ML20115C612

Monthly Operating Rept for Feb 1985

ML20115C612
Person / Time
Site:	Oyster Creek
Issue date:	02/28/1985
From:	Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8504180480
Download: ML20115C612 (13)

Text

e '

g

.c .

- MON 111LY OPERATIONS REPORT-February 1985

At the beginning of the report period,~0yster Creek Station was in the process

= of shutting down to correct a potential design deficiency in the core spray booster pump logic. Subsequent to completion of the logic modification to the core spray systems, four (4) different startups and four (4) additional

. shutdowns- have occurred. Three (3) startups/ shutdowns. were due to Electromatic. -Relief Valve (EMRV) problems, and one (1) was caused by an automatic reactor scram.

As :previously ' reported, Technical Functions Division identified a potential design deficiency with respect to inputs to the core spray booster pump logic. . Pressure sensors (RV-40s) located at the discharge of the core spray booster pumps (CSBPs) are provided to insure sufficient discharge pressure-is established.- If sufficient discharge pressure (230 psig) is not established within five seconds after a CSBP start signal is received, the start signal to

.the primary CSBP (NZ03A/NZ03B) is automatically terminated and a start signal 2

to the backup CSBP (NZO3C/NZ03D) is initiated. Tech Functions calculated that

, during an event with . rapid depressurization (A.D.S. initiation), CSBP discharge pressure degrades to the point that a logic trip occurs. In order to resolve the concern, new differential pressure switches . were installed across the - core spray booster ptmps. The modification required a reactor shutdown.

Power ~ reduction commenced at 9:42 p.m. on February 1 and the generator was taken off line at 4:17 a.m. on February 2. During shutdown, stroke testing of the Main Steam -Isolation Valves- (MSIVs) was performed. Valve NS03A closure time did not meet _ acceptance criteria and was declared inoperable.

Subsequently, the' decision was made to isolate the main steam line and manually scram the reactor. A manual scram was initiated at 8:00 a.m.

inserting all ' control rods. The reactor was cooled to below 212 F by 2:51 -

p.m. on February 2.

During the ' process of shutting down, "B" feedwater regulating valve was observed to be not tracking with the power decrease. The valve was pinned so that it could be manually operated. With the valve pinned, a step decrease in flow occurred. Following shutdown, an inspection of "B" feedwater regulating valve.(FRV) revealed that the upper and lower poppets were split. Replacement parts were installed. The problem was attributed to material failure.

Inspection of "A" 6 "C" FRVs was not performed.

Initial drywell inspection, performed at pressure, identified a leak on feedwater isolation valve (V-2-36) as the major contributor to drywell unidentified leak rate. Misalignment of the valve bonnet was the cause of the leak. Repairs included bonnet alignment and sealant injection.

Another contributor to the . unidentified drywell leak rate was "D" EMRV (flange gasket leak).

During plant shutdown, a Fire Protection System leak developed as a result of a valve body crack on post indicating valve V-9-13. This valve was replaced after both Core Spray Systems were returned to operable status. The fire system is required to be operable as part of the core spray reduced availability criteria.

$Y 8504180480 850228 "J PDR R ADOCK 05000219 l PDRa

7 7..

• Montlily Operstitns R: port 'Pags 2 A ntnber of cleanup system valve problems were encountered during the plant shutdown. While in the process of unbackseating V-16-1 (system inlet valve),

the Cleanup System tripped. Additionally, valve V-16-14 (auxiliary pump g bypass) did not fully close electrically and had to be closed manually. Valve V-16-2 (auxiliary pump , suction) and V-16-60 (letdown valve to the Condensate System) both tripped a number of times while attempting to open to restart the Cleanup System. Tests and inspections performed on the cleanup system valves revealed no problems, with the exception of V-16-14. Inspection of V-16-14 revealed slight scoring on the stem resulting from inadequate stem-lantern ring clearance. Conditions were corrected by filing the lantern ring to achieve adequate clearanc'e; the stem was " stoned" smooth. Additionally, tests were performed to ensure that closure thrust was equal to or better than that recorded at the time of the last Appendix J 1eak rate test. Thrust criteria was satisfied, negating a need for a leak rate test.

