ML20033F359

Monthly Operating Rept for Feb 1990 for Hope Creek Generating Station Unit 1

ML20033F359
Person / Time
Site:	Hope Creek
Issue date:	02/28/1990
From:	Brennan C, Hagan J, Loeper S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HSE-90-066, HSE-90-66, NUDOCS 9003200164
Download: ML20033F359 (12)

Text

'

'.L. O PSEG Pubhc Service Elecinc and Gas Cornpany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station L

March 15, 1990 HSE-90-066 U. S. Nuclear Regulatory-Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 L

DOCKET NO. 50-354

.In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for February are being forwarded to you with the summary of changes, tests, and experiments for February 1990 pursuant to the requirements of 10CFR50.59(b).

Sincer y yours, g

J J. Ha 'an Genera anager -

Hope Creek Operations

% RAR:ld i

1 Attachment 1

C Distribution 1

/6V

/

The Energy People it g

\\

- {,DR ADOCK0500g3]4 F}

9003200164 900228 es omsvotee

y~,.

s,

..J.'

I T

.e

'l

.1

+

-j c.

INDEX m

l 1

p..

NUMBER J

b~,

SECTION

. OF PAGES

.j

. H 1

JAverage-Daily Unit Power Level.........................

1 l

Operating Data Report..................................

2'

)

]

V Refueling Information..................................

1

[,

' Monthly Operating Summary..............................-

1 Qi.;

Summary of.. Changes, Tests, and Experiments..............

5 i

t

.i p..

g-t r.

1 A-

.t:

I i

i

'{

?

m.

f 1

f

't 4

i

'l a

[I

'f l -(

l.

1 6

C lf i.

m

, ' -',.r

,,+---.r.

...n,-.

,---.e-

,..., +.,

nv.--

.ne

.--.e.

e

..-..s,

p._q,_

AVERAGE DAILY UNIT POWER LEVEL DOCKET No._ _50-354 3

UNIT

_ Hope Creek j

+-

i DATE 3/15/90 COMPLETED BY

__S._Loeper o

i TELEPHONE (609) 339-5257 i.

HONTH

_ February 1990

['

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-

- ( MWe-Ne t ).

(MWe-Net)

- l'

-1014' 17 1021

[

t 11 2'

997 18 1028-t i

3 1026 19 1024 i

g L

f 4

997 20 1_023 t

h f

5

-1017 21 1012 i.

.6 1034 22 1037 7-1018 23 997 i

8 1054 24 834 l

9 980 25 1021-L-

10 1010 26 1_019 11 1030 27 1007 12-1023 28 1046 13 1028 29 14 1032 30 11 5 1035 31 i'

16 977

-s l

G e

e

(

- ~,,

r OPERATING DATA REPORT DOCKET NO. _50-354 UNIT

_ Hope Creek DATE _3/2/90 COMPLETED BY S. _ _Loeper TELEPHONE (609) 339-5257 OPERATING STATUS 1.

REPORTING PERIOD February 1990- GROSS HOURS IN REPORTING PERIOD 6 7 2___

2.

CURRENTLY AUTHORIZED POWER LEVEL-(MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1031 DESIGN ELECTRICAL RATING (MWe-Net) 1067 3

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net)

None 4.

REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE 5.

NO. OF HOURS REACTOR WAS CRITICAL 672

_1278.2

_23,039.7 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 7.

HOURS GENERATOR ON LINE 672

_1257.5

_22 608.7 2

8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH)

_2,145,587 3,942,937

- 70,899,313_

10.

GROSS ELECTRICAL ENERGY GENERATED (MWH) 709,020

_1,297,240__ _23,453,503_

11.

NET ELECTRICAL ENERGY GENERATED (MWH) 680,313

_1,241,204__

22,397,753_

12.

REACTOR SERVICE FACTOR 100 90.3 82.3 13.

REACTOR AVAILABILITY FACTOR 100 90.3 82.3 14.

UNIT SERVICE FACTOR 100_

88.8

__80.7 15.

UNIT AVAILABILITY FACTOR 100 88.8 80.7 16.

UNIT CAPACITY FACTOR (Using MDC) 98.2 85.0 77.6 17.

UNIT CAPACITY FACTOR (Using Design MWe) 94.9 82.2 74.9 18.

UNIT FORCED OUTAGE RATE O

11.2 5.9 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:

N/A m.

p OPERATING DATA REPORT.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-354

-UNIT

__ Hope' Creek l

,.'r f

DATE _3/15/90 COMPLETED BY

..S.Loeper

[

. REPORT ~ MONTH February, 1990 TELEPHONE (609) 339-5257 r

METHOD OF I

SHUTTING DOWN THE H

. TYPE-REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO, DATE S. SCHEDULED (HOURS)

(1)

POWER (2)

COMMENTS

r NONE

}L i

6 1 'i ef..

v

,f 1

5

' i

SUMMARY

I

+

g pi,,,_

g-REFUELING INFORMATION COMPLETED BY: _Chris Brennan DOCKET NO: 50-354 UNIT NAME: Hope Creek Unit 1 DATE:'_3/15/90 TELEPHONE: 1609) 339-3193 EXTENSION: N/A Month February _1990 1.

Refueling information has changed from last month:

YES NO X

2._

Scheduled date for next refueling:

01/19/91 3.

Scheduled date_for restart following refueling _03/05/91_

4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO X

B)

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X

If no, when is it scheduled?

