ML17321B016
| ML17321B016 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/31/1985 |
| From: | Czajka, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8601080630 | |
| Download: ML17321B016 (11) | |
Text
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ACCESSION NBR:
FAC IL 50-316 AUTH. NAME CZAJKA SVENSSONg B. A.
SMI THe W. G.
REC IP. NAME REGULATORY INFORMATION DISTRIBUTION SYS>EM (RIDS) 8601080630 OC. DATE: 85/10/31 NOTARI D:
NO.
DOCKET 0 Donald C.
Cook Nuclear Power Planti Unit 2i Indiana 5
05000316 AUTHOR AFFILIATION Indiana 5 Mic h igan El ec tric Co.
Indiana 5 Michigan Electric Co.
Indiana h Michigan Electric Co.
REC IP IEN 1 AFFlLIATION SUB JFCT:
Monthly operating rept for Oct 1985. W/851108 ltr.
DISTRIBUTION CODE:
IE24L COPIES RECEIVED: LTR ENCL SIZE:
TITLF:
Op crating Rept (50 DKT)-Annua 1/Semiannual/Monthly NOTES: OL'2/23/72 05000316 REC IP IENT ID CODE/NAME PWR-A PD4 PD 04 INTERNAl:
ACRS 11 NRR/DSRO RM/DDAMI/MIB01 COPIES LTTR ENCL 5
5 10 10 1
1 2
2 REC IPZENr ID CODE/NAME NMSS/FCAF RCN3 COPIES LTTR ENCL 1
1 1
1 EXTERNAL: 24X NRC PDR 1
1 1
1 LPDR NSI C 03 05 TOTAL NUMBER OF COPIES REQUIRED: LTlR 24 ENCL 24
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N.R.C.
OPERATINB DATA REPORT DOCt ET NO."
50-316 DATE 11/04/85 COMPLETED BY CZAJKA TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D.
C.
Cook Unit
- 2. Reporting Peri ad OCT 85 lnates Licensed Thermal Power (MNt)
~4ii 4.
Name Plate Rating (Brass Mlle) 11Zu s
5.
Design Electrical Rating
<Net MNe>
1100.
6.
Mar,imum Dependable Capacity (GROSS MNe) 1100 7.
Mar,imum Dependable Capacity (Net MNe) 1060
- 8. If Changes Occur in Capacity Ratings (Items no.
~ through
- 7) Since Last Repart Give Reasons Power Level To Which Restricted.
If Any (Net MNe) 10.
Reasons For Restrictions. If Any:
11
~
1ia.
14.
15.
1 b.
17.
18.
19.
20 ~-l.
Hours in Reporting Period No. of Hrs.
Reactor Was Critical Reartor Reserve Shutdawn Hours Hours Generator on Line Unit Reserve Shutdown Hours Brass Therm.
Energy Gen.
(MNH)
Grass Elect.
Fnergy Gen.
(MNH)
Net Elect.
Energy Ben.
<MWH>
Unit Service Factar Unit Availab lity Factor Unit Capacity Factor
<MDC Net.)
Unit Capacity Factor (DER Net>
Unit Forced Outage Rate Shutdowns Scheduled over Next Si:<
This Mo.
745.0 158. 0 141. 8 0.0 16 ~249 42250 37 "69
- 19. 0
- 19. 0 4.7 4.6
- 81. 0 Months (Ty Yr. ta Date 7:596. 0 4665. 6 0.0 4589.1 0.0 14800561 481~7/0 46415~~1 6.0 62
~ 0
- 59. 2
- 57. 1 Zb. 6 pe, Date, and Cumm.
68664. 0 47745. 6 0.0 46587. 7 0.0 147878622 48599?00
+6859265
- 70. 4
- 70. 4 bb ~ 8
- 65. 4 15.9 Duratian):
REFUELING SCHEDULED FOR FEBRUARY 1986
- 25. If Shut Down At End of Report Periad, Est.imated Date af Startup:
UNIT SHUTDOWN FOR TRIP BREAKER ANALYSIS. Unit returned to service ll/8/85,
.6. Units in Test Status (Prior ta Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION 8601080630 8S1031 PDR ADOCK 05000316 R
AVERAGE DAILY POWER LEVEL (NWe-Net)
DOCKET NO.
