ML20129H686
| ML20129H686 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/31/1985 |
| From: | Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8506070637 | |
| Download: ML20129H686 (8) | |
Text
r N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-315 DATE 4/2/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS 1.
Unit Name D.
C.
Cook Unit 1 2.
Reporting Period Mar 1985 notes 3.
Licensed Thermal Power (MWt) 3250 :
4.
Name Plate Rating (Gross MWe) 1152 1 5.
Design. Electrical Rating (Net MWe) 1030-l
- 6. Maximum Dependable Capacity (GROSS MWe) 1056 :
(Net MWe) 1020 -----------------------
7.
Maximum Dependable Capacity 8.
If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since
~
Last Report Give Reasons ________
_ = - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - -
==-------------___-------- ___
9.
Power Level To Which. Restricted. If Any (Net MWe)
- 10. Reasons For Restrictions. If Any __________________
This Mo.
Yr. to Date Cumm.
- 11. Hours in Reporting Period 744.0 2160.0 89832.0
- 12. No. of. Hrs. Reactor Was Critical 744.0 1745.6 67439.4 13.-Reactor Reserve Shutdown Hours 0.0 0.0 463.0
- 14. Hours Generator on Line 744.0 1733.8 66095.3 15.JUnit Reserve Shutdown Hours 0.0 0.0
-321.0
- 16. Gross Therm. Energy Gen. (MWH) 2301237 5076754 194858327
- 17. Gross Elect. Energy Gen. (MWH) 752060 1649810 63421700
- 18. Net Elect. Energy Gen. (MWH) 724986 1587338 61018433 19.- Unit Service Factor 100.0 80.3 75.4
- 20. Unit Availability Factor 100.0 80.3 75.4 21.' Unit Capacity Factor-(MDC Net) 95.5 72.0 68.2
- 22. Unit Capacity Factor (DER Net) 94.6 71.3 65.6
'23.
Unit Forced Outage Rate 0.0 0.0 7.3
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
na f na l i n g. an el _10._ yea r _aurreil. lance._qutage._achedulesl_tq_b eqi_n _415]_8 5.
Expected _ duration _approximately_LQ0_daya ____________
- 25. If Shut Down At End of Report'Deriod, Estimated Date of Startup:
- 26. U~ nite ~I~n~TeEt Sthtus (PrI~or to CommeE~cIAI~OperAtI~on5I~~~~~~~~~~~~
~
~
~-~~
~
Forcast Achieved INITIAL CRITICALITY
' INITIAL ELECTRICITY COMMERCIAL OPERATION
^
8506070637 850331 PDR ADOCK 05000315 g
R PDR y
~ ~
,.;c _
_ 1
'e
- _ c.,.
p s
' ' AVERAGE'DAIL POWER' LEVEL
( MWe-Ne t ). -
~
H.,. ;
w'
^# DOCKET-'NO.
'50-315 N
' ~
UNIT
' ONE^
I'-
DATE-
- 4/2/85.
- COMPLETEDBY
-CLIMER.
l 4,p -
' TELEPHONE 616-465-5901:
2: MONTH' Mar- :' 1985.
s AVERAGE DAILY AVERAGE DAILY POWER; LEVEL-
. DAY,
. POWER LEVEL ~
. DAY; s
- 1
~ '
~
.1024-17-1025-
~2
.1024 18 1028 J3 a
.1016:-
19 1026-J' 4 -
1025' 20 1020 15 1022 21' 1021
'6 :'
~
~1022 22 1022.
.7m 1025~
23 990 r.'
=8,
.973-
-24 1028' L&. '.9 560 25 1025 e
~
,_.821 26 1029 f 10 -
- 11 1026 27 1007 12>
~ 1025 28 967 13 1027J 29
'946
- 1022 30 941 935-31' 941' 15- --*
16'.~ -
643
- -y r
+
'.ye b
T V
4 a
( v'
?
a s
F T
1
I 50-315 DOCKET No.
tlNIT SilullM)WNS AND POWEH HElHMTIONS D.C. Cook Unit'l UNIT NAblE DATE 4-5-85 COhlPEETED itY B.A. Svensson March, l'985 TELEPIN)NE 616/465-5901 HEPOR~l blONTil n.
