ML20079M851
| ML20079M851 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 12/31/1983 |
| From: | Gillett W, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC |
| References | |
| NUDOCS 8401270446 | |
| Download: ML20079M851 (9) | |
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DOCT TNC.90-319 DATI 1-9-Ra
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COS ?L_~. IO EY T3
'ri cillett
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616-465-5901 4.
C'IRAT!N. 5-ATUS 1.' Uni:Nacte:
Dnnn1r1 c. Cook 1
No::s
'-~.
December 1983
-. RC OT:'% ' 3.cC
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y
- 3. t i---s Th-
' ?:wer p,;w:):
3250
- 4. N===:.las':.-L.:i=; (Cro= alw=):
1152 1030
- 5. Desi;= II:=:i=! R=in;(Ne.51We):
- 6. 3!=d=== Dep:nd:ble C:p::i:7 (Cress 31We):
1056 1020
- 7. Sfaxi=== De-- >9!#---@ (Ne 31Weji
- 8. If C.:..; s C:=:in C:p::i:y R::i ;:(1::=s Nc=* ::3 Th::c;h 7) SI::: Lt.:: Repc::. Cive R:==ns:
- 9. Power Level To W'd:h 2==i==d If Any (N:: Siwe):
8
' 10. R=:ocs For R==i:d== 1f A=y:
t This 51oc:h Y.<o. Case.
C==I::ive
- 11. Ecu : != R:;o:.in; ?:: icd 744 8,760 78,888
- 12. Nc=b:: Cf Hoc s R==:r W:s C:.:i::.1 325.1 5,736.4 57,618
- 13. Re:=:r R=ene sh :down H::=
0 0
463
- 14. Ec== ce===::: ca. Lier 309.7 5,630.8 56,343.7
- 15. U..!: R::.erve sh :d=w= He.=
0 0
321
- 16. Cross Th== ! E==:;r Ce===::d (3:WH) 737.558 16.779.054 164.344.056
- 17. Grou E =:i=iI:=;y Ce:-=::d G.twa) 237.160._,_
5.490,440 53.926.290 i
- 13. N : E::=i=lIn::;y Cen=: : d (5;Wi.-)
226,311 5,286,839 51,880,340
- 19. U=i: Servi =.::=:r 41.6 64.3 >
73.3
- 20. Uci: Av.-il:hi!!:7 ::::or 41.6 64.3 73.3 29.8 58.2 66.2
- 21. Unit C:::=E / 7:::::(Usin; MrC Nec)
'.2. U !: C.:::ci:y. ::::r(Usin; CEE.'tet, 29.5 57.7 63.3
- 23. Uni:.:::::d C =;e R::
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- 25. !! Sh:: Down A: Zad Cf R::::: ?:-ici. I.::i=:: d 0:ta ei S::==:
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w 8401270446 831231
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PDR ADOCK 05000315 gut-i R
PDR I*
AVERAGE DAILY UNIT POWER LEVEL
~
C0CXET NO.
50-315 UNIT 1
DATE i-5-84 COMPLETED SY W. T. Gillett TELEPHONE 616-465-5901-MONTH twwnber 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
-(MWE-Net)
(MWe-Net) 1 0
17 o
2 0
18 0
3 0
19 182
'4 0
20 550 5
0 21 719 6
0 22 756 7
0 23 763 8
0 24 580 9
0 25 7ss 10 0
25 766
(
11 0
27 772 12 0
23 779 13 0
29 855 14 0
30 946 15 0
31 1004 16 0
l
\\
l INSTRUCTIONS On this fama list the average daily unit pcwer level in MWe-Net for each day in the reporting month.
Ccmoute to the nearest whnla mig;'??*
L
- - - - - ~ ~ ~
~ ~ ~ ' ~ ~
50-315 DOCKET NO.
UNIT SiluTI) OWNS AND POWER REDUCTIONS D.C. Cook - Unit i UNIT N AME l) ATE 1-13-84 COMPLETED I Y B.A. Svensson REPORT MONTil DECEMBER, 1983 TELEPilONE 616/465-5901 PAGE 1 of 2 S
4 u. 3 c_
r.
c Cause & Canaccaive 5 ;;
licensee g-*,,
8.9.
e e E
7 3
Auion to No.
Date Q
3g
,ggy Event g7
$5 5
55g Repo:I#
WU Prevent Recturence e
u O
207 831122 S
432.9 A&B 3
N.A.
ZZ ZZZZZZ At the beginning of the month the Unit was in cold shutdown for main-tenance on No. 14 reactor coolant pump motor and a pressurizer spray valve. The Unit was returned to ser-vice on 831219 and load to 30% for J
turbine / generator rotor warming prior to performing turbine overspeed tests.
