ML20066D473
| ML20066D473 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 10/13/1982 |
| From: | Campbell D, Svensson B, Tetzlaff A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML20066D465 | List: |
| References | |
| NUDOCS 8211110360 | |
| Download: ML20066D473 (8) | |
Text
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, CPERAT:NC DATA R.EPORT
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,s 5 -315 DCC:
NO.
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10-4-82 W
CO.st?LETED SY A.L. Tetlzlaff.
TELEPHONg (616146si_sq01 o?E?r'INGS ATUS Nor:s DONALD C COOK UNIT 1
- 1. Uni: Nacs=.
- 2. Repor:in; ?: dad:
SEPTFMRFD 14M
- 3. Lh= sed Th=r...:! ?ower @iWt):
3250
~
1089
- 4. N =mi:ta R::in;(Cso:s S1W:):
1054
- 5. Desi;= Ee=d=1 R::ia;(Nec 51We):
1080 6.S M :un:Deye::d:bIe C:p:d:7 (Cross 51We):
1044
- 7. Sie-De: --d '!: r ---d f (Net 51We):
S. If C.=;;s Oc=rin Cap 2 i:7 R::=;s (1::=s Numb:.: 3 Th:ou;h 7) Sine: L:s R=por:. Give R:ssons:
- 9. Power L:ve! To Which R=s=ic:d,If Any (N:: 5twe):
- 10. R:: sons For R==.:: ions.lf Any:
This 5tonth Yr..co.Cara Cu==htive 22.0 6551 67.919
- 11. Ece:s != Repor:is; P::fod 94.9 3428.2 49.f01.4
- 12. Nu=i:. Cf Hours R==:r W:s C i:i=I 0
0 463
- 13. Re=er R=sene Shu:down Hou:s 13.7 3315.3 48.537.5
- 14. Hou:: Cene=: r Ca.Li==
- 15. Uni: R: serve Shutdown Ecu=
0 0
3??
12,755 10,517,817 140.881.006 Io. Cross Thc=.i E:::::y Ce===::d @iWM)
.s.150 3.456,570 46,338,250
- 17. Cross Ee===! E=- ;y Ce -W GIwal 2.709 3.3ac;_104 44,575,782
- 13. Net E===i=1 e-- ;y Cen==::d p WE)
- 19. Unit Serri=.::::or 1.9 50.6 73.7 1.9 50.6 73.7
- 20. Uni: Av:il:'i!Lr.::c:or o
- 21. Uni: C:: sci:y 5::: r (Usi=; 5!DC Net)
.36 48.8 66.6
- 22. Unit Caoscity F:::or(Usin; DER. Net)
.36 48.3 61.6 95.8 29.7 8.8
- 23. Uni: Fore:d Cu::;e Rat,
- 24. Shu: downs Scheduled Over Nen 5 Ston:f:s IType. 0:te. :=d Du::: ion of I:ch1:
- 5. If Shu
- Down A: End Of Repor: Period. Esti==:ed 3:te of St::=c:
.25. Units la Tes: 5:::us iPnor to Ce==er:!st Open: ions:
Fore =st Ac.ieve.
INITIA L CRIT'CALITY
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INITIAL E*.ECT2:0:7 CO..:.*.;IF.C:A. O ?IT..G;ON 8211110360 821013 PDR ADOCK 05000315 R
- PDR,
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-315 UNIT 1
DATE 10-1-82 COMPL:.TED BY Art Tetzlaff TELEPHONE 616-465-5901 MONTH September DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)
(MWe-Net) 1 0
17 0
2 0
18 3
0 19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
25 0
11 0
27 0
l 12 0
28 0
i l
13 0
29 13 14 0
30 102 i
i 15 0
31 16 o
l l
i
(
INSTRUCTIONS On this famat list the average daily unit power level in MWe-Net for each l
day in the reporting month. Ccmoute to the nearest whole megawatt.
i
DOCKEIMD. 50-315 IINIf SililllHlWNS AND POWEst HElltirllONS UNII~ N Ah!E D & Caok - Unit 1
~1_0-13-82 DAIE ruhlPI ETEl> HY B.A. Svensson September, l982 TEl.i.PilONE 616-465-5901 HI POn r AION HI E
E
.EE "h
f, N'ii i icemcc 54,,
[<3 ranse a canicuive 9
A gron so No.
