ML20044B344

Monthly Operating Rept for June 1990 for Oyster Creek Nuclear Generating Station.W/900712 Ltr

ML20044B344
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1990
From:	Baran R, Fitzpatrick E, Sedar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007180367
Download: ML20044B344 (7)

Text

, -

-=

.: [i_

x.' d. :... ..

, y d .8 y,

% n_

4 GPU Nuclear Corporation N .

g' Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971 4000 g Writer's Direct Dial Nurnber:

July 12,1990 U.S.1 Nuclear Regulatory Commission 4 ATTN Document Control Desk Washington,.D.C. 20555

Dear Sir:

-Subjects Oyster' Creek Nuclear Generating Station Docket No. 50-219

' Monthly. Operating Report In accordance with the Oyster Creek Nuclear Generating Station LOperating. 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 tho' Oyster Creek Nuclear Generating Station.

If you should.have,any questions, please contact Brenda DeMarchant,;

Oyster-Creek-Licensing Engineer at (609) 971-4642.

,, 4

Very _

uly yours,

,, s 2

-,- 4 , -)

E  %.tzpktick -

Vice President-and Director ';

a Oyster Creek .

.-EEF:BDEM:jc (MOR) -!

N Enclosures

.- tcca iMr. Thomas Martin,' Administrator.

d ' Region I U.S. Nuclear Regulatory Commission 475~Allendale Road King of Prussia,.PA- 19406-

'Mr. Alexander W. Dromerick, Project Manager

> U.S. Nuclear Regulatory Commission ,

, Washington,EDC~-20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station l

9007180367 900h30 ,

PDR ADOCK 05000219 / 1 t-R PDC .I (IM ?Qj g L GPU ' Nuclear Corporation is a subsidiary of General Pubhc Utikties Corporation f - -.

r-

-] - g.' c.

HONTHLY OPERATING REPORT - JUNC 1990

h. At the beginning of June, Oyster creek was operating at a grvss generator load of 656 MWe and increasing power gradually. Full power was achieved on June 1.  !

On June 9, gross generator load was reduced to 383 MWe to clean "A" condensate pump lube oil cooler and replace brushes on 'D' reactor recirculating water pump motor generator set.- Full power was achieved on June 10.

On June 21, in order to-reduce the radiation field, power was reduced to 316 MWe during-replacement of the 1-2 auxiliary flash tank pump motor. Following

. repair, power was increased to 91% and stabilized while a problem with the j reactor manual control system was corrected. Full power was achieved on June i 22.

On' June 25, a reactor scram occurred due to low condenser vacuum caused by a  ;

tripped condenser backwash outlet valve. The plant remained shutdown for .I' maintenance through the end of June.

q-i i

.l 4

t -

3

,

s' 'e

'A >ol MONTHLY OPERATING REPORT JUNE, 1990 The following Licensee Event Report was submitted during the month of June, 1990s.  !

1

-LER 90-06: Individual components Exceed TS Max Test Interval Due to j Personnel ErgpI '

l

'1

' on May 9, 1990, the Group Shift Supervisor and the Shift l Technical Advisor removed the cleanup System losses from the plant heat balance calculation while the cleanup System was out j 16 of service.- On May 11, 1990 the cleanup System was placed back  !

into service without the 7.84 megawatt loss added into the heat- j balance-calculation.- For t's next nine and one half hours the 1 average power level exceeded the Licensed limit by approximately 1.64 megawatts. The safety significance of-this event is minimal. ,

as the power level during this event averaged 100.08%. -This-power'1evel would have a negligible impact on the results of-transient or accident analyses. Furthermore, there were ampla margins to. operating limits for the Critical Power' Ratio and'  ;

Average Planar Linear Heat Generation. Rate. {

q The cause of this occurrence is personnel error.. This activity was not controlled by plant procedures and the individuals. .;

involved:did'not ensure adequate controls were established to control-the-evolution.

Procedure changes will be made to-ensure that the computer inputs.

to.the heat balance are adequately controlled.

i

>r' ,

s A

s s

i l

l Y

u o

I t

i ((

I- i p

, =.

4 f

t

.ys.

OPERATIN3 DATA REPORT 3

' OPERATING STATUS

', .1.- DOCKET: 50-219

2. REPORTING PERIOD: 06/90

3. UTILITY CONTACT: JOHN SEDAR 609-971-4698

4. LICENSED THERMAL POWER (HWt): 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 ABOVE SINCE LAST REPORT, GIVE REASONS: NONE