208 831219 S
1.4 B
1 N.A.
ZZ ZZZZZZ The Unit was removed from service for turbine overspeed testing and then immediately returned to service.
Re-I actor power ias increased to 75% by 831222.
209 831224 F
0 H
4 U.A.
ZZ ZZZZZZ Reactor power reduced to 557. to per-mit removal from service of one main feed pump at a time to clean the F.P.
Turbine condenser tube sheets due to an excessive amount of trash in the circulating water system. During re-f I
2 3
4 F: Fin ced Reason:
Mcihud:
Exhibin G-Insiinctiims S. Soheilnical A Lignipmerie Faihne(l;xplain) 1 -Manual for Prelmation of Data ll-Maintenance or' Test 2 Manual Sciam.
Entiy Sheets (in I.icensee C. Refueling 3-Automatic duam.
Event Repini (I.l?R) File (NilRI G-D Regulatiny Resisiction 4 Oihes (Explam) 0161l i
li Ope:atos l' raining & Liccuse lixaininatmo F-Asiminist ative 5
G Opciational Enos (lixplam)
'tislnbu ! - Same Somce j
19/17) 11 Othes li!xplain) t
50-315 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS D.C. Cook - Unit 1 UNIT NAME l-13-84 DATE DECEMBER, 1983 COMPLETED BY B.A. Svensson HEPORT MONTli TELEPl10NE 616/465-5901 j
PAGE 2 of 2 f
E E
u
.! E 3
$ $5 Licensee h,
Causc a Can sective 3
Action to No.
Date g
Eg d
,Ey$
Event g,y gO jE j;g Repunt #
mO Prevent Hecurrence t-g 6
covery, a turbine control problem 209 (C->ntinued) developed which limited reactor power l
to 76%. Reactor power was increased to 95% on 831230.
l I
l J'
i I
2 3
4 1:: Foiceti Reason:
Methuit:
Exhibit G Insisuctions S: St heilnleil A-l?ignipinesa I;ailuse(l.xplain) 14tanual for Pacpasaliun of Data ll4taintenance or Test 2-Mannal Scram.
Ent:y Slicets fos 1.icensee C.Ri. fueling
- 3. Automatic Saam.
Event Repos (1.l?R) FileINilRl!G.
D Regniaiosy Restricsion 4-Olher ( Explain) 0161)
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ILOpesatm I'saining & license lixamination 5
1 -Ailministrative G-Ope:a tional l i a ns (lixplain) 1.xliibit I - Same Somce I'l/ / / )
11 Othe. (lixplam)
p
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~ Docket No.: '50-315 g,;
4'
. Unit Namn D.. C.. Cook. Unit 11
~'
_p; Completed By:
G. J. Peak
- ' Telephone: :(616) 465-5901 Date:.
1/9/84 Page:
1 of 2
-MONTHLY OPERATING ACTIVITIES - DECEMBER 1983 F
Highlights:
The Unit entered the reporting period in Mode 5 with the Reactor Coolant 1 System' drained to~halfnloop..The scheduled
-l outage to repair the.#14 Reactor Coolant Pump and a Pressurizer Spray' Valve was in the second week.
The outage-lasted 3.5' weeks and the Unit was returned to service after overspeed testing of the Main Turbine.
All.three Pressurizer Safety Valves were removed, successfully tested and reinstalled during_the outage.
Major power = reductions-occured to clean the Feedpump' Turbine Condensers and to test the Main Turbine Control Valves.
Total electrical generator.for the month was 237,160 MWH.
4'
~
Summary:
12/1/83' VRS-1500,. Vent Stack Radiation Monitor was inoperable.for a two. hour period for Trouble Shooting.
12/9/83
'AB. Diesel Generator was inoperable from-1916 hours on 12/9 to'0938 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.56909e-4 months <br /> on 12/11 due to Low Lube Oil Viscosity
.which was caused by fuel' oil leaking into the' lube oil.
12/12/83 ' Entered Mode 4 at 1746.
12/15/83 Entered Mode 3 at 0222.
i 12/18/83 Reactor critical at 1057.
Entered Mode 1 at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />.
I-12/19/83 Paralleled Main Generator to'the System at 0053.
The Unit was'then taken off line at 1429 for overspeed testing of I
'the Main Turbine which was completed at 1541.
The Main Generator was paralleled again at'1557.
12/24/83-Reduced power from 75% to 55% to clean the feedpump turbine condensers.
i 12/25/83 Problems with the Turbine Load Changer caused the power increase to stop at 76%.
