ML20042B509
| ML20042B509 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/01/1982 |
| From: | Amstutz S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20042B508 | List: |
| References | |
| NUDOCS 8203250379 | |
| Download: ML20042B509 (4) | |
Text
GREYD00K OPERATING DATA REPORT 8203250379 820203 PDR ADOCK 05000155 DOCKET NO. 50-155 DATE:
2/
1 70 R
PDR BY:
SUSAN AMSTUT UI'ER(ilING STATUS PHONE:
616-547-6537,E UllIT FLAME:
DIG ROCK POINT NUCLEAR PLANT NOTES:
Ext.
~
'80' l
REPORTIllG PERIOD:
1 / 82 Due to a faulty reset switch on LICENSED THERMAL POWER (MWT):
'240 Channel #2, the reactor was manually
~-"
ilAliErl. ATE RATING (GROSS MUE):
75 scrammed on January 7, 1982, forcing DESIGN ELECTRICAL RATING (NET MWE):
72 us into shutdown condition. The MAX 1 tium DEPEllDADLE CAPACITY (GROSS MWE):
69.0 reactor went critical January 13, 1982.
~~~~
f1AX1MUti DEPENDADLE CAPACITY (NET MWE):
65.0'
~
IF CIIANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:
al-sa
. M,4 PUWER LEVEL TO Wi1ICH RESTRICTED,IF ANY (NET MWE:
65.0
-~ -
cr**(Apf., -f;t -d /
a
' M44.h REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YEAR-TO-DATE
- CUMULATIVE ll0URS IN REPORTING PERIOD-744.0 744.0 165211.0 NUMDER OF ll0URS REACTOR WAS, CRITICAL 610.0
610. 0 -
- 115712.5' REACTOR RESERVE SHUTDOWN 110URS 0.0 0.0 0.0 llUURS GENERATOR ON-LINE 596.8 596.0 113467.6 UNIT RESERVE. SHUTDOWN HOURS 0.0-
-0.0 0.0 GROSS THERMAL ENERGY GENERATED (MWH) 94045.0 94045.0 21240750.0 GROSS ELECTRICAL ENERGY GENERATED (MWH) 29370.0 29378.0 6692680.0 llET ELECTRICAL ENERGY GENERATED (MWH) 27292.7
- -27292.7
--6331036.7 3
UNIT' SERVICE FACTOR 80.2%
00.2%
60.7%
UNIT AVAILADILITY FACTOR 00.2%
80.2%
60.7%
-56.8%
UNIT CAPACITY FACTOR (USING MDC NET) 56.4%
56.4%
UNIT CAPACITY FACTOR (USING DER NET) 50.9%
50.9%
53.2%
UNIT FORCED OUTAGE RATE 19.8%
19.8%
19.3%
SiluTDOWNS SCllEDULED OVER'NEXT 6 MONTHS (TYPE,DATE, & DURATION OF EACH):
IF SI'IUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
l
.et
50-155 UNITSIIUTDOWNS AND POWER REDUCTIONj DOCKET NO.
nig neck Point UNIT NAME DATE f 2-07 " )
COMPLETED DY SRAmst~te blo-%.'-bM7 REPORT MONTil Jn-n""
. TELEPil0NE 1982 ext. 180 1
"t.
h{e.,
,]?
}
)Y Cause & Corrective Licensee 5 r, Action to No.
Date g
3g g
,Ejs Event p
Prevent Recurrence dI 5
jgg Report #
mU H
g 5
82-01 01-07-82 F
142.1 A
2 None IA c
l l
l l
l l
2 3
4 Method:
Exhibi: C Instructions F: Forced Reason:
S: Scheduled A Equiprnent Failure (Explain) 14!anual for Prepar:t!on of Data 114taintenance of Test 2-Manual Scram.
Entry Sheets for Licensee 3-Automatic Scram.
Event Repon (LER) File (NUltEG.
C-Refueling D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Zxamination 5
F-Administrative Exhib's I Same Source G Operational Error (Explain)
(9/77)
Il-Other (Explain) e e
L__
3 UNIT SliUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS f_
This report should describe all plant shutdowns during the in accordance with the table appearing on the report form:s 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 !cvel 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 pertaining to the 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 completely. For such reductions in power level, report number occurrence code and report type) of the five l
g the duration should be listed as zero,the method of reduction part designation as desenbed m item 17 of Instru:tions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Everc Report Action to Prevent Recurrence column should explain. The (LER) Fi!e (NUREG-0161). This information may not be Cause and Corrective Action to Psevent Recurrence column immediately evident for all such shutdowns, of course, sm, ee should be used to provide any needed explanation to fu!]y further mvestigation may be required to ascertam wh:ther or describe the circumstances of the outage or power reduction.
not a reportable occurrence was mvolved.) If the outage or power reduction will not result in a reportable occurrence.