02/01/91 5.

Scheduled date(s) for submitting proposed licensing action: N/A 6.

-Important licensing considerations associated with refueling:

-Amendment 34 to the Hope Creek Tech Specs allows the-cycle

-specific operatino limits to be incorporated into the CORE i

-OPERATING LIMITS RERORTj_a___ submittal is therefore not b

-required.

.7.

Number of Fuel Assemblies:

A) Incore 764

.B) In Spent Fuel' Storage (prior to refueling) _496 C)'In Spent Fuel Storage (after refueling)

_744 8.

Present licensed spent fuel storage

. capacity:

1290 Future spent fuel storage capacity:

4006

.9.'

_Date of_last refueling that can be discharged to spent fuel pool assuming

.the present licensed capacity:

03-05-91 1

7:

1 l

t..

i E

i

+

HOPE CREEK. GENERATING STATION NONTHLY. OPERATING

SUMMARY

FEBRUARY 1990

'h i'

Hope Creek entered the month of February at 95% power; the limitation was due to the 2C Drain Cooler being out-of service..

.After consultation-with General Elcetric, power was raised to-98%

l on! February 6.

.The: unit operated throughout the month without i-experiencing any shutdowns or reportable power reductions.

On i:

February,28,.the plant completed its 49th day of continuous power-l E

-operation.

I i

')

I i

f a

's b

9

'N 4

D l

I Ii y

L

c- ;/,

s-.ca - m ~g '., a t

p4

- q

ai fS,d;g s g - :yp 3.,

"g

.y# :

i i

1 a

r y

~.

w

, 1

.-=y:

1

. c 9 7. < f,.,

..s, i

i1 s.

h A

f # 4 g

j'N 'k i.

4

,,.s. -

q j

t,;._g g;

. ;p:.

S t;-;

if & qr P;.-

*.^ -.

' 1

% m;;

T SUNNARY OF4 CHANGES, TESTS,'AND' EXPERIMENTS

,g, v

i ws r

"y ;n, g

,w; t

y a

s

- FOR THE HOPE CREEK. GENERATING STATION-

-yl

. I f

i-q._ s 1

7)L 4

s FEBRUARY 1990*

.s, s

T 1

.\\.

.p sr.

• T I

_j,_

J '

3 5' -

T*

1.,'

5i g

n I

J -4"-

ir.

43p.e

.s i

q s

1.

, ~...

y.

I g' 4

-. $' i.

?

LI9 ' k k.

O, l (,j,..

r

.]

,'I 1

s mt e1 e44

-?

t.l j

?

M. ~.

': h i.A [f s-g' 4.)

5 t-t 0

.]

I

.,4 br

']

J

o., W--

,.3,-

_ g t

v.

+

b, '!,4 Y

., -m,-

g4. k I

1 A

t i

k.

?

i'...

$N i.

,f.',_

f/,

3 g\\' l s

9'-

_d g'.

g'_-

D i

s 7

1.

s A

-I f

it

+

! ' j,'

-.E N'y('

n.

't

l

^^

r

+L*y 1

e

- i?

s Av 4

k-g

+

• t",

J

-. 7 L f.g

,--J / 1 -..

L r

y j # {-

tdI-(

b

The_following Design Change Package (DCP) has been evaluated to determine:

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 2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3) if the margin of safety as defined in the basis for any technical specification is reduced.

The DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.

The DCP did not change the plant effluent releases and did not alter the existing environmental impact.

The Safety Evaluation determined that no unreviewed safety or environmental questions are involved.

1 DCP Description __ of _._Desion_ Chance Packace 4HM-0124 This DCP installed a door between the Radwaste Building Controlled Instrument Shop and the Radwaste Building Uncontrolled Instrument Shop Annex to allow the Radwaste Building Controlled Instrument Shop to be outside of the Radiological Control Area.

This room was originally scheduled to be used as a hot shop, but was never used for that purpose.

l I

"The following Temporary Modification Requests (TMR's) have been evaluated to determine:

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 2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3) if the margin of safety as defined in the basis for any technical specification is reduced.

The THR's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.

The THR's did not change the plant effluent releases and did not alter the existing environmental impact.

The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

1 l

5

l

., Safety Evaluation Description.ot Temporary Modification Reauest- 029 This Safety Evaluation authorized a revision to the Temporary Modification Administrative Procedure.

This revision provides

. administrative control, other than a TMR, for temporary floor drain ~ plugging.

Temporary floor drain plugs will have a tagging request associated with their installation.

A_ monthly audit will be performed on plugs which will verify that the plugs are in place, properly installed and tagged.

The need for continued use of the plugs;will also'be reviewed monthly.

Precautions will be taken to ensure ECCS divisions.are maintained by_ allowing temporary floor drain plugs to be used in only one ECCS division at a time.90-036 This TMR rewired the control circuitry of the Reactor Core Isolation Cooling Isolation Valve Bypass Valve.

Rewiring the circuitry will allow the valve to operate correctly and will allow' full closure to be verified.

This THR i

was necessitated by a ground in the circuitry.

[

90-044 This TMR added a jumper to the High oil Temperature Switch in the "A" Control Room Water Chiller.

The jumper will disable the High Bearing Oil Temperature trip; but will permit-the chiller to-operate until replacement ~

parts _can be installed.

Equipment Operators will' monitor the oil temperature as a compensatory measure..

l e

l l

l

- - - -