ML20033H172

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Mar 1990 for Big Rock Point Nuclear Plant.W/Undated Ltr
ML20033H172
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/31/1990
From: Beckman W, Jeanne Johnston
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9004180321
Download: ML20033H172 (6)
v • d • e


Text

.

e-

'~

4 y,.

Consumers Power

" a= ' Back=aa Plant bfanager POWERMG RIENNEAN'E PRDGRE55 Big Rock Point Nuclear Plant,10269 US 31 North, Charlevoix, MI 49720 1

I Nuclear Regulatory Commission j

Document Control Desk Washington, DC 20555

.j Dear Sir Enclosed please find the statistical data for the Big Rock Point Nuclear i

Plant covering the period

.I I

Sincerely,

/

ffW W L Beckman i

Plant Manager Enclosures i

Administrator Region III. Nuclear Regulatory Commission cc:

DRHahn, Department of Public Health RCallen, Michigan Public Service Commission SHall, Michigan Department of Labor PDKrippner,-American Nuclear Insurers INPO Record Center NRC Resident Inspector Document Control, Big Rock Point, 740/22*35*10 DPHoffman, P24-ll?B KWBerry, P24-614B File j

9004180321 900331 PDR ADOCK 05000155

//

R PDC

'/

i i

MIO186-0667A-BT01 A CAG ENERGYCOMPANY

CONSUMERS POWER'.

COMPANY NUCLEAR OPERATICO DEPARTMDIT Unit Shutdowns and Power Reductions 1- "*

Report Month Docket Number Unit Date Completed by.

Telep 6 w-March 1990 55-150 Big Rock Point Plant April 1, 1990 JRJohnston.

(616) 547-6537 ext' 223' Method of Shutting Duration

'Down License Event Systp Componpt l

2 3

Number Date Type (Hours)

Reason Reactor Report Number Code Code Cause and Corrective Action to-Prevent Recurrence 90-01 03/01/90 F

0 hrs H

4-

.The #1 reactor feedwater pump tripped after the oil pressure trip switch was bumped. Prompt action by:

. control operators in tripping the #1 reactor recirc pump prevented a plant trip.' The #1 reactor feedwater pump was immediately restarted and the #1 reactor.recirc pump was returned to service per the operating prxeu m s._

90-02 03/20/90 F

0 brs h

4 The plant load was reduced to allow repairs to a thru leaking #1 reactor feedwater pump vent valve 03/22/90 (VFW-106). 'After repairs were completed the. unit.

was returned to normal power.-

3 4

2,,,,,,

_ Method:'.

Exhibit 'G = Instructions for -

I p

F = Forced-S = Scheduled A = Equipment Failure (Explain) 1.= Manual:

Preparation of Data Entry Sheets-B = Maintenance of Test 2 = Manual-Scram for Licensee Event Report (LER)

' 3 = Automatic Scram File (NUREG-0161)

C = Refueling D = Regulatory Restriction-4 = Other (Explain)

E = Operator Training and License Examination g

. F = Administrative -

Exhibit'l = Same Source.

G = Operational Error ~(Explain)

H = Other (Explain)

T IURM 3156 1-82

~

s

,m~.

.-.--.n.--.

a-..

'.Y

,.h.-,,

' ' ' ~ ~

f

_ ' 'j

_y i t

4

)

W ser '

e.,4 d

W -

4 4,

W W

W a--

y..

n..

1*-

4

j

_}-

"~

l m

i l

?

g!-

r i

l I

e i

4 f

-l.

. i i

.I i.

i i

}

i k

I I

I i

3 i.

n

(

).

l ooo o o'd o tr.L UU$$

N

'D

~

[if5 hd dddd

,u n u

. :n M3 i_

't;f ca g n -

i 1

NlY e

  1. k $_

l-i 99E 9999" 9

{- sr sag m e.,so a re 3

- u

.a g

,n L

l g

j 8'

i i

s j

t-1 l

2) 8 o

l W

l:

-y G

N E

b I

h 999 9 990kk k

kl-d e :: qop:asseo i,w a

, a r --

a j

pa i

g!

-!~

{ $

w -

t l

D l

l l

l e

i o

i 8 i

.l

[

B oor j

i 4 4,.)

1

' T i.

0 -

9l E!

6 1

R

a h

E I b

  • m i

3 e

i 4

m E

h..

I Sm.

5 "h*$g$

d

~55 pp 8

h.

hl loE WW l

2

+

s

.e-r

-y

-m m

c 3<

gw gES M"d B o ;- 4, 5 W S 8.

a

{

  • gs g

i e

3u' EI w

18 4 r *- s$f --u

-E.

ga B og"

@f E

0 e

2 g

a Br,.5lWW di i yE we BE9w 5'

-g s

8" ggt "E

5.- E

,e>

ti- ~ a 8

b X

5:!

z 5t

'WE W*

m68,282i" g

s.

ww-m ui.'

I ruC

.W E-IJJ gal Zgo

, d { '{ d" d g IU Be8dfli338 C*W 6 5

Egggtr gg[-

1 85r. *. -g gg;8 a gat;S$i ese ar Ea a

h6ENE gW N 8

. m gge w'

"E e

ab s"bes

- I 'e ss' me ese 1

EIl 2

.5f." ed*

uen %"! u-u b

bub

.a sp legse s

tten ss h a se su sse s b

AcMA*l

'*f ddi idi dd* $dtld f\\

d

.--.~..... m.....................

