ML20042B360

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jul 1981
ML20042B360
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 08/04/1981
From: Amstutz S
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20042B355 List:
References
NUDOCS 8203250245
Download: ML20042B360 (6)


Text

}

o 4

)

J.m

  • 6VL,

.-I dally Pt..c.i, ' i1W1 s t rn G )

7, ' J '. )

y i

206.75 59.17 2

204.07 59.87

)

x ong

,v,

,?,

4 i-4 206.62 60.29 5

212.08 6i.i2 y

6 215.50 61.85 7

212.62 61.10 0

210.96 60.60

)

9 212.08 60.35 10 216.17 61.70 11 216.67 6'.72 y

12 217.17 62.04 4,,

,4 o.)..a. c...

4n a

2 x r,~,

y

e. o sh 7

oi?

f.: =, -

9 { Q.>. .

.s'.',-?. t r.

y 1S 2te.

c.

i >

216.27 61.97 20 2 i 5. 5 41 6i.57 3

6,.. or a.

9.1 9, c-n 22 215 04 61.91 23 215 79 62.04 3

24 219.04 62.90 25

.' i O 'o 62_4?

)

217. 5)

M ;o 27 218..27 63.23

. 9 *f. t')* "s

[ ~,1,

  • )'.')
  • )

.w 29

~

.6 63.41

)

36 9 4. M'.

7.C.

./.. "m). D. N 31 215.12 62.53

)

)

8203250245 810804 PDR ADOCK 05000155 3

R PDR

N

- us N.. c,.c H

4 F-T Cb O o-O is eq to tw,N q

,-q C

')

C4

', '.. v-cisc.c.c y,If,e; e.

I

,'-T

& W c.;

e-H-. ; 's 9

B a,.-

r;~.

> in s in I

9-o o to O

'y -0 D

veO e c

'.. to o

j O

O 9 'O rn

~ r4

.N,+>

+

N

}

O' i v. N

% ;e i

ltt'ut Lt H :'

.?.

2.*

O O

bi NNNNM

~1
n t,2 g

p q, r o. o o o O c,0., c. g Cc c4 Q.

11' c

id C

i

  • C C I-O -Cit 9 t9 t9 M f* Cb v-ir j

i C to C

e T9 b- 03 fD Tw $

i l

O 3 to C4 th % T i

H

!A T T

4 O !ft l

I CO f' in 1A H

M CO C4 c4 i

Lf1 O

q Ld i

O t-LA

^

O k.

  • C O

Ld O

Z n'

C til F-i--

h.

c.

td M

Gi h:

It' O

O O

W-

.t X

NNNNN

}.'

M H

O r'I i-O O C O O O O C3 O O.!'N O O

C Q

i.

Z s

U O

O

.' 7 O T O 9 T i" O O L1 tn D M

2 i

E vv v

is (b e-O O S-OJ T

e')

l-r-ts O<O v

M is.

V.i M

o co $

D O

H 4.T T D

I I

Ld v-Y p

5

[--

21 C

1 A

tt Q

N IJ A

Lt A

Cd G G F-O r--<

til 4

=

r 4

C:. ?p m A

b--

b-C e

H bl n'

<t M

ht O.

H

- A (N

Y t

p e..

H

i..

M

. O Z

r-.

^

Z H

y I

M Ld v

H

]

-3^

.!C

r-(L

.3 C

J

^rI

^^

H Q

  • i.

C

  • ?t a Iv2 F-H Z

O G:

Q'

.I

t.i O

3 Z

W Id a

H id c

L !

f,.

H H

EAv

'Z. Z E

C' n.

W 3CHe-v bJ 111 O

_1 I,; t.d O *?:

H

.-- O O O'

'O G-2 O

4 '1.C tr:

i;I C tr to O < [d A *B

.v.

}-v Q

H O Q*

tif O' H IR F--

v O

7. - *

~i.d O e, n

L- !.1<

X Y

i

. >. +

ta O

., <I* Z f2:

  • '! O lei

<3

'i L

(r:

CI tr' Q'Id LU ZZ l."

v t

1

4 3

3 td u Z

,: H id ul O i.] O 4:

fa M O

2.*. CZ id Cd M M Q'

Z

.Z I., 7 e c u.

