ML20087M669

Monthly Operating Rept for Feb 1984

ML20087M669
Person / Time
Site:	Cook
Issue date:	02/29/1984
From:	Gillett W, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8403300155
Download: ML20087M669 (7)

Text

._

c.e=

.. ~ ~. 9 A. A.= =,,.,.o..

D "".t* "-'..N O. 50-316

% ~

DATI 3-6-84 CO.or_-.

-..v.

w

d n-- ' ?:wcr (3:W::: 3411

4. N:== i::: ?..;(Geo:s 5 W:):

1133

5. Dei;: 21:=.=! ? -";(Ne:11We):

1100

6. Y.:. _.

De : d:ble Q ::i:f (Cress SIWE): 1100 7

7. if:::i=== C:p=d:him t ------.- %: 31We):

1060

3. If Ch: ;n C:=:in C::::i:f R=is;:(I::== Ne.=h:: a 1.=u;:,) 5;::: I : R:per:, c;,e R:= ens:

9. Powe-!.:ve! To Whi:h R..=i==?.!! Any (N:: 5:We):

10. R==ons. ct R_-.=i::i ::.If Asy:

6 nis 51an:.: Y..to. Car Cc=*::ive ,1 l

11. Ec= != R. ::: i.; ?::i:d 696 1,440 49.425

12. Nc.=h:r Cf Hec = R==:r '":s C-::i:

672.2 1,416.7 39,201.4 i

13. Re::: K=c:ve sh::d=v r. H::=

0 0 0

14. Ec = Ce===== Ca.I.Isr 663.9 1,407.9 3g,2og

15. Uni; ?.:.:rve ih=:ds-u He.:=

0 0 0

16. Crc:s n==:! E==;r Cen:=: d f3:WH) 2,235,476 6.906.683 121.144.175,,,

17. con II4:=:=i I:e;y Cen:=::d r,.'4WE) 738,120 1,548,680 39,775,290

13. N : E::=i :1I:=;y Cc==: d (.*4WE) 711.OG7 1.495,371 38,348,742~

19. Uni: Sem=.:::.:r 95.4 97.8 14.0

20. Uni: Av:il:hi!!:7.::::r 95.4 97.8 7a: 0

21. Uni: C::::i f.' :::::(Usin; Sir C ;;et) 96.7 97.3 7g_7

22. Uni: Q::ci:y. :=:r(Usin CII :eti 93 1 94 4 69.5

23. Uni:. o:::d C=::;; R-:=

4.6 2.2 13.5

24. Ih::d:sr.s 5:.h:d=1 :: Cver Ne :. 5 sten:hs (Type. 2:::.::d 02:::::: or I::.h :

Refueling outage 3/9/84 90 days II. If Ih:: Ocwn A: I::d Cf Re:::: ?=i:d. I::i==: d ::: e( 3::.- ::: . E Cases In Tc:: S::: s iP :r to (~;==: :i:1 C;==::::1: Fore =st Acnieved 1.%............,, -.....w. m. Ih..,A w. .a4 C o... -.e.... ..s -... :........ .....u 8403300155 840229 DRADOCK05000g guf i h l AVERAGE DAILY UNIT POWER LEVEL I a = DOCKET NO. 50-316 UNIT 2 DATE 3-6-84 COMPLETED SY w. T. G111ett TELEPHONE 616-465-5901 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net) (MWe-Net) 1 1101 17 1o78 2 1100 18 134 3 1100 19 217 4 1096 20 1014 5 1096 21 1067 6 1098 22 1068 7 1096 23 1083 8 1101 24 1069 4 g 1099 25 1086 ~ 10 1092 25 1090 11 1090 27 1095 12 1101 28 1097 13 1080 2S 1101 14 1087 30 15 1094 31 10 1079 l INSTRUCTIONS On this femat list the average daily unit power level in hJe-Net for each day in the reporting month. Ccmoute to the near><t.ke1,-a-e. e 'g' ~ 50-316 DOCKET NO. UNIT SilUIDOWNS ANI) POWER REllUCTIONS D.C. Cook - Unit 2 uni r NAME DATE 3-8-84 COMPI.ElED HY B.A. Svensson HITOR I MON I'll FEBRUARY, 1984 TE11PilONE 616/465-5901 .$ E 3 $[ t itensee ,E s,, Cause & Coneclive No. Dale 9, E@ .S65 livent g? O3 Acuan to $5 5 jdg Repost # va' ' y' Psevent Hecturence d 146 840218 F 32.1 G 3 84-002 11J ZZZZZZ The Unit tripped due to an apparent high water level in one of the mois-ture separator reheater, MSR, shells. The trip occurred while recovering from an automatic l'olation of the s MSR coils due to a cycle upset fol-lowing turbine control valve testing. While attempting to repressurize the MSR coils an operating error was com-mitted which rapidly admitted full pressure main steam to the South set of MSR coils. It is believed that this caused a vibration that shook the MSR shell high water level trip switch which resulted in the Unit trip from a false indication of high level. No apparent damage resulted. The Unit was returned to service on 840219 and reached 100% reactor power nn En??n_ l 2 3 1 F: I oiced Reason: Mettuki: Exlobin G Insiinctiim S: Sclieduleil A Equipmer.: Failuse(Explain) l-Manual for Psepasation of Data ll-Mainienance oi Tesi 2-Manual Scrain. Ensay Sliceis foe 1.icensee C Refueling 3 Automatic Scram. Event Repose II.ER) File INURI G-D Regulaiosy Resuiction l-Oilies I Explain) 0161) ILOpesaios training & !icense lixamination F-Administiative 5 G Opesational linoi IExplain) Eslobis 1 - S.ime Somce c1/77) Il Other IExplain) s UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desente all plant shutdowns during the m 20:ordance with the table appearmg on the report form. report penod. In addition. it should be the source of explan. If category 4 must be used. supply brief comments. ation of sigmEcant dips m average power levels. Each signi. ficant reduction m power level (greater than 20% reduction LICENSEE EVENT REPORT :. Reference the applicable in average daily power level fer the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) rep nable occurrence pertammg to the outage or power should be noted. even though de umt may not have been reduction. Enter the Erst four parts tevent year. sequentja! l shut down completely. For suca reducuans in power level. rep rt number. occurrence code and report type) or the tive the duration should be listed as zero, the method of reduction