ML20043G135

Monthly Operating Rept for May 1990 for Hope Creek Generating Station

ML20043G135
Person / Time
Site:	Hope Creek
Issue date:	05/31/1990
From:	Hagan J, Loeper S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HSE-90-214, NUDOCS 9006190106
Download: ML20043G135 (14)

Text

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Public Service E!cctric and Gas Compatiy P.O. Box 236 Hancocks Bridge, New Jert.ey 08038 Hope Croek Operatione l-June 15, 1990 HSE-90-214 U. S. Nuclear Regulatory Commission p'

Document Control Desk Washington, DC 20555

~O Dear Sir MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for May are_being ferwarded to you with the summary of changes, tests, and experiments for May 1990 pursuant to the requirements of 10CFR50.59(b).

Sincer ly yours,

.J H gan Gene al Manager -

Hope eek Operations R:1d Attachment C

Distribution l

9006190106 900531 y

FDR ADOCK 05000324

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AVERAGE DAILY UNIT POWER LEVEL e

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DOCKET.NO. _50-354=

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UNIT

_ Hope Creek DATE 6/15/90 COMPLETED BY S.

Loeper /f4

' TELEPHONE-(609);339-5257-MONTHi May 1990' DAY' AVERAGE, DAILY POWER-LEVEL DAY AVERAGE DAILY POWER LEVELL (MWe-Net)-

(MWe-Net)

1 1059 17 1054 e

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2-1059 18 1051

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% 15 102_2-31' 1061-J16-11047 3

• Due to.an error in recording _the metel readings, the-exact average dailyJ L

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' power 11evel for May 21, 22, and 23 is unknown'.

The listed averages for 4

.thosenthree. days. represent-the average of the three-day total.

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L OPERATING DATA REPORT i..

DOCKET NO. __50-354 UNIT

_ Hope Creek

[,

DATE _6/15/90 COMPLETED BY S.__LoeAer TELEPHONE (609) 339-5257 OPERATING STATUS

$v

-1L REPORTING PERIOD May 1990 - GROSS HOURS IN REPORTING PERIOD 744_

h 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 p

MAX. DEPEND. CAPACITY (MWe-Net) 1031 C

DESIGN' ELECTRICAL RATING (MWe-Net) 1067 I 3'.

POWER LEVEL TO WHICH-RESTRICTED (IF ?.NY) (MWe-Net)

None REASONS FOR RESTRICTION (IF ANY)

4. :

THIS YR TO MONTH DATE CUMULATIVE 5.

No. OF. HOURS REACTOR WAS CRITICAL 744.0,

_3307.8

_2_5 069.3 2

'6.. REACTOR RESERVE SHUTDOWN HOURS 0. 's 0.0~

0.0

,7 L. HOURS GENERATOR ON LINE-744.O

_3271.3

_2_44 22.5 8.-

UNIT RESERVE SHUTDOWN HOURS 0.0-0.0 0.0 9.-

GROSS THERMAL-ENERGY GENERATED (MWH)

_2,422,679_

10,469,566 '77,425,942_

10.. GROSS ELECTRICAL ENERGY.

. GENERATED (MWH) 805.070

_),463,180_ _25,619,4431 11.

NET ELECTRICAL' ENERGY GENERATED (MWH) 772;503

_3,317,7481 24,474,297:

12.

REACTOR SERVICE FACTOR 100.0 91.3 83.0-113.

REACTOR AVAILABILITY FACTOR 100.0 91.3 83.0' 14.

UNIT SERVICE FACTOR 100.0 90 3 81.5 1

?15.. UNIT 1 AVAILABILITY FACTOR 100.0 90.3 81.5 f 16 '. : UNIT CAPACITY FACTOR

(Using MDC);

100.7 88.8 78.6 x ' ' 17. - UNIT CAPACITY FACTOR i

.(Using. Design MWe) 97.3 85.8 75.9

==,

18. IUNIT_ FORCED OUTAGE RATE 0.0 5.9 5. 6__

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

None

.20'.,'IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:

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yo 7. + ; j OPERATING DATA REPORT-W UNIT SMITTDOWNS AND. POWER REDUCTIONS F

~ DOCKET No.