50- >1*
UNIT TWO DATE 11/04/85 COMPLETED BY CZAJKA TELEPHONE 616-465-5901 NONTH OCT 85 DAY 1
4 5
6 7
8 10 12 14 1 5ib AVERAGE DAILY POWER LEVEL 0
0 0
0 0
0 0
0 0
0 0
0 DAY 17 18 19 20 21 2~>
25 28 29
~0
~1
~
AVERAGE DAILY POWER LEVEL 0
0 0
0 0
59 209 211 212 214 uih D >6 0
UNITSIIUTI)O)VNSANI)POIVEII REI)Ul."TIONS REPOR1'hlONTII October, 1985 I)OIETNO.
UNITNAIIIE l)ATE
(:OhlPLETEI) llY TELEPIIONE PAGE 50-316 D.C. Cook, Unit 2 11 8 85 B.A. Svensson 616 465-5901 lof 2 a
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I.lccoscc I:vellt Rep<>rl Ir Ew P
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O Eu O
( XLISC Ec (L)lleetive Actloll I>)
Prevcot Rccorrcoce 164 165 850824 851029 F
545. 2 F
58.0 A&B N.A.
(Later)
CC zz HTEXCH zzzzzz The Unit was removed from service on 850824 for steam generator tube leak repairs and to perform required desig changes.
The Unit was returned to service on 851023 at 1712 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.51416e-4 months <br /> EDT.
During power ascension from the pre-vious outage, a reactor trip occurred from 79X power.
The trip was trig-gered by a spurious indicated low-flow condiiton in R.C. Loop 2 due to a momentary drop in the output volt-age from vital instrument bus, GRID II.
The voltage drop is believed to
'ave been caused by a component fail-ure in radiation monitor, ERS-2300.
Following the reactor trip it was discovered that reactor trip breaker "Al> failed to open.
The trip was accomplished through reactor trip e
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uNITSiiurl)O>VNS ANI)POWEII HEI)UNIONS IIEI'OI(TIIONfll October, 1985 I)OCKETNO.
UNITNhhIE l)ATE COhlPLETEI) IlY TELEPIIONE PAGE 50-316 D.C.
Cook Unit 2 11 8 85 B.A. Svensson 616/465-5901 2 of 2
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( ontinued) breaker wB".
The Unit remained shut down at the end of the month (RCS in Mode 3) pending resolution of the reactor trip breaker problem.
I I': I'orchid S: Scheduled Ilcxsiwr.
A.EI)uliforcnt Fxlhwe (Explxht)
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'I'xhfhit I S~fnc Suw<<c
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Dockeg+Io.:
Unit 8%.me:
Completed By:
Telephone:
Date:
Page:
50-316 D C Cook Unit 2 D. A. Bruck (616) 465-5901 Nove'mber 11, 1985 1 of 2 MONTHLY OPERATING ACTIvITIES OCTOBER, 1985 HIGHLIGHTS:
The reporting period began with the Reactor Coolant System in Mode 5.
On 10-13-85 at 2132, the Reactor Coolant System entered Mode 4.
On 10-19-85 at 0616, the Reactor Coolant System entered Mode 3.
On 10-23-85 at 0033, the Reactor entered Mode 2 becoming critical at 0102.
On 10-23-85 at 1506, the Reactor entered Mode 1'nd at. 1712, the Unit was paralleled to the system.
On 10-23-85 at 2350, with reactor power at 23%,
a 3%/hr increase was begun.
The power increase was stopped at 2215 with power at 29%.
On 10-28-85 at 0945, a power increase of 3%/hr to 50% was begun.
The increase was stopped at 1640 with power at 49% due to a chemistry hold.
On 10-29-85 at 0345, a power increase to 80% was begun.
At 1357 a reactor trip occurred from 79% power.
The trip was triggered by a spurious indicated low flow condition in R.C.
Loop 2, due to a momentary dip in the output voltage from vital instrument bus, CRID II.
The voltage drop is believed to have been caused by a component failure in radiation monitor, ERS-2300.
Following the reactor trip it was discovered that reactor trip breater "A" failed to open.
The trip was accomplished through reactor trip breaker "B".
The reporting period ended with the Reactor Coolant System in Mode 3.
