ML20042C026

Monthly Operating Rept for Sept 1981

ML20042C026
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	10/02/1981
From:	Amstutz S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20042C024	List: ML20042C023 ML20042C026
References
NUDOCS 8203300088
Download: ML20042C026 (7)

Text

"

GF1YBOOK OPERATING DATn REPORT DOCKET NO. 50-155 DATE:

10 /

2 / Of.

BY:

SUSAN AMSTUTZ OPERATING STATUS PHONE:

616-547-6537, EXT

t. UNIT NAt1E:

BIG ROCK POINT NUCLEAR PLANT NOTES:

~

' Ext.'160"

~

$. REPORTING PERIOD:

9 / 81

3. LICENSED THERMAL POWER (MWT):

240 W NAMEPLATE RATING ' (GROSS MWE)T--~~75 -

~-~

~-

- " - ' ' ~ ~ - -'

f. DESIQCEt.ECTRICAL RATING (NET MWE):

72

5. MAXIMyM' DEPENDABLE CAPACITY (GROSS MWE):

69.0 P; MAXIMO$-DEPENDABLE CAPACITY (NET MWE)'

65.0

~ ~ ~ ~ '

~-

3. IF CHAl GES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:

_k>

r r

1 Ic p i MER L

/EL~TO'WHICH RESTRICTED;IF ANY (NET MWE).

65.0

~ - ~ - ~ ~

- ~~ ~ - ~-- ~ ~

p..

SONS 70R RESTRICTIONS, IF ANY:

i.

<h l

THIS MONTH YEAR-TO-DATE~~

~

~~' CUMULATIVE i

l. HOURS IN REPORTING PERIOD 720.0 6551.0 162250.0 i

T NUMDER OF HOURS REACTOR WAS CRITICAL 720.0 5000.4

- ~112893'.5-REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.,0

4. HOURS GENERATOR ON-LINE 720.0 5731.0 110661.8 5T UNIT RESERVE SHUTDOWN HOURS' O.0'

-~ ~ ' " - ~ OTO ~~~ -

"-~-" -

~ ""07 0-'