During plant shutdown, problems were experienced with two (2) IRMs. IRM 18 IRM 14 experienced drive was giving a downscale alarm in all ranges.

problems. Both IRMs were repaired.

In addition to the problems identified during plant shutdown, a large number of other work activities were completed. Major jobs / tasks completed while shutdown include:

1. Repairs to steam system leaks identified since the plant has been running (i.e., flash tank manway, steam traps, valves,etc.)

2. Repairs to feedwater string "B" minimum flow valve and outlet isolation valve V-2-11 (flange leaks).

3. Accumulator and valve . repairs to nine (9) CRD hydraulic control units.

4. Thermocouple repairs on recirculation loops "A" and "C".

5. Checks for nitrogen inerting/ makeup system leaks. A number of leaks were identified and repaired.

6. Repair to torus /drywell vacuum breaker V-26-5. Repairs were completed and the valve tested satisfactorily.

7. Environmental qualification inspections and repairs were performed as required.

8. Various instrumentation (recorder) related repairs for problems determined to be in the drywell.

. 9. Reactor Protection System No. 1 motor generator set was returned to service after bearing replacement.

10. A position switch problem on No. 4 circulating water pump discharge valve was resolved.

11. The brushes on' all the reactor recirculation pump motor generator sets were replaced. The collector rings on "B" motor generator set were burnished.

k. p

• Monthly Operr,tions Report ,

-Pags 3

12. Position indication probe problems with CRD 30-23 and 30-15 identified'during shutdown, were also repaired.

13. ~All .MSIVs were adjusted to proper stroke times. A logic relay for MSIV NS03B was also replaced after failure.

14 .- Condensate return line high flow -isolation switch on "B" l isolation ; condenser was replaced after. the system failed surveillance testing.

15. Emergency - Service Water (ESW) pump 52A failed its operability test on low discharge pressure. After blowing down the suction side, the pump passed the surveillance test.

16. The seal on "B" fuel pool cooling pump was replaced after it failed.

17. . Coating and cleaning of.1-2 TBCCW heat exchanger water box was completed.

"An' operability problem occurred with isolation condenser valve V-14-35.

MDVATS - testing did not reveal any problems with _ the valve at this time.

Thermal expansion ' caused . the valve disk and seat to bind in the closed position. The . valve was satisfactorily retested and declared operable. It should be noted, however, that later in the report period, additional problems were encountered with this valve.

Standby Gas Treatment System (SGTS) No. 2 was temporarily declared inoperable ,

on February 10 after the system flow switch stuck causing the purge valve to remain open. IGC technicians exercised the switch ' a number of times and checked the calibration, which was found to be within specifications. No. 2 SGTS retested satisfactorily.

While surveillance testing IRM -15 (half scram in) on February 13, 1985, a spike in IRM 14' caused a full scram. As a result, the scram discharge volume surveillance test had to be performed again.

All_ required maintenance activities and testing were completed and a reactor startup was commenced at 6:21 a.m. on February 14. The reactor was critical at 9:50 a.m. ' During startup, and after placing a feedwater pump 'in service,

'drywell unidentified leak rate increased to 2 gpm. The reactor was brought subcritical to facilitate drywell inspection' (reactor pressure approximately 475' psig). Drywell inspection identified significant leakage from V-2-36 and "A" ISRV inlet flange. Additional sealant injection at pressure significantly reduced the leakage from V-2-36. Plant startup was terminated on the morning of February 15, and the plant was again shut- down to facilitate repairs to items' identified during startup and shutdown. All control rods were inserted by 5:19 a.m. and the reactor was in cold shutdown (less than 212' F) by 7:00 a.m.

E_ J

w ..

. - ,3. .

• Monthly;0perstions Page 4 Prior to shutting down,l repairs'due to spiking problems.were completed on-IRM e .

18.c.During shutdown,)IRM 16 was drifting and had to be bypassed.

a . Position ' indication problems. onf CRDs: 30-23' and 30-151 were identified' during startup on Februaryzl4 and repaired after shutdown on February 15.

T, /An, oil-leak on "C" reactor feedwater! pap:(RFP) was' identified and repaired.

~

,t, _. . .- -

m .Whil_elthe' plant was shutdown, the torus water level was lowered to ensure the

' level would remain 1within the. allowable operating ~ band during MV . testing

~ :after maintenance. ,

~

' Due?to: .theileakage . from V-2-36, four snubbers in the : area -of the valve

required' testing. Two of,the snubbers required replacement.