(d Z H C ' 3 Ld I k ' >- 0 O D D Id bJ n 't a

CC t; H u. O..I d' O 0: O O Z OO H v v l--

b_

' r) s.: s 1 -.

f.' C t1 H

ill H A H Z n' >-

O 4

O O

.< o C 3 f. !

Z F-

n. O F

..J 2 >- l'.I O C tr D. T/

r.1. - 0:

f. )>O C ~3 i C O Z Q' Cf L O O C

Q i:: i. ' e i H

O i:3.; Z Ci (L' id td O F 1 - b.!

ld

'I i

Z

'2 24 M O !- l t Z F- >- O r.*i

..f

' '1 M

2 a.

H D " I b.! O F-E C C D

D.

t r. < :,, O a

H 1 !!J CC % !d q q F r b.. E. H f-t H

1--

n (; O O DJ

&: 1

>OM O J Li

_.I D

!1f C

'c i.

.;..;)

a.

uH

..J M C HH>O "C

el ;t i

' L! * *: U: C M f 3 t,i Fa ! - *-

O

'f-f. i O_

.! L'.

tu

!. I 2 D.

Y. F - H ! J <, : *C

-^

IT itj. I E'2 t e., O CJ

' J W QC C ' O M t..J. ' f * :.-1 O

a.

i r c. / o

.- ti.

,Z d!:t W i- > ?-i c r. )

21 s

~

9e

.i-

.s:1

..:1 J.

i m'

. 'i.

1-1 a. ( 2 > - I. C

[J r.

7 O

t t.

  • -3t

-fi It C

!C. '.

. i t

"a

.g
- "

.4 i

..... 'i.

7.; { 1, I-I M

s a

(a 8 2 :

, =

J. W... )..2

.' Z,

.1

.I t

6.

  • 4-t s
  • s e

i

(

1,9 i)

I' g

'J wa=

1 3

Refueling Information Request 1.

Facility name:

Big Rock Point Plant 2.

Scheduled date for next refueling shutdown:

February, 1982 3.

Scheduled date for restart following shutdown:

April, 1982 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

No If yes, explain.

e If no, has the reload fuel design and core configuration been reviewed by Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR,Sec.50.59)?

Yes 0

If no review has taken place, when is it scheduled?

5.

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

None 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or sup: 1.ier, unreviewed design or performance ana-lysis methods, significant uhan.es in fuel design, new operating procedures:

None 84

spent fuel storage pool 108 7.

Number of fuel assemblies in:

core 8.

Present licensed spent fuel storage capacity:

193 Size of any increase in licensed storage capacity that has been requested or is planned (in number of fuel assemblies):

248 9.

Projected date of the last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:

193

UNITS!!UIDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report forra:s report period. In addition.It should be the source of explan.

If category 4 must be used, supply brief comments.

ation of signliicant dips in average power !cvels. Each signi.

LICENSEE EVENT REPORT #.

Reference the applicable ficant reduction in power level (greater than 20% reduction in average daily power 1:v:1 for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) f*portab!e occurrence pertainmg to tne outage or power reduction. Enter the first four parts (event year, sequential should be noted, even though the unit may not have been shut down comp!etely. For such reductions in power level, report number, occurrence code and report type) of the five l

the duration should be listed as zero, the method of reduction part desi; nation as described in item 17 of lastructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information :nay not be Cause and Correctise Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, since further investigation may be. required to ascertain whether or should be used to provida any needed explanation to fully describe the circumstanc.s of the outa;a or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NU51 DER. This co!umn should indicate the sequential num, the positive indication of this lack of correlation should be noted as not applicable (N/A).

.,er assigned to each shutdown or significant reductionin power for that calendar y:ar. Wh:n a shutdown or significant power SYSTEh! CODE. The systern in which the outage or power reduction begins in ene report period and ends in another, reduction ori;inated should be noted by the two digit code of an entry should be made for both report periods to be sure Exhibit G. Instructions for Preparat. ion of Data Entry Sheets all shutdowns or sitnificant power r: ductions are reported.

f r Licensee Event Report (LER) File (SUREG-0161).

Until a unit has acnieved its nrst power generation, no num-ber should be assi ned to each entry.

Systems that do not fit any existing code should be designa.