Danc
[g g
,8 g E livuie 9y o
[b g$
- M Nep*HI J8 5$U U
Pievesel Itecus sens e P
O 185 820703 5
694.3 B&C 1
N.A.
ZZ ZZZZZZ The Unit was removed from service at 0146 hours0.00169 days <br />0.0406 hours <br />2.414021e-4 weeks <br />5.5553e-5 months <br /> on 820703 for scheduled Cont'd Cycle VI - VII refueling and main-tenance outage. Low power physics testing was performed on 820915 thru 820917. The Unit was not returned to service until 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br /> on 820929 pending completion of repairs to the North safety injection pump.
4 Reactor power was increased to 35%
for warming of the turbine-gennator prior to turbine overspeed testing.
186 820930 S
12.0 B
1 N.A.
ZZ ZZZZZZ Unit removed from service for turbine overspeed testing and repair of pres-surizer auxiliary spray valyc, QRV-51 The Unit remained out of service at I
the end of the month.
t 1
2 3
.I lh l'oncil Itcas.m:
hie hoil:
linintos G. Inseinconms S. Sthedulcil A l'epiipmes;i 1 ailme (I.nplain) 1.klannal los piep.n.oion og Isaia 11 klainicnance or Test 2 nlannal Sciam.
linisy Sheess im 1.icemce C-Itefncling
.1. Automatic Soam.
liven Itepon il l'p i l'ile (Niltu G.
D Hegulasmy itesuitsion 1 Oihes II!xplaint nit 1) l' Ope atm I'saining & l accuse 1 xaminaleon it A.iminist sainvc 5
Isinta I. L me S.nnce G Opciational Esios ll:xplamn 08/ / /)
11 Ollice(lixi.laini
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l UNIT SHUTDOWNS AND POWER REDUCTIONS LNSTRUCTIONS Th:s report snould des;nbe 2!! piant shutdowns dunng the a m:ordan: with 2e tab!e sp:earmg on de re: ort form.
report penod. In addinon,it should be the sour:e of explan.
If catepry a must be used. supply Or:ef::mrnents.
ation of sigmneant dips m 2verage power levels. Each si:m.
5:2nt redu:non m power level (greater $2n IM : eduction LICENSEE EVENT REPORT =. Reference me apph:2ble m 2 vers;e dady power :evel for the preceding 24 hnurs) report 2cle oc:urrence ;ensamg to &e outage or.powe{
could be noted, even dough te un:t may not have beth cou:non. Enter the m, *our pans (event year. sequenn:a shut down completely. For such reducuens in power leve!.
report numoet. a;:urrence ::de 2nd report type) of tne dve l
tne duranon should oe 'isted as :ero, the medod of redu:non pan desapanon as desenbed in Item 17 at Ins mnons i:t snould be listed as 4 (Other),2nd de Cause and Corre:nve Preparanon of Data Entry Sheets for Licensee Event Report Acuon to Prevent Re:urrence olumn should expism. The LLER) File (NUREG.0161). Th:s infor=2non may not se Cause 2no Corre:nve Acuon to Prevent Recur:ence column
= mediate!y evident for 211 such shutdowns. or course, smee should be used to provuie any needed explanation to fully rurtner mvest:ganon may be required to ascertam whetner or des:nbe the circumstances of de outage or power reduenon.
not 2 reportsole oc:urrence was involved.) If the outage or power reducnon will not result in a repcrtable oc:ur:en:e.