NUSIBER. This column should indicate the sequential num.
the positive indication of this lack of correlation.should be ber assigned to each shutdown orsignificant reduc.tionin power noted as not applicable (N/A).
for that calendar year. When a shutdown or significant power SYSTESI CODE. The system in which the outage or power reduction begins in one report period and ends m another, reduction originated should be noted by the two digit code of an entry should be trede for both report periods to be sure all shutdowns or significant power reductions are reported.
Exhibit G. Instructions for Preparation of Data Entry Sheets f r Licensee Event Report (LER) File (NUREG.0161).
Until a unit has achieved its first power generation, no num-
.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 events where DATE. 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 COh!PONENT CODE. Select the most appropriate component as 770314. When a shutdewn er significaT ;ower reduction frem Exhibit ! - Instructions for Preparation of Data Entry begins in one report peried.md ends in another, an entry shou!d Sheets for Licensee Event Report (LER) File (NUREG.0161) be made for both rna periot to be sure all shutdowns usW the fo!!owing critieria:
or significant power reNions are reported.
TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.
duled." respectively for each thutdown or significant power B.
If not a component 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 1 ster than the weekend following 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 mal.
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. Self-explanatory. When a shutdown extends Components that do not fit any existing code should be de.
beyond the end of a report period, count only the time to the s snated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time events where a component designation is not applicable.
in the fo!!owing report periods. Report duration of outages 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 amplify or tor was on line should equal the gross hours m the reporting exp!:in the circumstances of the shutdown or power reduction.
peri d.
The column should include the specific cause for each shut.
down or significant power reduction and the immediate and REASON. Categorize by terter des.ignation.in accordance contemplated long term correctise action taken, if appropri-with the table appearing on the report form. If category 1-1 ste. This column should also be used for a description of the must be used.supp!) br:eicomments.
ma.ior safety.related corrective maintenance performed durint.
SIETLOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot; the erstical path activity and a report of any single release of REDUCING POWER.
Categorize by number designation radiosetivity or single radiation exposure specifically associ-INote that this differs from the Edison Electric Institute ateJ with the outage which accounts for rnore than 10 percen[
(EED definitions of " Forced Partial Outage" and " Sche.
of the a!!owable annual values.
(
duled P.ntial Outage / Fm these ierm>. III uses a change of For long testual reports continue nurative on separate paper 30 alW as the breal pomt. Foi larges powei reactors. 30 Slw anJ reference the shutdown or power reduction foi tin >
is 10.9 kWJll J Change to WJit ant e splJnJilon.
narra!jve.
DAY AVERAGE DAILY POWER (MWT)
(MWEN).
( 1/82) o 1
).67.58 48.77 O
2 67.58 I
48.59 3
66.83 48.44 j.
4 1 66.50 48.13 5
1 65.58 47.91 6
i 64.92
.47.70 7
1 35.13 26.13 --.-
o 8
- 0. 0, 0.0 9
0.0 0.0
~ ~ - - ' ~
9 0 - -
0. 5 0 - - - - -- - --
0. 0 -" - -- - -
e 11 3.0 0.0 12 ps0 0.0
$3
.$g,7
__3, 4 7 _
e 14 12El.7 37.21 15 157 46.14 16-
-163 3----
-47'45- - -"---
e 17 161 9
47.10 18 162 7
47.06 19 161jB3 46.86 o
20 169.')4 46.82
.21 16. 42 46.54 22-
- - - - 16.:2 5 4 6. 2 9 - - - - - - -- - - -- - -
e 23 i
. J' D.
~~ 4~6 715'
~ ' ~ ' '
24
'1 9.i7 45.93
,...., - 2 5
- - 1 8.C 8---
4 5. 6 9 - "- - - - - - -
'e "
26 1 7.4 45.40 27
' 56.
45.20
.j. _.. 2 8 55.
6
--- --- 4 4. 92 y'
29 154.4 44.48 54.6' 44.62 30 34 153.3 - - - -
~ 4 4. 22--
f e
P
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L
j Refuelinn Information Request 1.
Facility name:
l Big Rock Point Plant 2.
Scheduled date for next refueling shutdown:
February, 1982 3.
Scheduled date'for restart following shutdown:
April, 1982 h.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
yes explain. Two Technical Specification changes vith respect to NSSS system:
If(1) yes Iluelear Steam Supply System - Heatup, Cooldown, Hydrotest and Criticality (2) Reload H MAPLHGR limits change 2
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 vith the core reload (Ref.10CFR,Sec.50 59)?
i It will be reviewed. See below.
If no review hac taken place, when is it scheduled?
The review trill take place during the outage once the final physics package is submitted to the Plant.
(
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:
Yes - revision of only MAPLHGR limits for reload H '
2 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 duc date of the last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
1983 1
j