ML20197D074
| ML20197D074 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/1986 |
| From: | Czajka, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8605140121 | |
| Download: ML20197D074 (9) | |
Text
-
N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-316 DATE 3/5/86 COMPLETED BY CZAJKA TELEPHONE 616-465-5901 OPERATING STATUS 1.
Unit Name D.
C.
Cook Unit 2 2.
Reporting Period FEB 86 note.
3.
Licensed Thermal Power (MWt) 3411 :
4.
Name Plate Rating (Gross MWe) 1133 :
1 5.
Design Electrical Rating (Net MWe) 1100 :
I 6.
Maximum Dependable Capacity (GROSS MWe) 1100 :
7.
Maximum Dependable Capacity (Net MWe) 1060 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 Mu.
Yr. to Date Cumm.
- 11. Hours in Reporting Period 672.0 1416.0 71544.0
- 12. No. of Hrs. Reactor Was Critical 608.6 1352.6 50381.4
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator on Line 528.5 1272.5 49126.1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Therm. Energy Gen. (MWH) 1360957 3404597 154675207
- 17. Gross Elect. Energy Gen. (MWH) 436500 1097780 50784370
- 18. Net Elect. Energy Gen. (MWH) 418027 1053472 48954840
- 19. Unit Service Factor 78.6 89.9 71.1
- 20. Unit Availability Factor 78.6 89.9 71.1
- 21. Unit Capacity Factor (MDC Net) 58.7 70.2 66.9
- 22. Unit Capacity Factor (DER Net) 56.6 67.6 65.4
- 23. Unit Forced Outage Rate 20.8 9.9 15.7
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
_ BEGAN REFUELING OUTAGE 3/1/86.__ ESTIMATED LENGTH 100 DAYS
__=_____
- 25. ii 5s;t BE n-t Uns 67 E; port PEhiEU~~5~tiNatEU~5 Ate bi~5tSEEE~~~
__________aulY 10,1986_________________________________________________.1
- 26. Units in Test Status (Prior to Commercial Operation):
)
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l
b B605140121 860228 G
PDR ADOCK 05000316 T
[
R PDR
/
/
. i
/
b 4
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-316 UNIT TWO DATE 3/5/86 COMPLETED BY CZAJKA TELEPHONE 616-465-5901 MONTH FEB 86 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY
, POWER LEVEL 1
290 17 820 '
2 0
18 903-3 0
19 839 4
0 20
~ 950"
~,
l 5
0 21 71Es 6
0 22 657 7
318 23 672 8
584 24 854 i
9 855 25 851 10 857 26 853 11 856 27 852 12 856 28 482 13 855 29 O
14 859 30 0
15 857 31 0
16 861 4
+*
a I
)
i
?
r 4
~
.\\
,9-J I
e l
M*
e 50-316 INN:KEl Nf),
llNil' SilllllHlWNS AND POWI.it Hl:lilN'IIONS D_C. Cook._ Unit 2 llNil NAhlE IIAIE 3-10-86 COhlrl E'II?p Isy B. A. Svensson Hi PORI AlflNill February, 1986 616/465-5901 1El.l PlH)NE SHEET 1 of 3 I
p~l.
=
f Cause a rensettive
.3 g
'h
- s' l krusce
[n,,
) g s}e No.
Dale k
gg s
livene gy g3 Attion ein g
hevent itesmscnie t-aE d-j ;p, g Hepius e in U 6
169 860201 F
139,2 A
3 86-005-0 EB TRANSF The Unit tripped from 80% power due to auxiliary transformer 2 CD Unit differential operating. The trans-former unit differential was caused by a bushing exploding which re-sulted in a fire.
Repairs were made which permitted startup of the Unit utilizing the off-site auxiliary transformers. The Unit was returned to service at 1943 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.393115e-4 months <br /> on 860207 and reached the 80% administrative power limit on 850208.
170 860221 F
0 B
4 N.A.
HH HTEXCH P,eactor power was reduced to 55% to remove the West main feedpump from service to check the feedpump turbine condenser for tube leaks.
One leak-ing tube was plugged. Reactor power was returned to 80% the same day ~.
l
_l 4
17: l'in ceal Heasem:
hicehoil:
lintul.it G. Insamt:6.wis S: Silicalnicil A linguipmesa 1:ailme(1 nplain)
I klanpal for Psepaeatum of Data 11 hiaintenance os Test 2 klanual Scsam.