During1 startup and1 subsequent ~hutdown, s the - mechanical vacuum. pmp tripped numerous.. times. This presents a continuing -operational problem and is being

investigated. by- Plant Engineering. The plant .also experienced spiking problems with -IRM 13 and IRM 16. Troubleshooting continued at the end of the

report period.

The solenoid . for. air-operated valve V-24-35 (1-7 sump isolation valve) was

, replaced ~after the. valve failed its associated operability test.

The XA relay (panel 11R) for the Reactor, Building ventilation isolation logic ~

failed and had to be replaced. This necessitated operation of Standb> ss Treatment System (SGTS) while repairs were being effected.

' Repairs to "A" MV and IRM 16 were completed, and reactor startup comenc.ed-on : February 17 at 12:23 p.m. The re~ actor was critical :at 2:35 p.m. and reactor heatup commenced. With pressure at 500 psig, the reactor was brought'

subcritical as required to inspect the 'drywell. The inspection revealed that "C" MV was leaking significantly at the flange. Feedwater valve V-2-36 was

=stil1~ leaking slightly. Due to "C" M V leak, the reactor was shutdown again comencing' at 9:15 p.m. on February 17. A11~ control rods were inserted by 11:00 p.m. and the reactor- was in a cold shutdown condition by 1:40 a.m.. on

~

' February 18.

- A decision was made to replace the gaskets on all five (5) MVs. The M V leakage problem was caused by a combination of the following:

1. .the amount of compression or crush being put on the gasket.

2.. -pitting of the steam line flange.

To correct the pitting problem, a sealant was used on the flange seating surfaces. In addition, 0.175" thick gaskets were used instead of the existing 0;125" gaskets and provided increased compression on the gasket when torqued.

Due to stackup. problems encountered during reassembly, a 0.125" gasket had to be installed on "D" and "E" MVs. The seating surface on "B" MV required machining due to excessive pitting. All EMRVs were subsequently reassembled, however, . "B" MV solenoid would not stroke. Troubleshooting identified a broken shorting bar which was subsequently replaced. Acoustic monitors in the area of "B" MV were installed and tested after -its solenoid was repaired.

[M

y ,

~

f' Montfily Operations Report- Page 5

"' L During s startup :and subsequent . shutdown;on February 17, the plant experienced-

! spiking problems with IRM-13 and IRM 16. . Troubleshooting of IRM 13 and~IRM 16-

did not; identify any problems. The_ spiking- problem mainly occurred when the IRMs were . ranged from 6 to 7; therefore, the IRMs were considered operable.-

This problem has - also . been identified at . cther nuclear facilities.

Engineering and M6C are evaluating.

During the shutdown, . vibratiorJ data were .taken on two drywell recirculation -

fans.- LThe . data revealed vibration-had increased significantly since the fans -

~

lwere balanced in 1 July, -1984. . This prompted 'an inspection of all drywell

. fans. All of1the fans required rebalancing. The bearing support assemblies on fans No. 2 and 3 required extensive repairs. All repairs and testing were completed on February 22.

Deepwell -pump "A", which supplies the domestic water system, failed on February 18,~1985 and has been replaced with a new p mp.

{

Air = compressor No. 2 unloading solenoid was replaced; however, upon testing a relief valve problem developed. < Air compressor No. 2 remained out of service for relief valve repairs at the end of the report period.

Environmental Qualification ~ repairs (Raychem-splices) are in progress on the Core Spray System suction valves and two Containment Spray System-valves.

w The ' collector rings on reactor recirculation pep MG set "C" were burnished and the unit returned to service.

. AllJ repairs and surveillances required for plant' startup were completed on

-- February 1 23. Reactor startup commenced at 12:45 p.m. The reactor was

> critical-at 2:15 p.m. and heatup continued. An initial drywell inspection was completedi-late .in the' day on February 23 at a reactor pressure ~ of

.- approximately - 500 psig. Minor leakage from feedwater valve V-2-36 and three CRD' flanges was noted. The. drywell was closed and reactor pressure was increased - for . the. 1000 psig.~ Einspection. .While increasing pressure,

, calibration problems with IRMs 11 and 15' were encountered; the IEis were

. bypassed.'-Prior to'drywell' inspection at 1000 psig,-all: M Vs were tested.

