ML20247A947

Monthly Operating Rept for June 1989 for Oyster Creek Nuclear Generating Station

ML20247A947
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1989
From:	Baran R, Fitzpatrick E, Sharma H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8907210371
Download: ML20247A947 (8)

Text

_

.y.

l GPU Nuclear Corporation Nuclear

en:r888 Forked River. New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

July '17,1989 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk 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 Kachy Barnes, Oyster Creek Licensing at (609) 971-4390.

Very truly yours, E.E.Fitzpatpicksf ee Vice President and Director Oyster Creek EEF:KB: dmd (0841 A:1 )

Enclosures ec: Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Comrr.ission o..

dashindtx, DC 20555 Mr. William T. Russel?, Administrator o,-o Region I

$$f U.S. Nuclear !!egulatory Commission

$8 475 Allendale Avenue g

King of Prussia, PA 19406 pd Mr. Alexander W. Dromerick, Project Manager gg U.S. Nuclear Regulatory Commission ge Washington, DC 20555 wgg NRC Resident Inspector coa.cc Oyster Creek Nuclear Generating Station GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation L _

MONTHLY'0PERATING REPORT JUNE 1989 The following Licensee Event Reports were submitted during the month of June 1989:

LER 89-013 - TECHNICAL SPECIFICATION SHUTDOWN DUE T0 ISOLATION CONDENSER VALVE OPERATOR FAILURE On May 8,1989, during a reactor startup,.a reactor plant. shutdown and cooldown, as required by Technical Specifications, was conducted due to the "B" isolation condenser becoming inoperable. The isolation condenser became inoperable when isolation condenser condensate return valve, V-14-35, Limitorque operator (type SBD-2-60) tripped due to electrical current overload protection during a valve cycling evolution.

This removed remote operation capabili.ty, leaving it inoperable in the shut position. Manual operation was still possible. The "B" isolation condenser was out of service approximately

~ 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.. The cause of this occurrence is component failure.

Immediate investigation revealed that a 3/32 inch roll pin in the Limitorque geared torque switch had sheared, preventing the torque switch from stopping the motor operator when the valve was fully seated in its shut position.

The safety significance of this event is considered minimal since during this period the' "A" isolation condenser was available for operation. Concurrently with plant shutdown, the "A" isolation condenser was demonstrated operable.

The torque switch on V-14-35 was replaced.

No evidence of further damage was discovered in the Limitorque operator. Analysis showed that the' thrust applied to the valve during the event was not sufficient to damage the valve stem or seat. All other motor-operated valves in the "B" isolation condenser systrm wera tested for operability with satisfactory results.

LER 89-014 - REACTOR COOLANT IODINE ACTIVITY SAMPLE NOT TAKEN DUE TO PERSONNEL ERROR On May 15,1989, a reactor coolant sample was not taken and analyzed for dose

. equivalent iodine-131 (D.E. I-131) activity following a reactor power change of greater than 15% as required by Technical Specifications. The reactor power change was approximately 17% which met the criteria to perform the sample. The root cause of this occurrence is personnel error.

The Group Shift Supervisor forgot about the I-131 sample requirement. Two contributing factors were also evident.

The procedure change.that incorporated the requirement into the technical specification log sheet (TSLS) was worded incorrectly, such that the sample was required only upon an increase in power. Additionally, the power level change was calculated from power levels logged hourly, on the hal f-hour. Thus, the minimum power level attained did not coincide with the minimum that was logged (because of the short duration of the transient) resulting in a transient of less than 15% by the logged rea dings. The safety significance of this event is considered minimal.

The intent of the D.E.1-131. analysis following a significant power change is to detect a transient increase in coolant f odine levels termed " iodine spiking".

The information obtained by this sampling requirement is used to assess the parameters associated with the spiking phenomena.

Corrective action included correcting the wording error, and reviewing the sampling requirement with operations personnel. Additionally, guidance concerning this requirement is being added to other appropriate station procedures.

l 1

MONTHLY' OPERATING REPORT - JUNE 1989 At the beginning of the report period, Oyster Creek was operating at-full power with a gross generator load of approximately 645 MWe.

l l-On June 8, during routine surveillance testing on a 4160 Volt Emergency: Bus, an undervoltage relay failed.to trip.

In accordance with Technical Specifications, plant shutdown commenced.

Following installation of jumpers around the relay to simulate a trip condition, the shutdown was terminated.

On June 12, a leak developed on a feedwater string and plant load was reduced to approximately 70% to accommodate repairs.

On June 17, plant load was further reduced to approximately 34% to facilitate cleaning the strainer on the Stator Cooling Water System.

Upon completion of stator cleaning and repair of the feedwater leak, power was increased.

Full power was achieved on June 18.

