ML20066D322
| ML20066D322 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 10/13/1982 |
| From: | Murphy C, Svensson B, Tetzlaff A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML20066D306 | List: |
| References | |
| NUDOCS 8211110282 | |
| Download: ML20066D322 (9) | |
Text
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OPER.C?G DATA REPORT
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DCC:CrNo.
50-316 DA7:
10-4-82 J
COSiP's T.y A.t Tot 71aff
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TELI?HCNE 6mm_ con}
CPE7.AT!NG 5""ATUS DONAl.D C COOK UNIT 2 Notes g, ung, y,,,.
- 2. Reporting ? dod: SEPTEMBFR. 19A?
3391
- 3. L'~W Tts-+f Power (5tWr):
1133
- 4. Nz=eplate Rada;(Cross ?,1We):
1100
- 5. Desi 2Iled=1R::in2(Net 11We):
T 1118
- d. 312xfmure Depend 2W Caysci:y (Gross atWe):
1082
- 7. Siaxi==m Depte.hh! C p:ci:7 (Net 31We):
S. If Changes Oc:ar in C:paci:y F.:i:;s (Ita=s Nu:nhar 3 Throu;h 7) Sinca Last Repor:. Give Reasons:
2
- 9. Power Level To Whi=h Res::i:::d.If Any (Net 51We):
- 10. Rz: sons For R=d.:dar.s.lf Any:
This 5tonth Yr co. Data Cu=u!::ive 720 6551 41.615
- 11. Es ::s In Repe,r:ia; P::iod
- 12. Number of Hou:s R==:or W2s C:i&.g 677.4 5599.8 29.624.R
- 13. Re:cto.- Resene Shu::iown Hou:s 0
0 0
I
- 14. Hourscene=:sr on.use 667.6 5554.9 28.775.9
- 15. U..i: Re:erve Shutdown Ho==
0 0
n l
- 16. Cross The==:1 Enz ;y Centsted (3tKT) 2.241.332 18.314.699 92.375.520 719.040 5.980.690 29.688.490
- 17. Gross Ele==i=l Zser;y Genen: d G.tWH) a 693.705 5.770.748 28.614.889
- 15. Net IIe==i=1 I:=r;y Gene =: d C.tWc~-)
92.7 84.8 73.7 l
- 19. Unit Serri:= ?setor 92.7 84.8 73.7
- 20. Unit Av I12 bit:
F 7 :::or 89.0.
81.4 69.2
!. Unit C:pscity 7:c:or (Usi=: 51DC Net) 87.6 80.1 68.4
- 20. Unit Capacity.::::or(Using DER.4et) 7.3 15.2 14.4
- 23. Uni: Forced Cu::ge Rat,
- 24. Sh tdowits Se: eduled over Nec 5 Ston:hs (Type. D:te.:nd Du=:fon o(I:cht:
REFtlELTP.'G OUTAGE NOVEMBER 1982
~5. If Dtu: Down At End Of R= port ? :iod. I:ti==:ed D:te oists :up:
7
. 25. L* nits In Tes: 5:::us IPnor :o Ce==ercis! Oper::fon1:
Foreast Achieved iNITA L CRIT:CAUTY
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IN TIA L I.ICTR:C;W Cost:.t?J.C:A:. ?IRAT:CN t977i I
8211110282 821013 PDR ADOCK 05000316 R
3 AVERAGE DMLY UNIT POWER LEVEL DOCKET NO.
50-316 UNIT 2
DATE 10-1-82 COMPLETED BY Art Tetzlaff TELEPHONE 616-365-5901 MONTH SEPTEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)
(MWe-Net) 1 1052 17 1050 2
1056 18 716 3
1056 19 4
1057 20 153 5
1055 21 952 6
1056 22 1063 7
1058 23 1052 8
1058 24 1053 9
1056 25 1059 10 1049 25 1060 11 1046 27 1052
(
12 1046 28 1050 1051 13 1047 29 14 1045 30 736 15 1045 31 l
l 15 1050 INSTRUCTICNS On this famat list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
IMM'KEI NO. 50-316 IINil'SHullH)WNS AND POWI H MLilllCIlONS D.C. Cook - Unit 2 UNil NAklE 10-I3-SZ DATE cOberl LTED ay B. A. Svensson September, 1992 lEl.LPilONE 616-465-5901 1
HIPOHI AIONill PAGE 1 of 2 I iccusec 5,,,
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Date y,
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liven 3y 93 Aunin..