.E E
}
E Iicensee ps,,
"L Causc & Consective No.
D.ste f,
yg o y gg livent 3,"g p
Action ::
g' Psevent Heemtence fE 5
j ;p, g Hepent 4 mu t-5 244 850308' F
0 B
4 N.A.
HH HTEXCH Reactor power was reduced to 55% to permit removing one main feed pump from service to check the feed pump turbine condensers for tube leaks.
12 tubes were plugged in the east feed pump turbine condenser. No leaks were found in the west feed pump turbine condenser. Reactor power was returned to 100% on 850310.
i 245 850315 F
0 B
4 N.A.
HH HTEXCH Reactor power was reduced to 55% tc.,
permit removing one main feed pump from service to check the feed pump i
turbine condensers for tube leaks.
I No leaks were identified in either condenser. Reactor power was re-turned to 100% on 850317.
I 2
3
-l 1;: I;incett Heas.m:
hicihoil:
Exhibit G. Insisuctiims S: Scheiluteil A liquipmes;I Failuee(Explain) l blanual fin Psepasatism of Data 11 hiaintenance oi Test 2 Manual Scram.
Entay Slicets fin I.icensee C-Refueling 3 Automatic Steam.
livens Repius II.l?RI File iNilRi?G-D Hegulatiny Restsiction
-l Othes (Explain)
-0161) li-Opesatos I'saining & liccuse 1:xaminalism F Ailnsnistsative 5
lixinbit 1 - Same Souice G Opesatiinialliiso liixplain) 19/D) 11 Othes (Explain n
ia: u
-w.~
"~
=+
a UNIT SHUTDOWNS AND POWER REDUCTIONS -
INSTRUCTIONS Tlus report should desenbe 211 plant shutdowns dunng me in accordance with the taole appearms on the report form.
report penod. In addition. it should be the source of explan.
If category 4 must be used. supply bneicomments.
anon of sismResnt dips in average power levels. Each signi.
ricant reducuon in power level (greater than 20", reduction LICENSEE EVENT REPORT =. Reference the applicable 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 />) reportacle occurrmes pertammg to the outage or power should be noted, even mough me unit may not have been reduction. Enter the first four pans (event year, sequennal l
shut down completely. For such reductions in power level, report number, occurrence ecde and report type) or the tive tne duration should be listed as zero.the method of reducnon part designation as desenbed in Item 17 ot Instrucuons for should be listed as 4 (Other) and the Cause and Correenve Preparanon 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 Correenve Acnon to Prevent Recurrence column immediately evident for all such rhutdowns.of course, since should be used to provide any needed explanation to fully rurther investigation may be required to ascertam whether or desenbe the circumstances of the outage or power reduction.
not a reportable occurrence was involved.) If the outage or power reduction wdl not result in a reportable occurrence.
the posinve indication of this lack of correlation should be NUMBER. This column should indicate the sequential num.
ber asagned to each shutdown or sigmilcant reductionin power noted as not applicable (N/A).
for that calendar year. When a shutdown or ugnificant power SYSTEM CODE. The system in which the outage or power reduction begms m one report penod and ands m another.
~
an entry should be made for both report penods to be sure reduction originated should be noted oy the two digtt code of 211 shutdowns or sigmdcant power reductions are reported.
Ex}ubit G. Instrucnens for Preparation of Data Entry Sheets Unt:12 unit has achieved its first power generation, no num.
for Licensee Event Report (LER) File (NUREG.0!61).
ber should be assigned to each entry.
Systems that do not tit any existmg code should be designa-ted XX. The code ZZ should be used for mose events where DATE. This eclumn should indicate the date of the start a system is not applicaole.
- of each mutdown or signiilcant power reduction. Report as year. month, and day. August 14.1977 wcuid be reported COMPONENT CODE. Select the most acpropriate component as 770314 When a shutdown or stgruncant power reduction from Exrubit I. Instruenons for Preparanon of Data Ent:1 begms in one report pened and ends in another, an entry should Sheets for Licensee Enne Report (LER) Fde (NUREG.0161).
be made for both report penods to be sure all shutdowns using the following entiena:
or ugnincant power rtducticas are reported.