On June 25, while operating at 97% power, a generator trip occurred due to failure of M1A main transformer and caused a reactor scram due to an anticipatory turbine trip signal.

The sudden closure of the turbine control valves resulted in a reactor pressure spike which caused the automatic actuation of the isolation condensers, electromatic relief valves and an automatic trip of the reactor recirculation pumps.

The plant responded as expected during the transient and was subsequently placed in a cold shutdown condition.

At the end of the report period, preparations to return the plant to service with only one transformer were completed and reactor startup commenced on June 30.

Plant load will be limited to approximately 50% power with only one transformer in service.

l 1

I 1

l.' censee Event Reports -June 1989.

i

~

~

, Page 2 LER 89-012 - REACTOR SCRAM CAUSED BY INADVERTENT MISPOSITIONING OF THE REACTOR MODE 5 WITCH WHILE REMOVIWG KEY FROM THE SWITCH LOCK On May 20,1989, in preparation for a reactor startup, the reactor mode switch was moved from the SHUTDOWN position to the REFUEL position. The control room operator experienced difficulty while attempting to. remove the key from the, mode switch to lock the. switch in the REFUEL position. While manipulating the key, the switch was moved out of the REFUEL position and contacts from the SHUTDOWN position were opened and a full scram signal was received. The cause of the occurrence is binding in the reactor mode switch key lock and excessive play in the mode switch due to mechanical wear.

Since the reactor was shutdown and no rod movement actually occurred the safety significance of the event is considered minimal.

Immediate action was taken after the scram signal.to ensure that the Reactor Protection System responded normally.

The scram was reset, and the switch was locked in REFUEL. Maintenance will be performed to attempt to ease the binding of the key in the lock on the reactor mode switch.' Additionally, mode switch replacement is being evaluated.

LER 89-015 - MAIN GENERATOR TRIP-CAUSES AUTOMATIC' REACTOR SHUTDOWN DUE TO PTR50NNEL ERROR

.On May 18,1989 at 1103 hours0.0128 days <br />0.306 hours <br />0.00182 weeks <br />4.196915e-4 months <br /> the reactor automatically shut down due to a trip of the main turbine generator. An instrument technician had been assigned the task of calibrating the plant megavar recorder. He : discussed the activity with shift management but did not mention that input leads to the recorder would be disconnected.

The technician started the evolution an hour and a half later without informing the Control Room. Upon disconnecting the input leads to the recorder, a Hi/ Low VAR alarm was received. The operators did not realize that the alarm was the result of the technician's work and attempted to manually restore the VAR loading. The operator did not realfze that he was actually increasing megavars because he was not observing bus voltages, which were increasing. A generator overexcitation condition resulted which tripped the main generator, caused a reactor scram, and resulted in a fast start of both diesel generators.

The operators proceded to cooldown the plant with the Isolation Condensers until the Shutdown Cooling System was placed into service at 1523 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.795015e-4 months <br />. The plant reached cold shutdown conditions at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />. The root cause of this event was personnel error on the part of both operations and maintenance personnel.

To prevent a recurrence of a similar event, administrative controls have been f

implemented and increased emphasit has been placed on communications between the work group and the control room.

Operators will be briefed on the need to-use all available indications during a response to an abnormal condition to avoid'a recurrence of this event-1 3

l

____________________________J

OPERATING DATA REPORT OPERATING STATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD:

06/89 3.

UTILITY CONTACT:

HARI S. SHARMA 609-971-4638 4.

LICENSED THERMAL POWER (MWt):

1930 5.

NAMEPLATE RATING (GROSS MWe):

687.5 X 0.8 = 550 6.

DESIGN ELECTRICAL RATING (NET MWe):

650 7.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

642 8.

MAXIMUM DEPENDABLE CAPACITY (NET MWe):

620 9.

IF CHANGES OCCUR AB0VE SINCE LAST REPORT, GIVE REASONS:

NONE

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): Approximately 50%

power.

11.

REASON FOR RESTRICTION, IF ANY:

Main transformer out of service.

MONTH YEAR CUMULATIVE

12. REPORT PERIOD HRS 720.0 4343.0 171119.0 13.

HOURS RX CRITICAL 576.1 1132.7 107378.1

14. RX RESERVE SHTDWN HRS 0.0 0.0 91 8.2

15. HRS GENERATOR ON-LINE 576.1 993.4 104536.9 16.

UT RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THERM ENER (MWH) 1030000 1734870 174225759

18. GROSS ELEC ENER (MWH) 337410 566250 59170434

19. NET ELEC ENER (MWH) 323854 524593 56784461

20. UT SERVICE FACTOR 80.0 22.9 61.1 21.

UT AVAIL FACTOR 80.0 22.9

61. 8

22. UT CAP FACTOR (FDC NET) 72.5 19.5 53.5 23.

UT CAP FACTOR (DER NET) 69.2 16.6 51.1

24. UT FORCEO OUTAGE RATE 20.0 19.2 11.6

25. FORCED OUTAGE HRS 143.9 235.7 13746.4

26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):

None 27.

IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:

A Plant shutdown occurred on July 11 caused by a fault in the M1B main transfonner.

Estimated start-up date is July 15, 1989.

1619B/0045X I

, tr o -

?e, 2 l

ce SJf9h 7jf' 1

1 Gdij

{

p

^

AVERAGE DAILY POWER. LEVEL-1 NET We:

DOCKET #......'..

50219 UNIT.. _........ 0YSTER CREEK #1 REPORT DATE........ July 6,1989 COMPILED BY...:....HARI S.'SHARMA

TELEPHONE' #...... :.609-971 -4638 '

MONTH' JUNE,1989 DAY-

_MW DAY

_MW.

1.

620 17.

276 2.

61 8 18.

558-3.

61 6

19..

611 4.

61 6 20.

'608 5.

. 61 8 21,

6 01 6.

~ 615 22.

593 7.

61 6 23.

596

8.,

61 5 24.

594 9.

61 5 25.

0 10.

61 6 26.

0 11.

620 27.

0 12.

61 2 28.

0 13, 41 4 29.

0 14.

427 30.

0 15.

428 16.

428

'16198/0045X :

___1__

____.__.________________m._

__.__m._.... _ _ __ _ _ _ _ _ _ _ _ _ _,

f s-Oyster Creek Station #1 Docket No. 50-219

[

REFUELING INFORMATION - JUNE,1989 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Ja nua ry 11, 1991 pending necessary state approval.

Scheduled date for restart following refueling: April 13,1991 Will refueling or resumption of opera tion thereafter require a Technical Specification change or other license amendment?

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

July 15,1990 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 performa nce analysis methods have been approved by the NRC.

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

The number of fuel assemblies (a) in the core 560

=

(b) in the spent. fuel storage pool 1595

=

(c) in dry storage 37

=

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, in number of fuel assemblies:

Present licensed capacity: 2600 The projected date of the last refueling that can be discharged to the spent fuel pool aming the present licensed capacity:

Reracking of the fuel pool is in progress.

Nine (9) out of ten (10) racks ha ve been installed to date.

When reracking is completed, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.

1619B/0045X

e ey c

rl n

k_

un a

i e

v t oe e

e 9 r -

a mo nAs r 8 oed omsit o

a C 9 n 0 t se t rat h e 1

a 4 S

e Aw t

d

.ph 9

r r 6 T

nmF

)

sn a1 t

1 e

, a 4 N

oo smEi e o:.n 2

t y B E

irn sew m

l ion M

tf o otMd e g

i s

l 1

0 y u 7_

5 O J R 9 M

c rs ec lid u gk G y5t n l set O

d na (S7 oe u

rl C

eie nm f pru

/

. E E Y E S

rrl E gt mn i ua O

Unaeoo mrcf Da N M T B N N

t D

O O

dS e e

Mi mci ot c OM A A I

a n v l ei s

r oa H

T N D H

T ori l

5 omt nn f e r

T E

E l el a

7 oi oe npoe E :

P C

K T T

E A

t V

CTnic miit m M1 E

% an o

ot s ab r r

I C

L E

N L

4 wi g

t r i ca rrt eo

)

O E

V 3d a n

o

.t u

cu uf 2

U P

T D

M T

er I

nt rad r St rd s

(

i O

C yed t

oaeree o

n E

l F a

it nurw r yt l a C

R e

a l

tSiD o

oraar u

c a

rp t oriT R

t 'B a

r g

uer e

ct et O

wf aannn C

m'i e

dht i

a R etS soo epeei xep r

rp rig ra ove r

nt u t

c eM ror e

d aeomr l i nf S

pm t

ael h oa l tifA N

peo a

ol n rt unai1 O

A rt w

LcI 2f s F aMdM ITC 9

2

)

U 8

N R(

OR D

9 W

E E

1 FO R P

E OD O W TO N

DG C P R

A A

U ON AG E

J I

/

/

3 H

D W T EN N

N T

TRI X O E

C P

M UEU lD HHD l

N D T

ST E i

E N N

R P A O

P S M

A N

)

T W

R 1(

O O

N D

P O

A A

A T

E SA U

R E

H R

S T

IN N

U O )S I

R T

4 9

A U 8

O R

7 7

3 H

U(

9 4

D 1

D E

D L E U EC PR D F

5 F

E YO H T F CS F :

N S

G 5

S 8

9 9

A E

/

8 8

E R

T 2

/

/

A 1

7 5

D

/

1 2

)

Y 1

6

/

/

3 3

R

(

A M

5 6

M O

4 N

7 7

7 U

S

-