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ifi Itepade J8 WD U
Pievens Recusscshe H
t5 115 820918 F
32.9 A
3 N.A.
ZZ ZZZZZZ Reactor / Turbine trip. The reactor trip was due to low level coincident
! with steam /fecdwater flow mismatch in No. 21 Steam Generator caused by No.
21 S.G. feedwater reg. valve failing closed. Rain water during roof re-pairs had entered solenoid valve for feedwater reg. valve causing it to short and the valve to fail closed.
The Unit was paralleled at 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> on 820920.
116 820920 F
14.2 H
3 N.A.
ZZ ZZZZZZ Turbine / Reactor trip due to high-high level in No. 24 S.G. during manual steam generator level control.
Trouble shoot of the control systems did not reveal the problem. During a subsequent outage, problems were found in the feedwater regulating valve booster relay.
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17 Ioncl iteason:
bleshnil:
Eminine G - Isnesm tions S: L heihileil A l' luipmes.1 1 asluie (Laplain)
I klaimal hu Psepasalion of Data 16 klaintenance or Test 2 klanual Sesam.
Esitsy Sheets Ine I.iscance r Refneling
.1 Aulumane & sam.
liven Rep.no (I l'Rl 1 ele iNtIRI G.
D llegulaeosy itestsidion 4 Othes (limplami 0161)
I Opes.stos l'eaining& Iitense 1 xamination 12 Ailmunsteative 5
hinhas 1 Same Somce G Opesassonal 1.seus Ilinplaint P8/I/)
11 Ot hes (lisplain t
UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desen:e 2!! ;isnt shutdowns hnng te
- t 2:::rdan; Mth de table ac:earms on the report form.
report penod. In addinon. It should be tne sour:e of explan.
If estepry 4 must be used. suppiy bnef::mments.
atton of ugrunesnt dips :n average power levels. Esd saps.
LICENSEE EVENT REPORT :r.
Reference the app!!cabie S:2nt redu:non :n power level Qrester dan 209 reduenon
- n aversp daily power level for the pre ding 24 hnurs) reportsole a::urrence pensem; to the outsge or power reduction. Enter the drtt four ;2rts (event yest. sequent:21
- hould be noted, even though de amt may not hase been snut down completely!. For sa
- n reducuens in power level.
report numcer, occurrence :cde and report type) of tne nye tne durstion should be 'isted as zero,the medod of reducnon part denpanon as des:nbed in item 17 of Instruenons far should be listed as 4 (Other). 2nd the Cause 2nd Corre:nve Precarsuon of Dats Entry Sheets for Licensee Event Report Action to Prevent Re:urrence :clumn should explsm. The (LER) File (NUREG.0161). Th:s information may not se Cause 2nd Carre:nve Act:on to Prevent Recurrence coiuran immediately evident for all such shutdowns. of coune, smee should be used to provide any needed explanation to fully rurther mvestgation may be reoutred to ascertsm whether or desen' e the circumstances of the outsge or power reducnon.
rtet 2 reportsble oc:urrence was involved.) If the outage or c
l power redu:non will not result in a reportable oc:urren:.
NUMBER. T!us :olumn should indic:te the sequenn21 nurn, the pounve mdication of 6is !sck of :orrelanon should be her assigned to each shutdown or sigraficant reductica m power noted as not applicable (Ni A).
for mst eslendar year. When a shutdown or s:gmdesnt power SYSTEM CODE.
reduenon begms m one report pened 2nd ends in another.
The. system in wh::n the outsp or power.
reducuen ortsmated should be noted by the two dig:t code of an entry snould be made for both report penods to be sure Exmbit G. Insuuenons for Preparsuon at Data Entry ineets ul sautdowns or sigmnesnt power reductions are reported.
for Licensee Event Report (LER) File (NUREG4161).