Episy Slicens fus Ikensce C.Mcfueling
.I Antomatic S sam.
liven Repent il i Hil'ile IHiiHI G-In Hegulasiuy Resisiciimi 4 Oilws (linplaini illtill l' Opesatos liaining & Ikeni.c I naminallon 17 Asinunistrasive 5
i; Opes asimial 1:ssos Blixplaint I sinlist 1 - Same Souwe l'J/ / /)
ll Ollies Ilimplain)
e 50-316 IMW:KEI NO IINil'Silll100WNS ANill'UWl H Hi DilrilONS
{,
,. PI Ahlli D.C. Cook, Unit 2 IIAIE 3-10-86 COHl'i l."IIED hY B.A.
Svensson i
HIl'UHIAlflNill Febf""YY' 1986 616/465-5901 I El.I l'IlONii SilEET 2 of 3
t.
p<,
e f
ranse A rensculve E E
'h
} @h"}
l 6tensec
[j.,,
3 Atenne tu N. i.
Date Q
gI g
g livent y, ?
gU Peevens Hcciusenic t-
,y -
tg Hepen
- in U g
g g
t5 171 860222 F
0 B
4 N.A.
1111 llTEXCil Reactor power was reduced to 55%
to again remove the West main feed-pump from service to check the feed-pump turbine condenser for tube leaks.
Six tubes were plugged.
The East feedpump turbine condenser was also checked with one tube plugged.
Reactor power was returned to 80% on 860223.
172 860228 S
4.3 B6C 1
N.A.
ZZ ZZZZZZ The Unit was removed from service at 1943 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.393115e-4 months <br /> for Cycle 5-6 Refuel-ing Outage.
In addition to the re-fueling activities, major mainten-ance work includes steam generator eddy current testing, control rod guide tube split pin replacement, replacement of the main feedpump i
turbine condensers, replacement'of PCB oil cooled transforemers and re-l 1
3
-l 1:: 1inted Heasini:
bleilniil:
1:alol>6 G-Instandi ms S: $s hedulcil A 1: guipmens 1:ailmell.nplain)
I kl.mnal law riepasanimi ni Data Il blainicnance on Test 2 Manual Sciani.
l.nasy Sheets fus Ikensee C Hefncling 1 Automatic Si sam.
1 vens Hepius il l'Hil'ile INilHI G-D Hegulaimy Hesseiction 1 Othei ttimplaml 0161) l' Opesalo l~saining A thense I xaminallen 12 Ailministsative 5
i G Opesalional 1:esus llimplain)
INinhat ! S.une Sonn e 19/11) 11 Othcs ilimplain)
i II I
llNII'SittlilHlWNS ANill'ilWilt Ill.litirilONS A [
C ook, Unit 2 IIAIE 3-10-86
( Oktri ETEI) ItY B.A. Svensson Hil'OH'I &lf) Nils February, 1986 6167G5-5901
. H.l l'
)NE.
SiiEET 3 of 3
~
i itensce S-s,,
h.
w
.y g
'k j h"j Cause & ronctiive N. i.
Date S,
gg
,g,g Event Q3 sgi Attion sie g'
Prevens Heciusenie P
oE j if, Helmes
- so O 172 placement of vital instrument bus inverters. The esti 'ted return to (Contir ued) service date is May 28, 1986.
L i
1 3
4 f: Foiccil Heason:
ble In=l:
lininliin G. insinical.uis S: Silicilnical A lign6pmens Failuse(linplain) 1 klannat los Picpaiation og Data 11 Maintenanc: of Test liiannal Sciani.
Ensiv Sheets foi I Aensee C.Hefueling 3 Automat 6c & sam.
livens Repos e Il l'H I I ile (NilHI G-D Hegulatiny Restoiction 4 Oilies tEmplain) 0161)
I! Opciatos I'saining a license I xamination i
F Asiministiative G Opesanimial 1:stus Ilimplaint ITinhis I - Same Somce 19/H) 11 Ollici (linplaisil l
4
Docket No.:
50-316 Unit Names D.C. Cook Unit 2 Completed By:
D. A. Bruck Telephone:
(616) 465-5901 Date:
March 10, 1986 Page:
1 of 3 MONTHLY OPERATING ACTIVITIES - FEBRUARY, 1986 HIGHLIGHTS:
The reporting period _ began with the reactor in Mode 1 at 80.5%
rated thermal power.
An unusual Event was declared on 2-1-86 due to an auxiliary transformer 2CD fire which caused the unit to trip.
After the trip the reactor was brought critical on 2-3-86 and the generator was paralleled to the grid on 2-7-86.
f There were two Engineered Safety Features actuations during this reporting period both due to high radiation alarms.
There were two major power reductions during this reporting period both to remove Main Feed Pump condensers from service.
t A reactor power reduction to take the Unit of line for a refueling outage was begun on 2-28-86.