NUMBER. T'us olumn should indimte the sequential num.
the positive mdication of 6ts !ack of correlst:en should te ber ass:gned to each shutdown or signtilcant reduction m power noted as not applicsoie (Ni A).
for mat es!endar year. When 2 shutdown or s:gmticant power SYSTEM CODE. The system in whi:h the outage or power reduenon begms in one :ecort pened 2nd ends :n another.
redu:non ongmated should be noted.:y de two d:.g:t acce at.
an entry snoulo. be made tot both re: ort cenods to be sure or P eparanon of Data,.naty snees nmost G. Innmnons :.
L.l snutdowns or sta:nd;2nt power redu:nons are reported.
u for Lt;ensee Event Resort (LER) r, :Ie (NL, REC 4161).
.m nt:12 unit.i,,s 2:meved its fir:t power generation, no num.
ber should be assiped to each entry.
Systems dat do not fit say e.tst:ng : ode shoulo :e des:ps.
ted XX. The ;oce ZZ should be used for dose events where DATE. This column should =dicate de date of te start 2 system is not appii:2cle.
of each shutdown or sigmneant power reducuen. Report
- s year. month. and 22y. Aupst 14. Ic77 would be reported COMPONENT CODE. Sels:t me ecst 2;propr:2te ;omponent as ~T0514. When a shutdown or s:gmficant power redu;nort from Exhielt !. Instru:nons f r P:::aranon of Data Ent:3 begms in one report penod 2nd ends m 2nomer, an entry should Sheets for Licensee Event Report t'LE' ) File (NUREG4161).
R be made for both report penods to be sure all shutdowns using the followmg :nnena:
or ug:uncant power redu:hons are reported.
TYPE. Use "F" or "S" to indicate e:ther "For:ed" or " Sche.
duled." res:eenvery, for each shutdown or significant power B.
If not 2 :om:onent failure use de reisted om:enent:
reducuon. For:ed shutdowns indude those requaed to be e.g.. wrong valve operated through erron list valve as citiated by no later than the weekend rollowmg discovery comoonent.
of an off. normal :endinon. It is recogni:ed that some judg.
ment :s requued in :stegonz:ng shutdowns in bis way. In C.
If 2 : ham of failures oc:urs. me first :omeonent to mai.
general. 2 for:ed shutdown is one that would not have been function should be listed. The secuence of events.meluc.
completed in 2e absen:e of de condition for which or:ective ing de other components which fa21. snould be desenbed 2cnon was taxen.
under the Cause 2nd Correct:ye Action to P: event Recur.
rence column.
DURATION. Sel When a shutdown extends beyond the end or.f. explanatory.
Comeonents that do not fit any e.ustmg :cde snould.=e de.
2 report penod. count only the n=e to the signated XXXXXX. The ::de ZZZZZZ should be used for end or Me re ort penod and pic. up the ensumg down time m the r. i:owing report penods. Report durauon of outages designatton is not 2pe: c2:le.
events wnere 2 omeonent o
rounded to tne nearest tenth of an hour to fae:!itate summation.
CAUSE & CORRECTIVE ACION TO PREVENT RECUR.
the sum of the total outage hours pius the hours the geners.
RENCE. Use the column m a narranve fash:on to ampiify or tor was on line snould equal the gross hours in the report:ng expiam se cir:umstances of the shutdown orpower reoucnon.
penod.
The colur.n should mefude the spec:iic :ause for each shut.
down or stanid:2nt power reducuon and the immediate 2=
REASON. Catesonze as
-. tter deu4 nation m 4c:ordance
.e conte = isted long term corre:nve acnon taken, if approen.
- tth the tab.te 2 pearme on tne re:urt form. If :2tegory H ate. sms cosumn snould also be used tot a desenpt:en af tne rnust 5e used. sucpty bnef eumments.
maior safety.re!sted corre:nve mamtenance performee dunna e autsp or ; wu mcu:non mducma 2n : dent G= tion at}
METHOD OF SHUTTING DOwN THE REAGOR OR REDUCING POWER. Categonze bv numner designat:en the :nt:est patn 2:nyty and 2 report or 2ny smpe release at r20to2envity or smpe :2distion ex osure s:ee:nestly asses:.