Unt:1 a unit has ad;eved its Erst power uneration, no num-cer snould be assiF:ed to each entry.
Systems dat do not fit any existmg : ode should :e denps.
ted XX. The : ode ZZ should be used for dose events where DATE. This column should indicate de date of the start a system is not sppii: sole.
of each shutdown or sipidcant power reduenon. Report
- s year. month. and day. Aupst 14.1977 would be reported COMPONENT CODE. Seie:: ce most appropriate ;omeonent as 770514 When a shutdown or sigruficanc power reduccon from Exhibit !. Instru:nons for Preparanon of Data Entr>
]
begms m one report per:od and ends m another, an entry should Sheeis for Licensee Event Report (LER) File (NUREG.01611.
be made for both report penods to be sure 211 shutdowns usmg the followmg :ntiena:
or ugmficant power reductions are reported.
TYPE. Lse "F' or -S" to indicate either "For:rd" or " Sche.
duled." res e:nvely, for each sautdown or signiilcant power B.
If not a iomponent failure, use the reisted component:
reducuon. Forced shutdowns include those required to be e g.. wrong valve operated through error: list valve as mitisted by no later than the weekend fo!!owing discovery
- omponent, of an off. normal :endinon. It is recognized that some judg.
ment is required in :stegonzmg shutdowns in tius way, in C. If a cham of failures oc:urs. me drst component to mai-general. 2 forced snutdown is one that would not have been function should be listed. The secuence of events.me!ud.
completed in me absen:e of th :endition for which orrective ing the other components whl:h fail. should be des:nbed tenon was taken, under the Cause and Correcnve Acnon to Prevent Recur.
tence column.
DURATION. Self. explanatory. When 2 shutdown extends Comoonents tnat do not ilt any existmg code should be de.
beyond the end or 2 report penod, count only the time to the itsna'ted XXXXXX. The code 777777 should be used for end or de recort penod and pick up the ensumg down t:me events where 2 :omponent dengnanon is not sppii:scle.
m the foIIowmg report penods. Report duranon of outages munded to the nearest tenth of an hout to fac:litate summation.
CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.
she tum of the total outage hours plus the hours the genera.
RENCE. Use de de in a mm NW m @'y a tor was on line snould equal rne gross hours in the report:ng expism the e reumstances of the shutdown or power recuenon.
pen d.
The :olu t n should include the seec:ile :suse for each shut.
down or stpriicant p wer reducnon and the immediate 2no REASON. Categonze bv !etter deuynation in accordance with the rabie acpearmy on the report form. If :stegory H
'0"*Y*d
" E "" ** """" **"* " ' *N '"' 'I 2 PP " E"'
ste. arus clumn should also be used for a desenotion of tne must be used.sucpiy bnef eumments.
maior safety.re!sted corre:nve mamtenance performed durma the outsee or power reducnon me!uding sn :denttilcation of METHOD OF SHUTTISG DOWN THE REACTOR OR de ennest patn ae*my and a report at sny smgie re! esse :(
REDUCING POWER. Categortte sy numner despanon radioact:vity or smgle racist:cn ex=osure spectnesily nsee:.
1%e that this differs t om the Edison E!e tn: Insntate 2ted with the outage which accounts for more tnan 10 per;ent iEEll dedmtions of " Forced Parn.1 Outaae~ 2nd "Sene, of de 2iloww!e annual values.
Juled P:rtial Outay." For these terms, hEl uses 4 hange or For long textual reocrts eentinue narrat:ve on separate : ner
.0 MW as the ete2i pomt. For larger power resetors. 30 MW
.nd referen.e the shurcewn or power recu.avn fM t us
- s :m amail a.hange to *anant opianattoo.
narrattve.