"A'? and I "E" MVs were tested and reseated properly. "B" EMRV had to be

. recycled to'get,it to reseat. "C" MV 'did not reseat after seven recycles.

-"D" M V-reseated.after.three recycles .

During the second attempt to reseat "D" MV, the valve remained open' enough to cause the associated acoustic monitor to go to full scale.

A drywell inspection was performed at a reactor pressure of approximately 1000 p- MV. was recycled following at which ; time "C" MV wasthe verified to beand inspection leaking (through reseated. No the seat flange lea{s.

>.were observed at that' time.

l M

b -

o

p. j .. ~

l l

4~1 t , Monthly.Operctions Raport' P2gs6'

.. u, .,

I L v < .

, 1 After the first drywell inspection at pressure, reactor power was increased 'to - l "approximately E23% ' t'o -calibrate the feedwater regulating valves (FRVs) and to '

scram itestE a number of - CRDs. . Power was being reduced after CRD' testing to

'injectE scalant : into feedwater valve V-2-36, : if required, when a reactor low

.leveloscram' occurred.

.. . . .. t

' Reactor feed' pump (RFP) "C" was in service.with level being controlled by "C"

- string feedwater regulating valve f (FRV) in the "AUT0" mode. The FRV position

. indicator and the total feedwater flow ' recorder in the Control Room were not-

' indicating properly. : When ~ #1 turbine bypass valve - was halfway closed, the

~

< operator took manual control.of the FRV.. Due to high rodworth of the' control rods .being used ' to lower power, a high cooldown t rate resulted. Rods were d , " withdrawn 'again-in order to stop- the cooldown and ~ to try and maintain reactor

< pressure;at approximately 1000'psig. It should be noted that. steam seals and '

i the'SJAEs were in' service adding to the cooldown rate. Due to the collapse of' '

, voids from the closure of the bypass , valves, introduction of m' ore cold feedwater, and -' group control rod movement, control room . operators were not-able ito stabilize reactor water level and power. -Because of the effects on I

. reactivity 'by cold ~ feed water addition, the CR0 became 'over cautious- in manually feeding and. allowed the low level scram setpoint to be reached and a

' reactor scram' occurred. Water- level and control of cool down were subsequently restored -and the transient terminated. A post trip critique was completed.

Mechanical vacuum pump trips were encountered again as during the previous startup. Additionally, a significant seal leak developed. The vacuum pump is being repaired and the tripping problem being evaluated. '

' FRV position -indication and total feedwater flow recorder (calibration) were repaired in preparation - for startup. "C" FRV stroke time has been adjusted.

The minimum flow valves on all 'three feedwater strings were calibrated to 'open at proper flow rates.

Reactor startup commenced at 3:45 a.m. on February 25. The reactor was critical : at 9:34 a.m. -At approximately 1000 psig, the . reactor was brought

_ subcritical for drywell inspection.

' Inspection revealed that the "A" and "C" EMRV flanges were -leaking U

significantly. A reactor shutdown commenced at 8:25 p.m. the same day. The f shutdown process was secured for approximately three hours to accommodate sealant ~ injection on feedwater valve V-2-36. Reactor shutdown(all rods inserted) was completed at 2:15 a.m. on February 26. Cold shutdown was achieved at 3:44'a.m. A decision was made to remove.the "A", "C", "D" and "E" EMRVs to machine the steam line pipe flanges. Seats on "C" and "D" EMRVs'were p - also scheduled to be inspected and repaired as necessary.

L In parallel with 'EMRV repairs, a containment device was installed for valve

! ~ V-2-36. The containment' is designed to divert any leakage from the valve to k . the DWEDT (identified leakage).

l l

• 3 ,-

J

'+ -

-m b e, , -r.rm m, 4~~,,,...,4.., yr-.,,,,',-w,, -.,,,-....m,m_,,,v.w-,---,. ,..~-w-,,.-.,,,,,..,+..m,.-<,..y . . .

n-  ;.,

' Monthly' Operations Report P gn 7 During startup on February . 25,' IRMs 16 and 17 were again spiking. IRM 13 experienced range correlation problems. As previously noted, _these concerns

.are being addressed by M6C and Plant Engineering.