6

................,4,... j

e> + n w

,,/

P-My M G.

+

~. - -

.; t ;,77,--

, r Q;

, 3 gy!yy;-

y;,,

u r

'p:

9ef e!-.

..a..,.

9 w.w a = u-s um

!?

U, AVEPACE DAILYL FUWEdH1 Win M}iWIN)-

(03/90L<:

? CYCLE"l2W p,i,w M.DNYi 2

f 31 Ji

[196$04?

159229:

eI~'

12(

m""

,;223.'71

'68.005 m.1. _.. -

f_. o_. sq 1 r

7

=

3 q,-

.;,22 3,og t *

-67466e

~

1

~

/224iOOL

53 67 W4 e; -

'22g ; gg '-

' 43. 47_;_2.2 R [' '

7; 225;373

6S i O2.

y_

7e :

L224.62

68.07
-

y yy,

'n a

_ _. _.._ _a _ a_,

- &_ c_ _ n '

,z

/

o.

C' l10."

' 223.75.=

!68;013 y'

.1is i223.83.

E67 i 67-3-

qc w..y t

37_ g 3 y, _

',' ?,

11 3s

'1220154;

67i32'

,t iW L14;, '

~

219146T 67.08.

4 4

., 9^

ir'

'220_00' 47.4E" Ol' 1161

223i29N

!67.54; b

'17 2224i62

,3 f 69i261 m

2w 22g 00

.s7. 93 ;.2++

w:: :w.w --.

1.

119

=222 S7-

.67 55-N

'l20

'218129' l66.32:

mr su

' < e_ v... u s.

e 7. 5,p-(,

22 1225.46i

..67.97J F

23

-225.04 68.35'

?

_29-

  • 23.42- ---

- :47 92:2 -,

. a --

' 25l 222i25 67464-26 223.42 67483 27

??Ei97^

6S;50 28-225.54

- 68 a 38.-

29 226.'67 68.87-

2W

'y:

.~.ng.y g

_Sg,$3 M'.

- 31 :

224.62 68.35'

..3

.g.

' 31

,~

32 tt

,.s.,.x Aa -,-

7

_ _ ~ - -

-3

., 35 :

' 35 [

q

-D f

5!

2

--.i

-]

~:D I

'c49

_ '. gf.

I 43

. (4

.- 3

- 4}

4&

.~. ->

a.-

,-Y AD

-.-~

f A

N

.d 4

JM1 -

]

'4 Id u.1

. ' $1

.)

~ * - ~

6

. i:.; - ~.....

.,,~%.~

,.n_

. =.

I

.q Refueling-Information Request l

~

l'. --Facility name:. Big Rock. Point Plant 2.

Scheduled date for next refueling shutdown:-September, 1990

3.. Scheduled date for restart following shutdown: October, 1990'

)

4.. Will refueling or: resumption of-operation thereaf ter require a technical specification change or~other license amendment?

No If.yes, explain:

1 If no, has the reload fuel design and core configuration been reviewed by Plant Safety Review Committee to detennine whether. any unreviewed -safety ~

v questions as associated with the core reload (Reference 10 CFR, Section

[

50.59)?- No If no review has taken place, when,is it scheduled?

Next outage 5.

Scheduled date(s) for submittal of proposed licensing action and supporting,information:

i 6.

Important licensing considerations associated with'. refueling, eg, new or different fuel design or supplier, unreviewed design or performance l

analyais methods, significant changes in' fuel design new operating-l procedures:

l 7.

Number of fuel assemblies in: core 84; spent fuel storage pool 254; new I.

fuel storage 0.

8.

Present licensed spent fuel' storage capacity: 441 l

Size of. any increase in licensed storage capacity that has been requested l

l, or is planned-(in number of fuel assemblies): 0

- t i

9.-

Projected date of last refueling that can be discharged to spent fuel pool a

assuming the present' license capacity:

1995 i

l

}i10886-0993A-BT01 BRP029 06/01/86 m

+

1 e

a

. n - ~J '

-. l y.

FORM 16.3.H Operating Status Report - Nuclear _ Regulatory Commission 4

-Prepared by:,

iv2a Date:

M

/,988 -

Reviewed _by: h Date: M Z[9()

(Reactor Engineer or Alternate)

Copy'to b'e sent to the following by the seventh day of each month:

cNuclears Regulatory >Consnission' Document *ControP Desk Washington, DC 20555 Administrator Region III - USNRC 799 Roosevelt Road Glen Ellyn, IL 60137 DRHahn, NFEM Division of Radiological Health Department of Public Health 3500 North Logan Lansing, MI 48914 RCallen.

Michigan Public Service Commission PO Box 30221 Lansing, MI 48909 Records Center INPO Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 Robert Aben, Assistant Chief Bureau of Construction Codes Michigan Department of Labor 7150 Harris Drive, Box 30015 Lansing, MI 48909 American Nuclear Insurers Att PDKippner The Exchange Suite 245 270 Farmington Ave Farmington, CONN 06032 Hean, P26-117B Routing Copy:

KWBerry, P24-614A HRSnider, P21-129 MEWorsham, P21-129 GBSzczotka, P21-135A NRC Resident Inspector - Big Rock Point Document Control Center - Big Rock Point DCC 740*22*35*10 (740*22*10*04) Cross Reference MIO385-0458A-BT01 16.3.3 - 17

)

Retrieved from "https://kanterella.com/w/index.php?title=ML20033H172&oldid=4585136"