3 ted XX. Tht code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is nc applicable.

of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported COstPONENT CODE. Select the most appropr'ste component as 770314. Wh:n a :,h.th.,n cr :Dificant pcwer reduction from Exhibit i. Instructions for Prepstr. tion of Data Entry begins1.:9ne report period. nd endt in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG 0161).,-

be made for both repr peridd: :o be :ure all shutdowns using the following critieria:

or significant power r dumions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.

duled," respectively, fee enh shutdown or signific:ct power B.

If not a component failure, use the related component:

reduction. Forced shutdowns include tho:e required to be e.g., wrong valve operated throu3h errort list valve as initiated by no later than the we:kend following discovery component.

of an off-normal condition. It is recognized that some judg-ment is required in categorinng shutdowns in this way. In C.

If a chain of failures occurs, the first component to ina!.

general, a forced shutdown is one'that would not have been function should be listed. The sequence of events includ.

completed in the absence of the condition for which corrective ing the other components widch fa!!, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. S !f explanatory. When a shutdown extends Components that do not fit any exining code should be de-beyond the end of a report period, count only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the report period and ptc% up the ensuing down time events where a component designation is not applicable.

In the following report periods. Report duration of outages rounded to the nearest tenth uf an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours plus the hours the genera-RENCE. U:e the column in a narrative fashion to amplify or tot was on line should equal the gross hours in the reportmg.

explain the circumstances of the shutdown or power reduction, period

  • The column should include the sisccific cause for each shut-down or significant power reduction and the immediate and REASON. Categorin by !ctter des.ignation in accordance contemplated long term corrective action taken, if appropri-with the table appearing on the report form. If category 11 ste. This column should also be used for a description of the must be tad.supp!y br:et comments, major safety.related corrective maintenance performed during the outace or power reduction including an identification of; M F.Ti!O D OF SHUTTING DOWN Ti!E REACTOR OR the critical path activity and a report of any simjle release or l

REDUCING POWElt.

Cate;orite by number designation radioactivity or single radiation c.spmure speeshea!!> a:soci-ated with the outage which accounts for more than 10 percen/

INote that this differs imm the Edison Electrie Institute (EEll definitions of "Ferced Partia! Outace' and " Sche, of the allowable annual value:.

(

l duled Putn! Outap " fo: thex term >. I I I uses a change of For long textual reports continue nurative on separate paper 30 Siw a the break point Foi larp power reaerors.30 51W and reference the shutdown or pm.er reduction foi this is s.

3 mall a change to wanant esplanation.

narrative.

50-155 UNITSIIUTDOWNS AND POWER REDUCTIONh DOCKET NO.

UNITNAME.Itic Rock Point DATE.k! m + b.

1 o81 REPORT MONTil July, 1981 COMP!.ETED BY m A--+,+-

,,ELEPl!ONE.kJ6-%7-6s37 ext. 180

,5?

3

.5 1.icensee

[g Cause & Corrective No.

Date g.

3g g

,g g 5 Event g*g E'

Actica to Ey F

3E 5

7; p, =M Re; ort e in U Prevent Recurrence e

u 6

(

None

)

1 2

3 4

F: Forced Reason:

Method:

Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data U. Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C. Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D. Regulatory RestrietIon 4-O her(Explain) 0161)

E Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I Same Souree (9/77) ll Other (Explain)

'o OPERATING STATUS REPORT - FR'CLE/2 REGULATORY COBS!ISSION Prepared by L\\(

Date P/ L// St Date O[

[

Reviewed and Approved by (Reactor Eligineer or Alternate)

Copy to be sent to the following by the seventh day of each month:

ffice of ttanagement Information and Process Control Documents t!anagement Branch United States Nuclear Regulatory Commission Washington, DC.20555 2.

Region.III Directorate of Regulatory Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 3.

DEvanFarowe, PE Chief Division of Radiological IIcalth Department of Public Health

~

3500 N Logan Lansing,tiichigaf 48914 4.

Ron Callen

?!ichigan Public Service Commission P.O. Box 30221 Lansing, ?!ichigan 48909 5.

Routing Copy to:

RBDeWitt - P26-ll7B DPHoffman - P24-115

~

JJDellas - Pil-228B RLRosenfeld - P24-402 LPhillips - P21-327 6.

Document Control Center - BRP - 740*22*10*04 7.

File Copy 8.

Resident NRC Inspector - Site 9

BLavallec, Mgr Nuclear Safety Analysis Center 3h12 lii11 view Avenue 1

P.O. Box 10 :12 Palo Alto, CA 94303 b

4'-

.