__50-354' 1

,s UNIT'..,_ Hope Creek DATE'_6/15/90 S

COMPLETED BY SeLoeper #

c-r REPORT HONTH May, 1990 TELEPHONE

( 609J_ __33 9-5257 '

(i, G

HETHOD OFc 8

SHUTTING-I DOWN THE; ls:-

TYPE

-REACTOR OR i

F-~ FORCED' DURATION REASON REDUCING CORRECTIVE ACTION /:

NO.

DATE SsSCHEDULED (HOURS)

(1)

POWER (2)

. COMMENTS

- i:

[; l 6

5/19.

- S' O

B 5

Resultsiof vibra-tion-data' trending' iW a n d - o i ll s a m p l e s --

?

indicated a' i

[i potential bearingL p

problem.on:a.

Secondary 1 Condensate ' Pump.

L; Bearings replaced _

as a precautionary-7:

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SUMMARY

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>4 REFUELING INFORMATION y

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[ COMPLETED BY:

Chris Brennan DOCKET NO: 50-354 I

. UNIT NAME:-tiope Creek Unit 1 10

.f DATE:._$f_15/90 l

TELEPHONE: '(609) 339-1232 2

EXTENSION: N/A

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V 1 Month-May 1990

=

i. cRefueling'information has changed from last month:

l O'

YES NO X-I ',

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.2.

Scheduled date for next refueling:

01/19/91 p

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3.

Scheduled date-for restart following refueling,_01/05]_91_,

[

4.

-A) 'Will Technical Specification changes or other license

- amendments be' required?

ii YES-NO-

_X b

B) _Has the reload fuel' design been reviewed by the Station' I

Operating Review Committee?

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YES-NO X

j.

If.no, when is it scheduled?

02/01/91-f 5.-

-Scheduled'date(s) for submitting proposed' licensing _ action: pfl.

Y p

Important: licensing considerations associated with refueling:

Ib

6..

P.

-Am,3ndment'34 to the Hope Creek Tech Specs __ allows the cycle

-specific operaMng limits to be_ipcorporated into the CORE i

-OPERATING LIRITS REPORT:. a _ p u b m i.t t a l _ i_s t h e r A f a r e n o_t, y

0-Lequ_irejl.

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b7._1 Number of Fuel Assemblies:

'B)nInl Spent Fuel Storage 764

's, :

fA);.Incore (prior to refueling) _496 7

,l' cC) In; Spent Fuel Storage (after refueling)

- _7,J4 j

4..

1 &" " '

38'.-CPresent licensed spent' fuel storage-icapacity:

1290 v

a

Foture spent fuel storage capacity:

4006

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9P TDate of last refueling that.can be

?g _..

' discharged.to spent fuel pool assuming J',

'the present licensed capacity:

03-05-91

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' HOPE CREEK GENERATINGJSTATION--

F sw.

MONTHLY' OPERATING.

SUMMARY

JN f ';g" Y

.MAy 1990.

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' Hope Creek. entered the month of. Hay at approximately 10 % power.

f'. ' On. May.19th power. was-reduced to-replace bearings on a Secondary

[ic

[ T-

% Condensate Purep. ' Power-was returned to aproximately 100%'..

The -

unit operated.throughout the. remainder of the; month without.

p' foxperiencing:any? shutdowns or other reportable power--reductions.

jf

On May 31..the plant'. completed its 65th day.of' continuous.. power'

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'The following Design Change Packages (DCPs) have-been evaluated to-ji1 determine::

E h

!1) if,the! probability of occurrence or the consequences of an--

accident or-malfunction of equipment important to safety previously evaluated.in the safety analysis report:may be increased;-or g

a

..2) if~a: possibility for an accidentior malfunction of a

?

'.differentLtype than"any evaluated previously in the safety

- analysis; report may'be' created; or-

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if thermargin of> safety as defined in the basis for'any

' technica11 specification is reduced.

The-DCPs[did not create 1a<new safety hazard to the plant.nor did

~it affect 1the safe shutdown of the reactor.