TYPE. Use -F or "S" to indicate either " Forced" or " Sche-duled." respectively, for each sautdown or signideant power 8.
If not a cor ponent fadure, use the re!sted component:
reducnon. Forced shutdowns include those required to be e.g.. wrong valve operated through errort list valve as miriated by no later man the weeicend fo!!owing discovery compo.ent.
of an off. normal condinon. It is recogmzed tha: some judg-ment is requared in categonzmg shutdowns in this way. In C.
If a cnam of fadures occurs. de first component to mai.
general a forced shutdown is one that would not have been function should be listed. The secuence of events.mciud.
completed in me absence of the condition for which correceve ing the other components wh:ch fail. shou!d be desenbed action was taken, under the Cause and Correcuve Acnon to Prevent Recur.
rence column.
DURATION. Seif. explanatory. When a shutdown extends Components that do not tit any existmg code should be de.
beyond the end or a report penod. count only the time to the signated )CCCOOC. The code 777777 should be used for end or the report penod and p:ck up the ensumg down tmie events where a componet*t deugnation is not appiicaole.
in the following report penoas. Report duranon of outages rounded to the nearest tenth of an hour to fac Etate summanon.
CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.
The sum of the total outage hours plus the hours the genera.
RENCE. Use me column in a narrative fastusn to ampiify or tot was on line should equal the gross hours in the reportmg explam the circumstances of the shutdown orpower reduccon.
pertod.
The column should nclude the spectSc cause for each shut-down or sigmricant power reducnon and the immeoiste anc REASON. Catepnze by !etter designation in accordance contemoisted long term correenve acnon taken, if appropn.
with the table appearmg on the report form. If category H ate. This ",lumn should also be used for a descnonon of tne must lie used, succiy bnet eumments.
,,,,,,,f
.ated correcuve mamtenance performed dunna
'wer reducnon including an identitication ot the outat a 2ennty anc 2 mport a any smpe Messe a}
METHOD OF SHUTTING DOWN THE REACTOR OR the ennea, REDUC 1NG POWER. Categonze by numner dessnanen radioactmty vr smgie radiation exposure spes:ticady asse.t-INote that this dift'ers from the Edisim E?e:.tr e Insuture ated with the outage whicn accounts for more taan 10 cerwent TEED derimtions of -Forced Partial Outage" anc "Sene, wi th* 211o*20le annual values.
auled Part:a1 Outage /' For these tenni. Ei!! uses a shange at For tong textual resorts eentmue narrat:ye on seoarate ;acer
.0 MW as the bres pumt. For !arver power reactors.30 MW and rereren,e the shurcown or power recu nun foi t: t>
- s t.u imall a enange to warrant espianation.
narrative.
pp --
, < ~ ~.
..e.n.
.m,,,.-
k
Docket No.:
50-315
-Unit Nams:
D.C. Cook Unit 1 Completed By:
D. A. Bruck Telephone:
(616) 465-5901 Date:
April 3, 1985 Page:
1 of 2 MONTHLY OPERATING ACTIVITIES - March, 1985 HIGHLIGHTS:
The reporting period began and ended with the Unit in Mode 1 at 100% rated thermal power.
The Unit operated continuously throughout the reporting period with one major power reduction occurring to remove the West Main Feed Pump Condenser from service for tube leak checks.
The Unit ended the reporting period at 92% rated thermal power.
Total electrical generation for the month was 752,060 MWH.
Summary:
3-02-85 At 0501, the Engineered Safety Features Ventilation fan, 1-HV-AES-1, was inoperable when the motor failed.
The fan was returned to service at 2110 on 3-02-85.
3-07-85 At 0325, the West Component Cooling Water Pump was declared inoperable when sparkes were observed coming from the motor during performance-of the monthly surveillance test.
The pump was returned to service at 1408 on 3-07-85.
3-08-85 At 1504,a power decrease to 55% was. begun to remove the East Main Feed Pump Condenser from service.
3-09-85 At 0640, the Unit reached 55% power.
At 1006, the East pump was returned to service and the West pump removed from service.
At 1729, the West pump was returned to service and the East pump was removed from service.
At 2236, the East pump was returned to service.
3-10-85 At 0035, a power increase began.