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l IMEKET NO. 50-316 IlNIf SilUllHlWNS AND POWER REpirllONS UNil NAblE 0.C. Cook - Unit 2 nA1E 10-13-82 September, 1982 COnirl E1En ny B. A. SvenS10ll__
H L P Olt i kl O N iil
'IEl.t ralONE 616-465-5901 PAGE 2 of 2 E
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6 The Unit was returned to service at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on 820920 and reached 100% reactor power on 820921.
117 820930 F
5.3 A
1 Later HH PIPEXX Unit removed from service to repair a weld leak at the root weld for a drain line on the feedwater to No.
21 S.G.
The drain line is located between the S.G. and the isolation check valve. The Unit remained out of service at the end of the month.
I 2
3 4
1: l'onc.I Henon.
hietlient:
lialiil>is G - Isisisin la.ieis S. Lliciluic.I A I apupmes.: 1 ailine (1.nplain) 1-klanual I.u Psepasainen of Isaia 11 Mainicaance or Test 2 kl.inual Scsaus.
Entey Slicens een liensee r H fueling
.1 Auluin.stic & sasu.
1% cut Reims e il l'It i 1 ale INilHI G-D Hegulasuiy He>:sidion 4 Osines (limplanin 11161) l' Opesasos is.itning & lis caise I maminalion 1: Ailnuna.tsaine 5
ITintui 1 - Same Soma G Opciational 1:ssen lihplatul l'8/ / /)
11 ( Hirce (lixplain)
O UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report saculd desente 2!! ;! ant shutdowns dunng me m :::ordan:e with the ts:le ancestmg an the report form.
report penod. In addinon. tt should be the sour:e of explan.
If category 4 must be used. suppiy,br:ef::mments.
stson of ugmacant dips m average power lewis. E2:h upi.
L!CENSEE EVENT REPORT z.
Reference the app 12:2ble fi:2nt reducuon m power level (pe2ter than 20", reduction m 2ver25e daily power !evel for the preceding 24 hnurs) apcruole occurance pensamg to de outage' or power should be noted, even though te unit may not hase been nducuen. Enter the int four parts (event year. sequent::1 4
saut down completely!, For suen reducuens in power level.
report nur-her, oc:unence : ode and report type) of the n,ve tne durst;on mould be !!sted as zero.the method of reducuen part designation as descnbed in Item 17 of lastrucuons ::t should be listed as 4 (Other). and the Cause and Correeuw Papannon of Data Entry Sheets for L::ensee Event Repen Acuen to Prevent Re urrence :olumn should explam. The tLER) File (NUREC.0161). This mformauen mty not be Cause and Corre:nw Action to Prevent Recunence column immediately evident for all such shutdowns, of course sines should be used to provide any needed _ explanation to fully rurther mvesugation may be recutred to ascertam whether or desence the ;ircumstances of the outage or power reduction, not a report 2cle oc:urrence was involud.) If the outage or power reduct:en will not result in a reportable oc:urrence.
NUMRER. This coluren should indi::te the sequenus! nurn.
th' P052nve mdtcation of this lack of :enelation should be bet a:Wed to each shutdown or signaticant reduction m power [ noted as not applicab!e (N/A).
for that esiendar year. When a shutdown or s:gmilcant power SYSTEM CODE. The system in whi:h the outage or power reducuon begms in one report period and ends m another*
redu non ortsmated dould be noted oy the two digit eode of an entry should be made for both report penods to be sure Exnst G. Iristruenens for Paparsuon or. Data Enuy Shms ul shutdowns or stgrud: ant power reducuens are reported.
fu Lmsa Ennt Roon RER) Re NREGM Unt:14 unit has 2:h:eved i:s Srst ;ower generation, no num.
ber should be assigned to es:h entry.
Systems that do not nt any ex:stmg code should :e denps.
ted XX. The :oce ZZ should be used for those events where DATE. This eclumn should mdicate the date of me start a system is not appli:2 ele.
of each shutdown or signiScant power reduccon. Report
- s year. menth. and day. August 14.1977 would be reported COMPONENT CODE. Seis:t de most apptcpriate ;omponent as 770814 When a shutdown or upincant power reduccon from Exhibtt i. Instrucuens fer Preparatton of Data Entr>
begms m one report penod and ends m another, an entry should Sheets for LL.ensee Ennt Report (LER) File (NUREG.0161).
be made for both report penods to be sure all shutdowns using the followmg entiena:
or ug:uilcant power reducuons are reported.