The DCPs did not-change'the plant effluent releases and did not alter the, existing v

'~

environmental. impact.

The Safety Evaluation determined that no

'Kunreviewed safety or environmental questions are involved.

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- p_escriptioniof ~ Desion_ Chance __ Packagg This DCP replaced the existing brick shielding 9

4HC-0294','

i on the-south-side of the post accident sample

' system (PASS) sample-panel with a removable i-1ead door.

In addition -the liquid sample 1 cask CJ will be^ restrained to the lead door support-f' steel.by means of a-chain, to restrict the-i movement of the-cask-when in the stored h

position.

Theilead door will allow operator t

access to the internals of the' PASS-panel in a

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-fraction'of..the timefeurrently required.

The tu replacement of the. lead. bricks;will-improve-the provisions for maintenance of post accident sampling equipment.

In. addition to the

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shielding modification-thelliquid sample

'l p

transport-cash will be tied down (chained)'to F

the lead door Jtructural' column.

The liquid i

sample cask requires restraint due to the

'l proximity of nearby.II/I equipment and class-1E raceway supports.

i 4HM-0026 This DCP installed sources on detectors in'the

l Process Radiation, Monitoring System.

The added 1

background activity-enables radiation monitors' i

to provide an-on scale indication during'all plant operational Lodes and all-reactor power

levels, i

4HM-0352 This DCP installed temporary instrumentation near'the drain valves on pipesLleading back to.

l 1

the condenser.' By monitoring the temperature

- remotely from areas, accessible.at 100% power, any. temperature substantially above room-tenperature.will_ disclose.a. potential.. source of-

. lost' megawatts.

4HM-0404

. This DCP permanently;installod'an ion ~

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chromatograph, bypass 1 flow capability.for sample' lines, corrosion. monitoring for sample lines, GE:Zine Plus Modification cabinets, spared _in place analyzers,.and' rerouted instrument. tubing.' The modification will' pr^ vide mo:e information1about water chemistry.-

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TheLfo11'owing Temporary Modification Request'(THR) has been' 8

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t evaluated to-determine:

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Lif.the probability of occurrence or the consequences of an accident'or malfunction of equipment importantLto-safety

[:

previously evaluated.in the safe?.y analysis report may be

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~ increased; or fs

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L2) it a possibility;for an accident or malfunction,of a'dif'ferent-6:

type,than any evaluated previously in'the. safety analysis ~

Ereport may be created or H

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if'th'e margin of safety.as defined in the basis-for any technica3' specification'is reduced.

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'The TMRLdid not. create a new safety hazard to the' plant nor.did

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g they. affect the safe shutdown of the reactor.- The THR did not

((

change the plant effluent / releases and did not' alter.the. existing-

. environmental impact.- The Safety Evaluations determined that no

'E O

' unreviewed'safetyhor environmental. questions are involved.-

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5 TUR Description of Temporary Modification Re, quest L

90-039 This Temporary Modification added a jumper-across wires in a high oil temperature switch to permit the Control Room Water Chiller to run p

with a defective module and/or thermistor until

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replacement parts can be procured and

(

installed.

Installation of this jumper as a

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temporary modification will disable the p

chiller's high bearing oil temperature trip, i

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4-The-:following; Deficiency Reportf(DR) has been evaluated.to

W' determine

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accidentTor malfunction of equipment important.to safety lijf Lpreviously evaluated in the safety _. analysis report may be

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. type'thaniany evaluated previously in the safety analysis:

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.if,a possibility for an accident:orimalfunction'of a'different-Qk

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- report may:be created; or

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I3) if'the margintof. safety as defined in'the basis for any b[

-technical: specification is reduced.

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t-The DRJdid not create.:atnew safety hazard to tiie plant nor didTthey,

affect

the: safe; shutdown of the reactor.. The DR:did not-change the-Q

'plantieffluent? releases and did'not alter the. existing g'

environmental impact.: The Saf ety. Evaluation: determined that no; y, ",

'unreviewed safety or environmental-questions are involved.

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