At 0340, because the Control Room Pressurization System fresh air makeup was in excess of plant design, a power decrease begun (power was at 69%).
At 0630, the fresh air makeup was within design and the power decrease was stopped (64%) and a power increase was begun.
At 1715, power reached 100%.
3-15-85 At 1105, a power decrease to 55% was begun to remove the West Main Feed Pump Condenser from service.
\\
-N
Docket No.:
50-315 Unit Names D.C. Cook Unit 1 Completed By:
D. A. Bruck Telephone:
(616) 465-5901 Date:
April 3, 1985 Page:
2 of 2 3-16-85 At 0355, the Unit reached 55% power.
At 0956, the West pump'was returned to service and the East pump was removed from service.
AT 1410, the East pump was returned to service and at 1432, a power increase began.
3-17-85 At 0021, power reached-100%.
At 0501, after placing the load changer in service for control valve testing a load increase of 35 MWe occurred. The recovery action resulted in a final-power of 98%.
At 0527, a power increase began reaching 100% at 0719.
3-22-85 At 2250, a power decrease was begun due to level one oxygen in the condensate.
3-23-85 At 1150, with power at 91.4%, the power decrease stopped because oxygen levels were within limits.
AT 1205, a power increase began reaching 100% power at 1650.
3-27-85 At 0910, a power decrease to 80% was begun as an interim measure pending an analysis of the impact of various axial power shapes that could occur during cycle 8.
At 1735, power was adjusted to 94% per the direction of the Nuclear Section.
3-28-85 At 1830, power was adjusted to 92% per the direction of the Nuclear Section.
3-31-85 At 0355, Because of a trailer fire within the protected area, an Unusal Event was declared.
At 0405, the fire was out and the Unusal Event terminated.
The Control Room Cable Vault Halon System remains inoperable as of 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 4-05-83.
The backup CO System for the Control 2
Room Cable Vault remains operable.
.=
,. ~..
.hy ?
if
=L 4
- /
s v.
s
~
DOCKET NO.
50 - 315
-UNIT NAME D. C. Cook - Unit No.- 1 DATE 4-5-85.
COMPLETED BY B. A.+Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1985 H-l '
Replaced worn indicator drive gears on FM0-212~(M. D.-Aux-iliary feed pump to #1 S/G) operator. Stroked valve to verify local position indicator tracking withivalve^ position.
.M-2 Replaced #3 S/G. blowdown isolation valve, DCR-330. Retesting was_ performed.to verify valve operability.
?
(
L
[
L
-i
3.
- K.,;..,, -
1
- Q p :.
g,
. c
/Y A <m IN0Mnt & MICHMAN ELECTRIC COMPANY.
DoneW C. Cook Nocher Pfent
'. 4' P.O. Bau 468, Bndgman, Mchsgen 49106 5,
April 5, 1985
^
/
- -b 2
- Director, Office Of Management Information
' and Program Control-
. U. S. ; Nuclear: Regulatory Commission -
' ~
Washington,:D._C.
20555 R
Gentiemen:
. Pursuant. tio the requirements of Donald C. Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.6,.the attached Monthly-Operating
~ Report for the Month of March, 1985 is submitted.
- Sincerely,-
~
. W
- W. G.l Smith,-Jr.
~ Plant; Manager-1 WGS:ab'
-Attachments.
cc: 'J. E. Dolt.n z
M. P. Alexich
~ R. W. Jurgensen NRC-Region III B.' L.- Jorgensen
.R. O. Bruggee:
-R. C..Callen S. J. Mierzwa R..F. Kroeger B. H. Bennett P. D.-Rennix' 1
cJ. H. Hennigan Z.
Cordero
- J.
- J. Markowsky.
J.- F. Stietzel PNSRC File
-INPO Records Center-ANI Nuclear Engineering Department h
.-j 7;
~
^
'^
n
-t
- 1
(
- ar-F-e
?
-t 9
a* W T t PT7Ne
- r"=r-**T-t*-9'a+wwe%'Mytr r !*4 P* Ma sf<
e Mg wM91W + t tW 7re-z' TP--tsw t vr 9 re 9 W-w te-p t-- f -
E'45 tr r*be"'*5e1'