part designation as desenbed in item 17 or, Instructions for should be listed as 4 (Other). and the Cause and Correcuve Preparau n f Data Entry Sheets for Licensee Event Report Action to Prevent Re urrence column should explain. The (LER) File (NUREG.0161). This informanon may not be Cause and Corre:nve Action to Prevent Recurrence column immediately evident for all such shutdowns. of course, since should be used to provide any needed explanation to fully rurther investigation may be reqmred to ascertam whether or desenbe the circumstances of the outage or power reduction. not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable oc:urrence. NU5tBER. Th:s column should indicate the sequential num-the posinve indication of this lack of correlation should be ber assigned to each shutdcwn or sigmdcant reduction m power noted as not applicable (N/A). for that calendar year. When a shutdown or sigm6 cant power SYSTE51 CODE. The system in which the outage or power reduction begms m one report pened and ends m another. ^ ~ an entry should be made for both report penods to be sure reduction onginated should be noted by the two digit code of all shutdowns or siamdcant power reducuons are reported. Exhibit G. Instrucuons for Preparanon or Data Entry Sheets Until a unit has 2:h'ieved its first power generation no num-f r Licensee Event Repon (LER) File (NUREG.0161). ber should be assigned to es:h entry. Systems that do not 6t any existmg code should be designa. ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable. of each shutdown or sigmneant power reduedon. Report as year. month, and day. August 14.1977 would be reported COSIPONENT CODE. Select the most appropnate component as 770514 When a shutdown or sigmficant power reduct:en from Exh it ! - Instructions for Preparanon of Data Entry begms m one report pened and ends m another, an entry shou!d Sheets for Li;ensee Event Report (LER) File (NUREG.01611. be made for both report pencds to be sure all shutdowns us:ng tne followmg entiena: or s:gmncant power reductons are reported. TYPE. Use "F" or "S" to indicate either "For:ed" or " Sche. duled." respectively, for each shutdown or signiScant power B. If not a component failure, use the related component. reducuon. Forced shutdowns include those required to be e.g.. wrong valve operated through error: list valve as initiated by no later than the weekend following discovery component. of an off.<tormal condition. It is recognized that some judg. ment is required in categonzmg shutdowns in this way. In C. If a cham of failures occurs, the first component to mal. general. a forced shutdown is one that would not have been function should be listed. The scouence of events.includ. completed in the absence of the condition for which corrective ing the other components which fail, should be desenbed I acuan was taken. under the Cause and Corre:nve Action to Prevent Recur. rence column. DURATION. Self. explanatory. When a shutdown extends beyond the end or a report penod. count only the time to the Components that do not fit any existmg code should be de. signated XXXXXX. The code 777777 should be used for end or the report penod and pick up the ensumg down time m the following report penods. Report duration of outages events where a component designation is not applicable. rounded to the nearest tenth of an hour to fac:litate summation. The sum of the total outage hours plus the hours the geners. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-tor was on line should equal the gross hours in the reportmg RENCE. Use the column in a narrative fasfuon to ampiify or pened. explam the circumstances of the shutdown orpower reduction. The :olumn should include the specific cause for each shut. REASON. Categonze by. setter deugnation in accordance down or siamilcant power reducuen and the immediate and with the table appearing on the report form. If category H contemplate'd long term correcuve acuan taken. if appropri. must be used. suppiy bner, comments. ate. Tlus column should also be used for a desenption of the major safety.related corrective mamtenance performed durma stETHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of ' REDUCING POWER. Categonze by numner designation the enucal path aeuvity and a report of any single release of, radioacuvity or smgle radiation exposure spectrically associ-INote that this differs trom the Edison E!ectne Insuture sted with the outage which accounts for more than 10 percent IEEI) detinitions of " Forced Parnal Outage" and " Sche. of the allowable annual values. duled Partial Outap/* For these tenus. eel uses a shange or For long textual reports continue narrative on separate paper .0 51W as the break pumt. For larger power reactors.30 31W and referense the shutdown or power reduonon for ttus