The Unit ended the reporting period with the reactor in Mode 3 at 530*F average temperature, j
Gross electrical generation for the month of February was 436,550 MWE.
SUMMARY
02-01-86 At 0811, the Unit tripped from 80.5% rated power due to auxiliary transformer 2CD unit differential.
The unit differential was caused by a fire on auxiliary trans-former 2CD.
The fire started when a bushing exploded.
At 0815, an Unusual Event was declared because of the fire on auxiliary transformer 2CD. -The Unusual Event was terminated at 0903.
4 02-03-86 At 0618, a reactor startup was begun.
At 0651, the reactor startup was terminated because the reactor wac not critical 500 pcm past the ECP calculated rod height.
At 2243, a reactor startup was begun, the reactor was critical at 2311.
j i
l
Docket No.:
50-316 Unit Namn:
D.C. Cook Unit 2 Completed By:
D. A. Bruck Telephone:
(616) 465-5901 Date:
March 10, 1986 Page:
2 of 3 02-04-86 At 0005, reactor power reached 2% and the power in-crease stopped.
At 1250 a reactor power decrease began to conserve auxiliary feedwater because makeup water to the conden-sate storage tank was of marginal quality.
At 1324, reactor power reacted 2E-6 amps on the inter-mediate range.
02-05-86 At 1120, reactor power was increased to 2% rated power.
02-06-86 At 2120, a reactor power increase began entering Mode 1 at 2153 and stabilizing at 8% at 2215.
02-07-86 At 0218, an Engineered Safety Features Actuation, containment purge isolation, occurred due to a high alarm on lower containment iodine monitor ERS-2303.
At 0325, the generator was paralleled to the grid.
At 0548, the reactor power increase was stopped at a hold point of 28% rated power.
At 0624, a reactor power increase was begun.
At 1140, the Boron Injection Tank was declared inopera-ble due to low boron concentration.
At 1240, a power reduction was begun to comply with Tech. Spec. 3.5.4.1 due to the Boron Injection Tank Being inoperable.
At 1344, the Boron Injection Tank was declared operable, j
At 1420, a reactor power increase began reaching a hold point of 48% at 1605.
02-08-86 At 1316, a reactor power increase was begun, reaching l
80.5% at 1838.
02-21-86 At 0803, a reactor power reduction to remove the West Main Feed Pump from service due to a condenser tube leak was begun.
The power reduction was stopped at 55%
at 1055 and the pump removed from service at 1053.
At 1745, with the West Main Feed Pump in service, a reactor power increase was begun.
The power increase was stopped at 79% at 2150.
Docket No.:
50-316 Unit Names D.C. Cook Unit 2 Completed By:
D.
A. Bruck Telephone:
(616) 465-5901 Date:
March 10, 1986 Page:
3 of 3 02-22-86 At 0820, a reactor power reduction to remove the West Main Feed Pump from service due to condenser tube leakage was begun.
The power reduction was stopped at 55% at 1050 and the pump removed from service at 1105.
At 1616, the west main feed pump was returned to service.
i At 1844, the east main feed pump was removed from service.
i At 2251, the east main feed pump was returned to service.
02-23-86 At 1109, a reactor power increase was begun.
The power increase was stopped at 79% at 1529.
02-25-86 At 0431, an inadvertant Engineered Safety Features Actuation, containment purge isolation, occurred due to a high alarm on lower containment particulate monitor ERS-2301.
02-28-86 At 0907, a power reduction to remove the Unit from service for a refueling outage began.
At 1943, the generator was removed from parallel.
At 2057, the reactor entered Mode 2.
At 2136, the reactor entered Mode 3.
9 y
r 4
DOCKET NO.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 3-10-86 COMPLETED BY.
B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of'l MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1986 C&I-l Leop 4, Teold RTD NTP-241, failed high. Resistance of NTP-241 i
was found to be out of specification.
Connected spare RTD, performed calibration and surveillance procedure and declared channel operable.
I l
1-9 INMM & MMIGM MCDJUDMMM
- yster, Donald C. Cook Nuclear Plant P.o. Box 458. Brdgman, Mehgan 49106 March 10, 1986 Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Pursuant to the requirements of Donald C. Cook Nuclear plant Unit 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of February, 1986 is submitted.
Sincerely, i
W. G. Smith, Jr.
Plant Manager WGS:ab Attachments cc:
J. E. Dolan I
M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee R. C. Callen i
S. J. Mierzwa F. S. VanPelt, Jr.
P. D. Rennix D. R. Hahn Z.
Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center i
ANI Nuclear Engineering Department t
j
_