TYPE. Lse "F" or "S" to indicate either "For: d" or " Sche.
duled." respe:tively. for each shutdown or signincant power it. If not a :omponent fat!ure. use the related ecmponent:
reducuon. Forced shutdowns include those required to be e.g., wrong valve operated through erron list valve as mitisted by no later than the weekend followmg discovery component.
of an off. normal conditton. It is recopized that some judg.
meat ts required in estegonzmg shutdowns in t!us way. In C. If a cham of failures occurs. the Erst comoonent to mai.
general. 2 forced shutdown is one that would not have been function should belisted. The sequence of' events.mciud.
completed in the absen:e of the :endition for which correcuve ing the other compcnents w!u:h (a11. should be desenbed acuen was taxen.
under the Cause sad Correcuw Acuan to Preunt Recur.
rence column.
j DURATION. Self-explanatory. When a shutdow extends Components that do not tit any exsstmg : ode snould be de.
m beyond the end or 2 report penod. count only the tune to the ugnated XXXXXX. The code 777777 should be used for end or the resort pened and pick uo the ensums down tune events where 2 component designation ts not appii:2cle.
m me followmg report penods. Report durauon of outages munded to me nearest tenth o(2n hour to fac:litate summation.
CANSE & CORRECTIVE ACTION TO PREVENT RECUR.
the sum ui the total outage huurs plus the hours the geners.
RENCE. Use the celumn in a narranve fashion to ampitfy or tot was on line should equal the poss hours in the reportmg expiam the circumstances of the shutdown or power recucten.
penod.
The column should melude the spect6c :2use for each shut.
- "E'
- "' E ""
REASON. Categurtze by !etter deitynstion :n ascordan:e e niemolated tong term correeuw scuan taken,if appropn.
1 witn the rabie appearmy un the report form. If :stegory H _
must be used.suppiy brzei eumments.
9'* "
'N maior safety.related correcuve mamtenance pertermed dunna the outage or ;cwer reducten me!uding an :dentatic: tion of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER. Categonee ov numner despanon
'A' #""'21 patn acumy 2nd a apon or any ungie niesa ei radioset:vtty or smpfe radiation exposure speettiesily assoc:.
1%te that this differs trom the Edison E:estne Institute sted with the outage which accounts for more taan 10 percent tEEli denmuons of " Forced Parnal Outsee' and -Sche.
of de allowso;e annual vslues.
l Juled Parttal Outage." For these tema. hEl uses 4,hange or For long textual recorts sontmue narrative on se:2r:te paper 20 MW as the break ;mmt. For larger ;ower resetors. 30 MW and reteren.e the shurcown or power recu uun im un
- s N 5. nail a.hange to wariant esplanattun.
narratave.
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Dock;t No.:
50-316 Unit Name:
D. C. Cs:k Unit 2 Completed By:
C. E. Murphy Telephone:
(616)465-5901 Date:
10/11/82 Page:
1 of 2 MONTHLY OPERATING ACTIVITIES - SEPTEMBER 1982 Highlights:
The Unit entered this reporting period at 100% power. At 1918 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.29799e-4 months <br /> on September 18,.the Unit tripped from Low Feedwater flow on #21 Steam Generator. The cause of the Low Feedwater Flow was found to be water contamination to the Level Control Circuitry, causing the Feedwater Regulating Valve to #21 Steam Generator to react as if the valve had received a Feedwater Conservation Signal.
On September 20, two Unit start-ups were commenced but were terminated due to high water level trips on #24 Steam Generator. The Unit was finally paralleled to the grid at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />.
100% power was achieved at 1036 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.94198e-4 months <br /> on September 21.
At 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br /> on September 30, a cracked weld was discovered on a one (1) inch drain valve located between the Main Check Valve and the containment on the Main Feedwater line to #21 Steam Generator. The Unit was removed from service at 1843 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.012615e-4 months <br /> and a Unit cooldown was commenced at 2116 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05138e-4 months <br /> in preparation for repairs.