s t.u small a hanne to wanant esplanation.

narranve. IW77 -em--., .m d Docket No.: 50-316 Unit Names D. C. Cook Unit 2 Completed By: G. J. Peak Telephone: (616) 465-5901 j Date: 3/8/84 i Page: 1 of 1 MONTHLY OPERATING ACTIVITIES - FEBRUARY 1984 Highlights: The Unit entered the reporting period in Mode 1 with the reactor at 100% of rated thermal power. The Unit tripped on Feb. 18, 1984 due to high level in the Moisture Separator Reheaters while they were being put into service. A reactor startup commenced the next day and the Unit was subsequently loaded to 100% of rated thermal power where it operated the balance of the reporting period. Preparations are being made for the fourth refueling outage which is scheduled to begin on March 9, 1984. Total electrical generation for the month was 783,120 MWH. Summary: 2/18/84 The Unit tripped at 0256 hours0.00296 days <br />0.0711 hours <br />4.232804e-4 weeks <br />9.7408e-5 months <br /> due to high level in the Moisture Separator Reheaters while they were being put into service. 2/19/84 Reactor startup commenced at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. The reactor was critical at 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />. Mode 1 was entered at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />. The main generator was paralleled at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br />. 2/20/84 Power reached 100% at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. 2/22/84 Train A of the Containment Hydrogen Monitoring System was inoperable from 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on 2/22/84 to 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br /> on 2/24/84. The Control Room Cable Vault Halon System remains inoperable as of 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on 4/14/83. The backup CO System remains operable. 2 l - o. i. DOCKET NO. 50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 3-8-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 l MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1984 M-1 IM0-340, lE RHR Heat Exchanger to Charging Pumps failed to close two out of four attempts. The close torque switch was increased from 1.375 to 1.5. The valve was tested and re-l turned to service. M-2 2CD Diesel Jacket Water Heater would not maintain 150 F. The heater and cable were replaced. M-3 BD-101-3, #3 Steam Generatcr blowdown valve had a body-to-bonnet leak. The valve was repaired by Furmanite. l d e ~ -.._-_--.-.__.,__.__.a / n X INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman. Michigan 49106 (616) 465 5901 March 8, 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 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of February, 1984 is submitted. Sincerely, l$i f 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 l R. F. Hering l -J. F. Stietzel l PNSRC File l INPO Records Center j i .