1%e that this differs trom the Edison E'estne Insutut, atec with the out:ge wruca accounts for more tn:n !0 percent tEEll dedninons or " Forced Parnal Outage" and "Sene.
Ji2' 21!o*20k 2rmu21 values.
- uied Parnal Outan.* For enese tenm. eel uses a saange or For ions textusi re crts eentmue narrative an se:2rste ; 2:er
.0 MW 2s the cres not. For taryer power resetors.30 MW
.nd referense the shutcown or power recu nun im tm
.s em > mail a hanze to *2nant opianation.
narranve.
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i Docket No.: 50-315 4
Unit Name:
D. C. Cook UnitL1 Completed By:
D. R. Campbell Telephone:
(616) 465-5901 Date:
10/11/82 Page:
1 of 1 MONTHLY OPERATING ACTIVITIES - SEPTEMBER 1982 Highlights:
The Unit entered the reporting Lperiod in Mode 5 following the refueling outage. Core physic tests were. begun on September 13th. The' Unit was paralleled to the grid at 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br /> September 29, 1982, and loaded to approximately 35% to warm the turbine generator rotor in preparation for over speed tests. The turbine generator was removed from service at 1158 hours0.0134 days <br />0.322 hours <br />0.00191 weeks <br />4.40619e-4 months <br /> on September 30, 1982, and the turbine over speed tests were completed successfully. The reactor was then' shut down and the Unit cooled down to Mode 3 to make a repair to the Pressurizer Auxiliary Spray Valve. The Unit was returned to service October 1, 1982, 4
and is now completing the power escalation testing.
l The gross electrical generation for the month was 3,150 MWH.
Summary:
09/03/82 Reactor Coolant System being filled and vented.
09/15/82 Reactor critical at 0033 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> with low power physics tests in progress.
09/17/82 Entered Mode 3.
Various combinations of operating Reactor i
Coolant Pomps were obtained for testing of the newly installed Reactor Vessel Level Indicating System.
09/29/82 Reactor is critical at 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br />.
09/29/82 Unit entered Mode 1 at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, the turbine generator was paralleled at 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br /> and held at approximately 35% power.
4 09/30/82 The turbine was tripped at 1158 hours0.0134 days <br />0.322 hours <br />0.00191 weeks <br />4.40619e-4 months <br /> and turbine over speed tests were completed.
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DOCKET N0.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 10-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 3 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER,1982 M-1 The BIT outlet isolation valve to Loop 2, IM0-52, position indication was not correct.
Replaced the limitorque housing cover which was cracked and reset limit and torque switches.
M-2 Control air system containment isolation valve, XCR-103, failed to meet Type C leak rate test criteria.
Lapped the valve seating sur-faces, replaced the gaskets and repacked the valve. Had the valve retested.
M-3 The manual operator would not engage on the RHR heat exchanger cross-tie valve, IM0-314.
Investigation revealed that the bevel gear in the motor operator was broken.
Replaced the bevel gear and had the valve tested.
M-4 Accumulator isolation valve, IM0-110, was leaking.
Repaired bonnet leak, repacked and had valve tested.
M-5 Radiation monitoring system containuent isolation check valve, SM-1, failed to meet the Type C leak rate test criteria.
Replaced gasket and had the valve retested.
M-6 The clutch would not engage to allow handwheel operation of the RHR heat exchanger bypass valve, IM0-324.
Replaced broken bevel gear in the motor operator and had the valve tested.
M-7 CCW return line containment isolation valve, CCM-452, from RCP coolers would not operate.
Replaced the butterfly valve. Replaced the worm gear, drive sleeve and bearings in the motor operator. Had the valve tested.
M-8 The West CCW heat exchanger ESW outlet valve, WM0-737, leaked by.
Replaced the butterfly valve and had it tested.