%. GROSS THERMAL ENERGY GENERATED (MWH) 140732.0 1192029.0 20714030.0

7. GROSS ELECTRICAL ENERGY GENERATED (HWH)'

45654.0 364401.0 6529490.0 a.~ NET ELECTRICAL ENERGY GENERATED (MWH) 43094.3

' ~344006T6'"

~~~~"61~77796!5 -

he..UNITSERVICEFACTOR 100.0%

87.5%

60.2%

UNIT AVAILABILITY FACTOR 100.0%

07.5%

68.2%

f. UNIT CAPACITY FACTOR (USING MDC NET)'

92.1%

~

~ 00.'9%

~ - ~~~ 56'.4%

. UNIT CAPACITY FACTOR (USING DER NET) 83.1%

72.9%

52.9%

c.

UNIT FORCED OUTAGE RATE O.0%

0.9%

20.1%

g

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

F. IF SHUT DOWN AT ENDROF REPORT PERIOD,' ESTIMATED DATE OF STARTUP:

' ' ~ ~ ~ ~ ~ ~ -' ~ - - "

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DAY A V E N A L,t. DAILY VUwttunwi>

' nw:.ru 7 vie i,

208.83 60.20 2

209.42 60.27 i

3 208.?6 60.27 2Ou.vu 60.13

- p 5

207.25 60.28 6

<206'.21 60.08 7

205.62

-~ 57-5 8-8 204.50 59.04 3

9 203.46 59.00

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am 11 201.42 58452 s

l 12 200.83 58.31 iT 19y.6/

ar.9u 14 200.00 58.06 l

15 203.71 58.80 io zuz.iz an.uo

.s 17 202.04 58.75 i,

i8 201.71 58.89 t ?-

206.56 57 58 20 205.79 59.75 21 205.42 59.57

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2(76 3T 57.73 23 206.96 60.18 24 21i.52 6i.25

.:T 41a.1i T>i~59

?6 213.42 61.83

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e Refueling Information Request 1.

Facility name:

Big Rock Point Plant 2.

Scheduled date for next refueling shutdown:

January,1982 3.

Scheduled date for restart following shutdown:

April, 1982 4.

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

No If yes, explain.

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 If no review has iaken 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 supplier, unreviewed design or performance ana-lysis methods, significant changes in fuel design, new operating procedures:

None 7.

Number of fuel assemblies in: core 8h spent fuel storage pool 108 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):

2h8 9.

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

1983

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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS f

This report should describe all plant shutdowns during the in accordance with the table appearing on the report formk report period. In addition,it should be the source of explan-If category 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi.

LICENSEE EVENT REPORT #.

Reference the applicable ficant reduction in power level (greater than 20% reduction in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertammg to the outage or power redu: tion. Enter the first four parts (event year, sequential should be noted, even though the unit may not have been shut down completely. For such reductions in power !cvel,

'ePort number, occurrence code and report type) of the five l

the duration should be listed as zero,the method of reduction Part designation as described in item 17 of instructions 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 may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outa;;e or power reduction.

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

NUMBER. This column should indicate the sequential num.

the positive indication of this lack of correlatic,n should be ber assigned to each shutdown or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in whi:h the outage or power reduction begins in one report period and ends in another, reduction originated sh"ould be noted by the two digit code of

~

an entry should be made for both iaport periods to be sur Exhibit G -Instructions for Preparation of Data Entry Sheets all shutdowns or sapificant power reductions are reported, Until a unit has ac;t.eved its first power generation, no num.

for Licensee Event Report (LER) File (NUREG-016!).

ber should be assigned to each entry.

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

ted XX. The code ZZ should be'used for those eventswhere MTE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year month, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770314. When a shutdewn cr :i;n!'ha.! power reduction from Exhibit I - Instructions for Preparation of Data Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-0161)/

be made for both repa, periih to be sure all shutdowns using the fo!!owing critieria:

or significant power reductions are reported.

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

duled." respect!ve!y, for each Butdown or s!gnificant power B.

If not a cornponent failure, use the related component:

reduction. Forced shutdowns include those required to be e.g., wrong valve operated through error; list valve as initiated by no later than the,<eekend fe,thwing discovery component.

of an off. normal condition. It is recognized that some judg.

ment is required in categorizing shutdowns in this way. In C.

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

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 which fail, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Selfexplanatory. When a shutdown extends Components that do not fit any existing code should be de.

beyond the end of a report penod, count only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the report period and ptek up the ensuing down time events where a component designation is not applicable.

In the follow, g report periods. Report duration of outages m

rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fashion to amplifyor

, tor 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 specific cause for each shut.

down or significant power reduction and the immediate and REASON. CateForize by letter des.ignation.in accordance contemplated lone term corrective action taken, if appropri.

wnh the table appearing on the report form. If category F1 ate. This column'should also be used for a description of the must be used. supply brief comments, major safety.related corrective maintenance performed durin;t the outage or power reduction including an identification of METilOD OF SHUTTING DOWN Tile REACTOR OR the entical path activity and a report of any smgle release or REDUCING POWER.

Categorite by number designation radioactivity or single radiation exposure specifically associ.

ated with the outage which accounts for more INote that this differs from the Edison Electric Institute of the allowable annual values.

IEEI) definitions of " Forced Partial Outage" and " Sche, duled Partial Outage." Fin these term >. hl.1 uses a change of For long textual reports continue narrative on separate paper 30 MW as the break point. For larger power reactors.30 MW and reference the shutdown or power reduction for tha is roa small a change to wariant esplanation.

narrative.

r

GREYBOOK OPERATING DATA REPORT DOCKET NO. 50-155 DATE:

10 /

2 / 81 -

BY SUSAN AMSTUTZ

~ 0PERATING STATUS

~

~ ~ - ' PHONE:

616-547-6537, EXT 1 UNIT NAME:

BIG ROCK POINT NUCLEAR PLANT NOTES:

Ext. 180 REPORTING PERIOD:

8 /- 81 LICENSED ' THERMA'L POWER (MUT)T- '240 "" " ' ~ ~ ' -

~"

~ ~ ~~

" --~-

~

~ ~~--

~~~

' NAMEPLATE RATING (GROSS 11WE):

75' DESIGN ELECTRICAL RATING (NET MWE):