Total electrical generator for the month of October was 42,250 MWE.
SUMMARY
10-13-85 At 2132, the Reactor Coolant System entered Mode 4.
10-19-85 At 0616, the Reactor Coolant System entered Mode 3.
At 0831, an Engineered Safety Features actuation resulted from a high alarm on containment particulate radiation monitor, ERS-2301.
At 0850, an Engineered Safety Features actuation resulted from a high alarm on containment particulate radiation monitor, ERS-2401.
10-22-85 At 1441, an Engineered Safety Feature actuation result-ed from a high alarm on containment area radiation monitor, VRS-2201.
Docke~o.:
Unit Mme:
Completed By:
Telephone:
Date:
Page:
50-316 D.C. Cook Unit 2 D. A. Bruck (616) 465-5901 November 11, 1985 2 of 2 10-23-85 At 0102, the Reactor was critical.
At 1506, the Reactor entered Mode 1.
At 1712, the Unit was paralleled to the system.
At 2008, with power at 23%,
a 3%/hr increase was started.
At 2215, reactor power increase was stopped at 29%.
At 2350, an Engineered Safety Features actuation resulted from a high alarm on the containment high range noble gas monitor, ERS-2309.
10-24-85 At 2358, an Engineered Safety Features actuation resulted from a high alarm on the containment particulate radiation monitor, ERS-2401.
10-27-85 AT 0910, an Engineered Safety Features actuation resulted from a high alarm on the containment particulate radiation monitor, ERS-2301.
10-28-85 At 0945, a power increase to 50% at 3%/hr was begun.
At 1640, the power increase was stopped at 49% because of secondary chemistry.
10-29-85 At 0345, a power increase to 80% was begun.
At 1357, a reactor trip occurred from 79% power.
The trip was triggered by a spurious indicated low flow condition in R.C. Loop 2, due to a momentary dip in the output voltage from vital instrument bus, CRID II.
The voltage drop is believed to have been caused by a component failure in radiation monitor, ERS-2300.
Following the reactor trip it was discovered that reactor trip breater "A" failed to open.
The trip was accomplished through reactor trip breaker "B".
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DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 316 D.
C.
Cook Unit No.
2 11-8-85 B. A. Svensson (616) 465-5901 lof 1 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER%
1985 M-1 2-NRV-152, Pressurizer Power Operated Relief Valve leaking by.
Lapped seats and replaced gaskets.
C&I-1 Unit 2 AB diesel engine lube oil level was indicating almost zero level with tank almost full.
Level indicator was repaired and calibrated.
C&I-2 Amphenol triaxial cable bulkhead connectors for the Source Range and Intermediate Range Nuclear Instrumentation Systems were in-spected in accordance
'with Westinghouse Technical Bulletin NSID-TB-84-12.
The right connector on Source Range Channel N36 was found faulty and was replaced.
C&I-3 BLP-122, S/G Level Protection Set III Indicator was indicating erratically.
The reference leg to BLP-122 was found to have been nicked with a grinder.
A patch was welded at the nick and the indicator was verified operable.
C&I-4 A calibration check of 82 hydrogen recombiner thermocouples was required.
The heater bank was removed and thermocouples were re-inspected.
Heater bank was re-installed and thermocouple continuity was verified.
C&I-5 CFA-454, CCW flow to 824 RCP lower motor bearing was stuck at 3 gpm and would not change when the outlet throttle valve was stroked.
The strain gauge was replaced and range resistors from the circuit board were removed.
Transmitter was calibrated and system was verified for proper operation.
C&I-6 CFI-451, CCW flow to 824 RCP upper oil cooler was reading off scale high.
The transmitter ampfifier was found to be bad.
The amplifier board was replaced and the loop was calibrated.
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monsoon DIAN & NICH D N ELEC 8 C C Donald C. Cook Nuclear Plant P.O. Sox 458, Bridgman, Michigan 49t06 November 8, 1985 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 October, 1985 is submitted.
Sincerely, W.
G. Smith, r.
Plant Manager WGS:ab Attachments cc:
J.
E. Dolan M. P. Alexich R.
W. Jurgensen NRC Region III B. L. Jorgensen R.
O. Bruggee R.
C. Callen 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 ANI Nuclear Engineering Department
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