Another problem 'noted while the reactor was at pressure, was the increasing 1shell temperature of "B" isolation condenser. A problem was suspected with the condensate return valve V-14-35. On February 27, while checking the stroke / current characteristics (MOVATS) of V-14-35, the valve motor failed.

~

The cause has.not yet been determined. A new valve-motor was installed prior to startup.

A seal on No.1 Reactor Building Closed Cooling-Water (RBCCW) pump failed and was' subsequently repaired.

Collector rings on No's.. 2 and 3 circulating water pumps required machining / burnishing prior to startup. The work was performed after "C" and "D" EMRV flanges were machined.

Environmental -Qualification work on various containment spray system motor

. operated valves continued after the shutdc.m on February 25 and 26.

Substation power line J6931 tripped on February 26, due to two seagulls landing on two different phase lines. Lighting in various parts of the plant, including the drywell, was temporarily lost. This prompted the installation of DC lights in the drywell.

Repairs to building heating systems continued during the report period, as

. conditions and manpower permitted. The package boiler was secured .for a few days to permit repairs to equipment that can't be isolated with the boiler in service.

The chlorine dioxide modification started during the report period.

Subsequent to the . report period (March 4, 1985) a reactor startup was completed and successful test of.EMRVs "A", "C", "D", and "E" conducted.

I 1570W' L

m Monthly' Operating R: port' Pags 8 The ffollowing Licensee Event Reports were submitted during the month of February 1985:

Licensee Event Report 50-219/85-001 -

During the monthly test of the Reactor Low-Low-Low Water Level sensors, one of the sensors remained out of service for: a period greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 minutes).

This exceeds- the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit requirement in the Technical Specifications.

The cause was attributed to personnel error, and this limit was not identified in the surveillance procedure. The requirement was re-emphasized to responsible personnel and the applicable _ administrative controls will be revised as appropriate.-

Licensee ' Event Report 50-219/85-003 - On 1/29/85, a design deficiency was discovered in the Core Spray System booster pump failure logic. Two events were identified 'which can cause this instrumentation to misinterpret Core Spray System status and result in the system not performing according to its original design intent. The cause of this occurrence is a deficiency in the original plant t design. Corrective action consisted of performing a modification to. replace the pressure switches on the booster pump discharge with differential pressure switches..

Y '

.__. ._ _ . _ _ . . . . - _ - - _ . _ . _ . _ . . . . . - - - - - . - ~ ~ -

97 Ljn

~

CPERATING DATA REPORT OPERATING STATUS

'T -1. DOCKET:. '50 -219 :

2. REPORTING' PERIOD * . February 1985'

'3.- UrILITY CONTACT: . JOSEPH R. MOLNAR 609-971-4699 4.: LICENSED THERMAL POWER ( Wt): 1930 l

'5.- NAMEPLATE RATING (GROSS ~We): 687.5 X 0.8 = 550 L6. DESIGN ELECTRICAL RATING'(NET MWe): 650

17. . hAXIMUM DEPENDABLE CAPACITY (GROSS We): 650 8.. . MAXIMUM DEPENDABLE CAPACITY (NET MWe): _620

. 9 . __ IP' CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS: NONE L10. POWER LEVEL 'IO WHICH RESTRICTED, IF ANY (NET MWe): N/A