Total electrical generation for the month was 719,040 MWH.
Summary:
09/09/82 The West CCW Train was inoperable for a 66.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period while Maintenance made repairs to CM0-420.
09/11/82 The Diesel Fire Pump start logic was inoperable for a 49.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for C&I repairs.
09/18/82 1918 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.29799e-4 months <br />, Unit tripped from Low Feedwater flow on #21 Steam Generator.
09/19/82 2253 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.572665e-4 months <br />, commenced Reactor start-up.
2313 hours0.0268 days <br />0.643 hours <br />0.00382 weeks <br />8.800965e-4 months <br />, Reactor cri tical.
09/20/82 0105 hours0.00122 days <br />0.0292 hours <br />1.736111e-4 weeks <br />3.99525e-5 months <br />, Mode 1.
0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br />, Paralleled Unit to the grid.
0417 hours0.00483 days <br />0.116 hours <br />6.894841e-4 weeks <br />1.586685e-4 months <br />, Unit tripped from extreme high water level on
- 24 Steam Generator.
0853 hours0.00987 days <br />0.237 hours <br />0.00141 weeks <br />3.245665e-4 months <br />, commenced Reactor start-up.
0916 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.48538e-4 months <br />, Reactor critical.
1002 hours0.0116 days <br />0.278 hours <br />0.00166 weeks <br />3.81261e-4 months <br />, Mode 1.
1054 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.01047e-4 months <br />, Unit tripped from extreme high water level on
- 24 Steam Generator.
1 1509 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.741745e-4 months <br />, commenced Reactor start-up.
1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, Reactor critical.
1623 hours0.0188 days <br />0.451 hours <br />0.00268 weeks <br />6.175515e-4 months <br />, Mode 1.
1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, Paralleled Unit to the grid.
r Docket No.: 50-316' Unit Name:
D. C. Cook Unit 2 Completed By:
C. E. Murphy Telephone:
(616) 465-5901 Date: 10/11/82 Page: 2 of 2 09/21/82 1036 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.94198e-4 months <br />, 100% Reactor power.
09/30/82 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br />, started removing Unit from service to repair Feedwater leak.
1843 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.012615e-4 months <br />, Unit manually tripped.
2116 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05138e-4 months <br />, Unit cooldown started.
r DOCKET N0.
50 - 316 UNIT NAME
- 0. C. Cook - Unit No. 2 DATE 10-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER,1982 M-1 The equalizing valve for the upper containment personnel airlock inner door was stuck open. Adjusted the valve linkage and had the airlock tested.
M-2 Steam generator #21 had indications of tube leaks.
Plugged t10 tubes; row 1, columns 71 and 72.
M-3 The West CCW heat exchanger outlet valve, CM0-420, would not close.
Replaced burned-out motor and had the valve retested.
M-4 A containment inspection during a forced outage revealed a body-to-bonnet leak on #4 steam generator shell drain valve, BD-101-4, in the blowdown system. The leak was sealed by Furmanite injection.
M-5 A leak occurred in the main feed line to #1 steam generator. The leak was from a socket weld on a one-inch drain line that could not be isolated from the steam generator. The Unit was shut down and the weld was ground out. A new drain line and valve were installed. The nec-essary NDE was performed.
C&I-l Feedwater regulating valve FRV-210, steam generator No.1, had an inter-mittent short-to-ground on "AB" battery. Water was found to have entered "B" train conduit and also a solenoid coil, which had then burned out, causing the valve to close. The water was removed and the coil was replaced. Conduits and coils for FRV's 220, 230, and 240 were likewise checked and repaired and dried as necessary. The flex conduit was wrapped with waterproof tape to prevent recurrence of the problem. The water entered the building during roof repairs.
C&I-2 Residual heat removal header "E" flow indicator IFI-330, read 800 gpm I
with no actual flow. The entire instrument loop consisting of flow transmitter, square root extractor and control room indicator was
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recali brated.
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