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): None

11. REASON FOR RESTRICTION, IF 6NY: None MONTH X1hg CUMULATIyg

12. REPORT PERIOD HRS 720.0 4343.0 179879.0

- 13 . ' HOURS RX CRITICAL 582.3 3465.8 114726.4

14. RX RESERVE SHTDWN HRS- 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 582.3 3358.3 111590.1;

-16. UT RESERVE SHTDWN HRS 0.0 0.0= 1208.6 17.- GROSS l THERM ENER (HWH)- 1103254 5840120 187113179

18. GROSS-ELEC ENER (MWH) 364390. 1931610 63054350

19. NET ELEC ENER (MWH) 349930 1851670 60506648

20. UT SERVICE FACTOR 80.9 77.3 62.0

21. UT AVAIL FACTOR 80.9 '<7.3 62.7

'22. UT CAP' FACTOR-(MDC NET) 78.4 68.8 54.3

23. .UT CAP-FACTOR.(DER NET) 74.8 65'6. 51.7

24. UT ' FORCED ' OUTAGE RA IE 19.1 18.6 12.0-25.- FORCED-OUTAGE HRF 1$7.7 765.8 15175.9

-26.- SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION): NONE.

27. IF CURRENTLY SHUTDOWN-ESTIMATED STARTUP DATE: 7/03/90 o

1619B/29

, Q 22--_________- . _ _ _ - - - - -

k .'

Yl e

- ';'.6.,,

~

't' -

AVERAGE DAILY POWER LEVEL.

[1 , NET MWe DOCKET #. .-, . . . . . 50219 "f" '

UNIT. . . . . . -. . . . . OYSTER CREEK #1-REPORT DATE . . . . . . . JULY 9, 1990 COMPILED BY .-. . . . . . JOHN H. SEDAR TELEPHONE # . . . . . . .609-971-4698 MONT!! JUNE, 1990' T

DAY E -PAX E l '. 622 17. 614 2, 618 18. 612

3. 611 19 '. 609-4 '. 622 20. 609 5.: 618 21. 500

's,; 6. 616 22. 578 7.- 617 23, 578

8.  ! 616 =2A. 607'.

'9. '499 -25. 152,

.a .

10. 615 26. . 0.

ll. 616 27. 0

12. 619 28. O Tp 13, 616 29. 0 14, 617 30. 0

'y 1

15. 617

16. 617 t

i

il r

.l! 1

'1619B/28' q

> N .- ,

) .

S

^

b w '

j 'gbyf -i Oy3tcr CrOrk StCtien #1 k

Docket No.'50-219 ,

L.

REFUELING INFORMATION - JUNE, 1990 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: January 11, 1991 pending necessary state approval.

Scheduled date for restart following refueling: May 19, 1991 L.

Will ~ refueling or resumption of operation thereafter regpire a Technical Specification change r, other license amendment?

Yes ,

J- ' Scheduled date(s) for submitting proposed licensing action and supporting informations.

I 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:

t

-1. General Electric Fuel Assemblies fuel design and performance ,

analysis methods have been approved by.the NRC. 1 I

( 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 = 11595 (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 b numbercoftfuel assemblies: .

Present licensed capacity: 2600 -

The projected date of the last refueling that can be discharged to tho spent

. fuel pool. assuming the present licensed capacity: ,

LReracking of the fuel pool is in progress. Nine (9) out of ten (10) racks have~ been installed to date. When reracking is completed, :i 7p '

discharge capacity to the spent fuel pool will be available until 1994 refueling outage, i

.i 1619B/27 m

k ~

if h 4/ i:

~-- -

~

. . . . . UNIT SEUTDOWNS AND POWER REDUCTIONS DOCKET NO.

~

50-219 UNIT MADE Ovetor Creek DATE- July. 1990 COBE'LETED BY R. Baran' TELEPHONE 971-4640 REPORT MONTE JUNE 1990 TYPE NETHOD OF SEUTTING F Forced DURATION DOWN THE REACTOR OR NO. DATE S Scheduled. (Bours) REASON (1) REDUCING PONER (2) CORRECTIVE ACTIONS /COBSENTS 101 6/9 5 -0 B 1 Load reduction to clean *A*

h sate Pump Lube 011 Cooler Imad redaction to replace the 102 6/21 S O A 1 sootor on the 1-2 Auxiliary Flash Tank Pump. (ALARA concerns) 103 6/25 F 137.7 A 3 Automatic full scram due to main condenser loor vacuum. Loer vacuum caused by a loss of of circulating water when backwash valve V-3-18 failed to open during condenser backwashing.

SUMMARY

(1) REASON (2) METHOD A.- Equipment Failure'(Explain) E. Operator Training & License Exam 1. Manual B. Maintenance or Test .F- Administrative 2. Manual Sc3Ea C. Refueling 4. Operational Error (Explain) 3. Automatic Scram D. Regulatory Restriction E. Wher (alzplain)' 4. Other (Explain)

~>

e

• ~ - -

w ., y ~ *-%. -

,,y -

g,w . __ p. _, _ _ _ _ _ ,_ , _ _ _ _ _ _ _ _ . _ . , _ _ . _ _ _ _ ,,

________,____m,_, , ,