?ll. REASON FOR RESTRICTION, IF ANY: NONE MONIH YEAR CUMULATIVE

'12. REPORT PERIOD HRS- 672.0 1416.0 133129.0

13. HOURS RX CRITICAL 98.8 842.8 .86470.7

14. "RX RESERVE SHTDWN HRS 289.8 289.8- -759.5

.15. - JHRS GENERA'IOR ON-LINE 28.3 772.3 84309.0-

.16. Ur RESERVE SHTDWN HDS 552.8 552.8 555.5-

17. GROSS THERM ENER (MI) 61440 1444440 138706769-

% D. GROSS ELEC ENER (WH) 16340 501310 46884305

19. NET ELEC ENER (WH) 11152 478805 45041370

20. Ur SERVICE FACIOR 4.2' 54.5 63.3 21'. Ur AVAIL FACIOR 86.5 93.6 63.7 22.. Ur CAP FAC'IOR (MDC NET) 2.7 54.5 54.6

23. Ur CAP FACTOR (DER NET) 2.6 52.0 52.1'

24. .Ur FORCED OUTAGE RATE 39.5 2.3 9.6

- 25. - PORCED OUTAGE HRS 18.5 18.5 8969.6

- 26 . - SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION): N/A

. 27 . .- IF CURRENTLY SHUPDOWN ESTIMATED STARTUP TIME: N/A d _

r.-_.-. -q-c.-

AVERAGE DAILY POWER LEVEL NET MWe-DOCKET 4.-

4 . 50-219

. UNIT. . . . . . . . . .-. Oyster Creek #1 REPORT DATE . . .-. . . . MARCH 08, 1985 COMPILED BY . . . . . . . THOMAS J. MCKINNEY TELEPHONE #'. . . 1. . . 609-971-4456.

m .

M0tfIH FEBRUARY, 1985 DAY- E DAY E

1. 612 - 16. 0

2. 37 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

15. 0

v .. . ., . . .

2,

~ l?[ '

Oyst:r Creek' Stttion il 1

- Dock;t No. 50-219 y.

REFUELING INPCRMATION.- February,1985 Name of Facility: ~ Oyster Cre.

Station il Scheduled date'for next. refueling shutdown: November 30, 1985' Scheduled date'for: restart following. refueling: June 1,'1986 Will refueling-or resunption of operation thereafter require a Technical Specitication change or-other; license' amendment?

Yes V - . .

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

June, 1985 Important licensing considerations' associated with refueling, e.g., new or ditterent fuel design or supplier, unreviewed design or performance analysis 7 methods, significant changes in tuel design, new operating procedures

1. General Electric Fuel Assemblies - tuel design and performance

' analysis methods have been approved by the NRC. New operating 'I procedures,.'if'necessary, will be submitted at a later date.

2. Exxon Fuel Assenblies - no major changes have been made not are there any anticipated.

We number of fuel assemblies (a) in the core = 560 (b) in the spent fuel storage pool = 1029

%e present licensed spent tuel pool storage capacit.y and the size of any increase in licensed storage capacity that has been requested or is planned, in nunber ot. tuel assenblies:

Present licensed capacity: 2,600

%e projected date ot the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

~

'Reracking of the.tuel pool is in progress. Four out of ten (10) racks have been. installed to date.

4 I

.)

.,7ty; '.ag = -

~

%-} --_'-

. _ ' s 3 _.; , = :.  :

DOCKETNO.- 50-219 tj UNITSHUTDOWNS AND POWER REDUCTIONS Oyster cree};

UNITNAME ,

DATE 3-R-R5 .

COMPLETED BY R. Baran REPORTMOrmt February 1985 TFfFPHONE 971-4640 ,

E ._

m o e ~

No. Date g

$E 3 sj "g

$I3 ygy Licensee Event E%

u3 o-3 Cause & Corredive Action to F

$E E jig Report ; no o Prevent Recurrence 36 2-2-85 F 643.7 A Z N/A ZZ ZZZZZZ Unit shutdown to correct a potential design deficiency with the Core Spray System booster pump logic.

s .

I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sh::ts for Licensee C-R:iu: ling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory R:striction 4-Oth:r (Explain) 0161)

E4)perator Training & License Examination F-Administrative . 5 .

G-Operational Error (Expls'm) Exhibit !-Sanne Source ~

(9f17) Il4):her(Explain)

=m,

m- ,*+---

~,

p. ,- - _ ,

.t s ,

A.

~

'~

GPU Nuclear Corporation r

NggIg{ '

Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writers Direct DialNumber:

March 18, 1985 Director Office of Management Information U.S. Nuclear Regulatory Comission Washington, DC. 20555

Subject:

Oyster Creek Nuclear Generating Station -4 Docket No. 50-219 -

. Monthly Operating Report In accordan:e 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. Drev Holland at '

(609) 971-4643.

Yery truly yours, ., ,

p , '..

P 8 i er Vice President and Director Oyster Creek ,

~

P8F:KB: dam (0170A)

Enclosures v 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 GPU Nuclear Corporation is a subsiduty of the General Public Utilities Corporation

- X6Y g

-.