M-9 Glycol containment isolation valve, VCR-10, operator had an air leak.
Replaced the operator diaphragm and had the valve tested.
M-10 CVCS letdown regulating valve, QRV-lll, had a body-to-bonnet leak.
Replaced the bonnet gasket and the bonnet studs and had the valve tested.
M-ll Steam generator blowdown isolation valves, BD-103-1, 2, 3 and 4, leaked by.
Replaced all four valves. Had necessary NDE performed and com-pleted leak test at operating pressure.
D0CKET NO.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 10-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 3 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER,1982 M-12 Threads were stripped out on a reactor coolant system, Loop 4 RTD well fitting.
Installed a welded cap on the fitting and had NDE performed.
M-13 Main feedwater check valve to #4 steam generator, FW-ll8-4, had a leak at the bearing cap due to the cup fastener holes being drilled too deep. Similar check valves, FW-llE-1, 2 and 3, also had fastener holes which were drilled too deep. Welded the bottom of the affected bolt holes, had necessary NDE perfomed and completed a leak test at operating pressure.
M-14 The North boric acid filter outlet valve, CS-422, was leaking; replaced the valve diaphragm.
M-15 The South waste gas compressor was reported to have a mechanical seal leak.
Replaced the compressor and had it tested.
M-16 Blowdown regulating valve for #1 steam generator, DRV-311, had a body-to-bonnet leak. Replaced bonnet gasket, repacked valve and had the valve tested.
M-17 The containment isolation valve to radiation monitor R-ll and R-12, ECR-31, was found to have a bent stem.
Replaced the s+
ilug and gaskets.
Lapped the valve seat and had the valve rete M-18 Blowdown regulating valve for #1 steam generator, DRV-311, had a bent stem.
Replaced the valve stem, packing and gaskets. Had the valve tested.
M-19 The dump valve for #2 steam generator stop valve, MRV-221, was leaking by.
Replaced the valve disc, seat and stem. Had the valve tested.
M-20 The normal CVCS letdown regulating valve, QRV-ll2, air operator was leaking.
Replaced the operator diaphragm and had the valve tested.
H-21 Pressurizer auxiliary spray regulating valve, QRV-51, had a body-to-bonnet leak. Replaced the valve gaskets and two bonnet studs. Had th7 valve tested.
M-22 Radio-gas detector sample containment isolation valve, ECR-31, was binding during operation. The valve stem was found to be bent.
Re-placed the valve stem and plug. Had the valve tested.
r DOCKET N0.
50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 10-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 3 of 3 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER,1982 M-23 The lower containment personnel airlock inner door equalizing valve was leaking by. Readjusted valve operating linkage and functionally tested.
M-24 An unacceptable indication was discovered in the main feedwater line to #2 steam generator. The indication was ground out and rewelded.
Necessary NDE was performed.
C&I-l Unit vent air particulate process radiation monitor, R-25, failed low. The detector connector wiring was repaired and a new scintil-lation tube and high-voltage power supply were installed to restore proper operation to R-25.
C&I-2 Diesel generator l AB power inverter failed, making the 1 AB diesel inoperable.
Four silicon controlled rectifiers and their respective diodes were replaced, along with the " transformer gate" and " shorting" printed circuit boards. The repaired system was tested first by simulating the diesel generator output power, and then by running the diesel. After a frequency adjustment, l AB diesei was declared op-erable.
C&I-3 Feedwater regulating valve to No. 4 steam generator, FRV-240, fai?sd to stroke within the prescribed 8 seconds closing titre.
It was dis-covered that the pneumatic booster associated with the valve had ex-haust orifice diameters of 5/32". This booster was replaced with a unit having the proper 1/2" diameter exhaust openings.
FRV-240 then closed within the alloted time.
C&I-4 Residual heat removal bypass cooldown regulator valve, IRV-311, had a broken airline which caused it to fail to the open position. Tne broken line was refitted to the valve bonnet. The valve was cycled and found to be satisfactory.
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