72 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE)-

69.0

~

~

MAXIMUM DEPENDABLE CAPACITY (NET MWE):

65.0

'IF CHANGES OCCUR.TN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:

5 POWER LEVEL TO WHICH RESTRICTED,IF ANY (NEl HWE):

65.0 REASONS.FOR RESTRICTIONS, IF ANY:

l e

THIS MONTH YEAR-TO-DATE CUMULATIVE HOURS'IN' REPORTING PERIOD

~"'

~

~

~" 744.0'

~~'

~ ~' 5831. 0' ~ ~" ~ ' ~ ~ ~ ~

i61'538T0-2 NUMDER OF liOURS REACTOR WAS CRITICAL 744.0 5000.4 112173.5 2

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.6 7 HOURS GENERATOR ON'LINE

~744.0

- ~ ~

~- 5011.0' 109941.0"-

a UNIT RESERVE SHUTDOWN fl0URS 0.0 0.0 0.0 GROSS THERMAL ENERGY GENERATED (MWH) 157501.0 1044097.0 20565290.0 7" GROSS ELECTRICAL' ENERGY-" GENERATED ~(MWH) 401'14.0'

"- - - ~ ~~~3107 A7 ; 0-

- 6483036.0

~~

. NET ELECTRICAL ENERGY GENERATED (MWH) 45430.4 300912.3 6134702.2 UNIT SERVICE FACTOR 100.0%

85.9%

68.1%

7 UNIT AVAILABIL~ITY FACTOR ~ " ~ ~'"

-~

-" ' 'i 0 0 ; 0 % ' ~ ~ ~ - "' " - ---" ~ " ~ ~ 8 5. 9 % ~ -

- ' ~ ~ - -

60;i%'

. UNIT CAPACITY FACTOR (IISING MDC NET) 94.0%

79.5%

56.2%

UNIT CAPACITY FACTOR (USING DER NET) 84.8%

71.7%

52.7%

7 UNIT 70RCED' OUTAGE RATE ' ~ ~ ~ ~ ~ "

- 0. 0 % " ' ~~ ~ ~~ - ~ ~ ~

T. 0%~ ' - - ---'~"~ ~ ' ~ ~"- 2 013% -

s. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE,DATE, E D U R AT I O N O F~ E A CHT ' "-- " ~~~~ '"- -

IF-SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP m

m

• ' DAY AVERAGE DAILY POWER (MWT)

(MWEd)

( 8/81) 211.75 62.13 1

2 218.54 61.72

. C.&5 61.43 g,e; ;. '

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4 213.42

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3 5

213.37 61.32 1;,..*,

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215.83 61.77

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215.62 62.10 8

215.29 62.12 9-2D1334 6i-BD l' >

10 201.25 61'04

'r ii 212.08 60.67

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n 12 2T3.75 60.95 l' n 13 212.71 6'). 75 n

14 215.50 61.24 ns 15 212.62 60.77

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. '? n, 16 213.12 61.22 o

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n' 17 213.62 61.42

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n 16

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' er 19 210.92 60.68 n

20 209.67 60.64 m

21 212 8o 61.,50

?n 22 210.92 60.73 Y

23 211.12 60.60 24 2TT. 4'2 60.UY n

'? n 25 210.33 60.58 26 209.75 60.42 n;

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' a 31 209.04 60.36

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r A,' OPERATI!!G STATUS REPORT - NUCLEAt. P.EGULATORY CO OIISSION Prepared by .k b%d; Date /0-06-h Reviewed and Approved by bbf"1CA SfxCf ,__ Date /O //A [$(( /~' (Reactor Engineer or Alternate) Copy to be sent to the following by the seventh day of each month: E 0ffice of Management Information and Process Control Documents Management 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, Michigaf 48914 4. Ron Callen Michigan Public Service Commission P.O. Box 30221 Lansing, Michigan 48909 5. Routing Copy to: RBDeWitt - P26-ll7B DPHof ftr.au - P24-115 JJDellas - Pll-22SB RLRosenfeld - P24-402 LPhillips - P21-327 6. Document Control Center - BRP - 740*22cl0*04 7. File Copy 8. Resident NRC Inspector - Site 9 Records Center INPO 1820 Water Place Atlanta, CA 30339 ~ A 1' -}}