The Load Changer was repaired at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on 12/28 and the power increase resumed.
12/26/83 AB Diesel Generator was inoperable from 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> on 12/26 to'0321 hours0.00372 days <br />0.0892 hours <br />5.30754e-4 weeks <br />1.221405e-4 months <br /> on 12/27 for work on the Electronic Overspeed Trip.
i i
.p
4C lDockst~No.:
50-315
-Unit Ncm3
'D.
C.' Cook Unit 1 Completed By:
G. J. Peak Telephone:
(616).465-5901 Date:
1/9/84 Page:
2 of 2 12/30/83 LDCR-305, #4 Steam Generator Blowdown Sample Isolation 6
was inoperable for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period due.to an air leak on
-the valve.
ReducedLpower from 95% to 90% to test the Main Turbine-Control Valves.
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 4/5/83.
The back up CO System for the Control Room 2
Cable Vault remains operable.
The Control Room' Fire' Detection System remained inoperable as off1435 hours on'8/4/83.
Hourly fire patrols were-being conducted behind the Control Room Panels.
The system was declared operable at 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br /> on 1/4/84.
'The Fuel Handling Area Exhaust Fans HV-AFX-1 and 2, remained inoperable
- as of 11/2/83.
No operations-involving movement of fuel within the Spent Fuel Pit or. crane operation with loads over the Pit have occured.
i I
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4 4
DOCKET No.
50 - 315 UNIT bueE D. C. Cook - Unit No. 1 DATE 1-13-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE t'
t DECEMBER, 1983 M Pressurizer Power Operated Relief Valve, NRV-152, was leaking by.
Replaced the valve stem, plug, seat and gaskets. Had the valve tested.
M-2 Snubber, 1-GRC-S594, on the discharge line of a pressurizer safety valve was found with the fluid reservoir detached.
Re-placed the hydraulic snubber with a new one which was tested
' prior to installation.
M-3 Auxiliary Feed Valve, EM0-222, to #2 steam generator was leaking by..
Scating surfaces were reconditioned. Had the valve tested.
M-4 Pressurizer safety. valve Serial #N-56499-00-0001 was removed from the SV-45A position. The valve was. tested and popped at greater than 24G0 psig. The valve was sent to Wyle Labs for further testing. Spare safety valve Serial #RV-1-8010A was disassembled, cleaned, lapped and reassembled. The spare valve was also tested and installed in the SV-45A position.
M-5 Pressurizer safety valve Serial #RV-2-8010C was removed from the.
SV-45B position. The valve was disassembled, cleaned, lapped and reassembled. The valve was tested. The valve was sent to Wyle Labs for further testing.
Spare safety valve Serial
- RV-1-8010C was disassembled, cleaned, lapped and reassembled.
The spare valve was tested and installed in the SV-45B position.
M-6 Pressurizer safety valve Serial #RV-2-8010B was removed from the SV-45C position. When tested, the valve revealed excessive seat reakage. The valve was disassembled, cleaned, ~1apped and re-assembled. The valve was tested and again reinstalled in the SV-45C position, l
C&I-l Circuit 30 of the Containment Area Fire System had a frequent I
" Trouble Alarm" occurring. A bad terminator was found which was replaced with a new one.
C&I-2 Emergency diesel generator LAB tripped when paralleled to buses TilA and TllB. Engine overspeed trip target was displayed.
Electronic overspeed trip device relay case was found to have metal drips inside, which apparently were shorting the circuitry.
The case was cleaned. When tested, performance of the overspeed device was satis #ac, tory.
. =-
P,g DOCKET No.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE l-13-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 i
MAJOR SAFETY-RELATED MAINTENANCE DECEMBER, 1983
. C&I-3 Rod Control " Urgent Failure Alarm" was received and shut-down rod banks could not be withdrawn. The pulser card at A101 was re-placed and the alarm was cleared. When rods were stepped,
" Urgent Failure Alarm" was received at 2BD power cabinet due to blown fuse FU9. This problem was traced to defective oscillator circuit transistors Q and Q3 The fuse and transistors were 2
replaced.
C&I-4 Containment personnel airlock radiation monitor, R-2, failed due to a broken coaxial cable at'the detector. The cable was repaired and tested.
i I
N-
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s C(
C X INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 4654901 January 13, 1984 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 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of December, 1983 is submitted.
Sincerely, i
(j).
sv '
W. G. Smith, Jr.
Plant Manager WGS:ab Attachments cc:
'J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (NSAC)
R. C. Callen S. J. Mierzwa R. F. Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center T+?*$
.