have been unsuccessful.

Testing of major plant power distribution cables was in progress at tne end of the report period.

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Monthly Operttions Report P ga 3

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The following Licensee Event Reports were submitted during April 1984:

i Reportable Occurrence No. 50-219/84-001 On March 2,1984, diesel generator (DG) #2 was started and allowed to run approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for post-maintenance testing.

The DG fuel oil tank level after testing was above the '1%chnical Specification limit of 14,500 gallons.

Early on March 3, 1984, another load test was performed on DG #2 for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The oil tank level by the level gauge was below the Technical Specification limit; however, by visual check inside the tank, the level appeared to De above the Technical Specification limit.

On the next shift the level was checked again and found to be below the Technical Specification limit.

Tne apparent cause of the occurrence is attributed to operator error for not sufficiently following-up on the low level indication.

The imediate corrective action was to transfer oil to the tank to bring the level above the Tecnnical Specification limit.

Future solutions to be evaluated include the following:

1)

Utilize a level instrument which is not sensitive to changes in specific gravity, or one which compensates for changes in specific gravity.

2)

Reduce the Technical Specifications limit to a value which i

i does not compromise the design basis capacity, yet which allows more operational flexibility than there is at present.

3)

Replace the existing tank with a larger tank.

4)

Instruct operators to transfer oil as required by the indication on the level gauge.

l Reportable Occurrence No. 50-219/84-002 i

l On March 2, 1984, the unit sub-station (USS) circuit breaker to Motor Control Center (MCC) 1B32 failed to trip when the undervoltage (W) device was de-energized.

Again, on March 7, 1984, the circuit breakers to the shutdown cooling pump (SDC) NUO2B and the building l

exhaust fan EF-1-6 failed to trip within the specified time limit in the l

procedure when their W devices were de-energized.

%ese events in l

themselves are not considered to be reportable, but were reported under 10 CFR 50.73 as they may be an indication of a potential generic problem.

The cause of occurrence on the MCC 1832 circuit breaker was attributed to hign torque on the trip shaft bearings due to hardened lubricant.

The cause of occurrence on the SDC pump NUO2B and EF-1-6 circuit breakers was attributed to instrument drift of the static time i

delay W tripping device.

Se immediate corrective action was to i

perform preventive maintenance on the circuit breakers.

The circuit i

breakers were tested for operability three (3) times and were returned l

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Monthly Operations Report Pag 2 4 i

to service.

Tne longer term corrective actions are the same as those listed in GPU Nuclear's response to IE Bulletin 83-08, namely, PM procedure revision, investigation into modifying the control circuits,

and more frequent checks of the W trip mechanisms.

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.e DOCKETNO.

50-219 UNITSHUTDOWlO AND FOWER REDUCTIONS UNIT NAME Ovster cran}c DATE 5-2-84 COMPLETED BY R.

Baran REPORT MONTII April 1984 TELEPHONE 971-4640 "L

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licensee Ev.,

c Cause & Corrective No.

Date g;

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Event gg E.3 Action to H

$5 ri jdi Report #

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Prevent Recurrence o

l 31 2-11-83 S

10656 C

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

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l F: Forced Reason:

Method:

Exhibit G-Instructions S. Scheduled A-Equipment Failure (Explain)

1. Manual for Preparation of Data B-M2intenance of Test 2-Manual Scram.

Entry Sheets for Licensee C. Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other(Explain) 0161)

E-Operator Tra :ing & License Examination F-Administrative S

G-Operational Errur (Explain)

Exhibit I-Same Source 19f77)

II-Other (Explain) i

OPERATING DATA REPORT

• OPERATING STATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD:

April, 1984 3.

lffILI"' CONTACT:

JOSEPH R. h0LNAR 609-971-4699 4.

LICENSED THERMAL POWER (MWt):

1930 5.

NAMEPLATE RATING (GROSS FMe):

687.5 X 0.8 = 550 6.

DESIGN ELECTRICAL RATING (NIif FMe):

650 7.

MAXIMlN DEPENDABLE CAPACITY (GROSS MWe):

650 8.

MAXIMLN DEPENDABLE CAPACITY (NET MWe):

620 9.

IF CilANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

NONE 10.

POWER LFXEL 'ID WilICil RES'illICTED, IF ANY (h2T hMe): N/A 11.

REASON FOR RESTRICTION, IF ANY: NONE h0NTil YEAR CUMULATIVE 12.

REPORT PERIOD 1RS 720.0 2904.0 125832.0 13.

10URS RX CRITICAL 0.0 0.0 84623.9 14.

RX RESERVE SIITIMN llRS 0.0 0.0 468.2 15.

IRS GENERA'IUR ON-LINE 0.0 0.0 82693.8 16.

UT RESERVE SilTIMN liRS 0.0 0.0 0.0 17.

GROSS 'IllDIM ENB1 (hM1) 0.0 0.0 136224729 18.

GROSS ELEC ENER (hWil) 0.0 0'. 0 46056905 19.

NET ELEC ENIR (hWI)

-1900

-7616 44278067 20.

UT SERVICE FACTOR 0.0 0.0 65.7 21.

UT AVAIL FACTOR 0.0 0.0 65.7 22.

Lif CAP FAC'IDR (MIX: NET) 0.0

-0.4 56.8 23.

UT CAP FAC1DR (DER N!?f) 0.0

-0.4 54.1 24.

Lif IDRCED OlffAGE RATE 0.0 0.0 9.7 25.

FORCED OlffAGE IRS 0.0 0.0 8916.8 26.

SIUIDOWN3 SCllEDtiLED OVER NEXT 6 bONTilS (TYPE, DATE, DURATION): N/A 27.

IF CURRENTLY SilUTDOWN ESTIMATED STARTilP TIME:

6/11/84

AVERAGE DAILY POWER LEVEL NET MWe DOCKET #........ 50-219 UNIT.......... 0yster Creek #1 REPORT DATE.......MAY 03, 1984 Q)MPILED BY....... DONALD V. NUTIGAN TELEPHONE #...... 609-971-4695 htXfDI APRIL, 1984 IRY g

DAY g

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10.

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0 11.

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,o-Oyster Creek Staticn #1 Docket No. 50-219 REFUELING INFORMATION - April, 1984 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:

Presently shutdown for Refueling Scheduled date for restart following refueling: June 11, 1984 Will refueling or resumption of operation thereafter 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-24195: G.E. Reload Analysis incorporating LOCA 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 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.

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

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150 The number of fuel assemblies (a) in the core (b) in the spent fuel storage pool - 1313 The present Ilcensed 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 assemblies:

Present:

1,300 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.

O

.o GPU Nxlear Corporation NggIgf Post Office Box 388 Route 9 South Forked R:/er.New Jersey 087310388 609 971-4000 Writer's Direct Dial Number:

May 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 tio. 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 shculd have any questions, please contact Mr. Drew Holland at (609) 971-4643.

Very truly youro, fg

^

O Peter b. Fiedler Vice President and Director Oyster Creek PBF: dam Enclosuren cc: Director (10)

Office of Inspection and enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. ThorMS 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, IU 08731 Q,M GPU Nodear Corporahon is a '.utm!'ary of the General Pot >he Utihties Corporation