ML20100L850

Monthly Operating Rept for Oct 1984

ML20100L850
Person / Time
Site:	Cook
Issue date:	10/31/1984
From:	Climer, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8412120106
Download: ML20100L850 (8)

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.DCC:I No. 50-316 Da.4_- 11/3/84 ..

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1. Uni:N:==: ~ Donald C. cook" Unit 2 Nor:s ,

. . 2. Repor:i=;?: dad: October 1984

3. ' *--- -d Ti-- ' ?swer C.tW::: 3411 ,.

4. N ===!:i: ?d.;(Cro:s 5:W:): 1133 .

5. Desi;=II::=i=!?d.;(Ne 11We): 1100

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6. 3'- " =:= Dry ==d..ht C:p:d:7 (Cicts 31We):

1100 T. Sf:xi== De;=d:-h!: r ---- 7 ry:: 3 we): 1060 3 8,. If Ch=:;:: C:=:in C:Mf R::i=;: (1: =: Ne. ah:: 3 Th::=;h 7) 3;::: I =: R:per:. Cive R:= ens:

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9. Power Leve! To Whid R==i==d. !! Any (N:: 3:W:): * .

10. R=:oas Toe ?.. =i:d:=.1f A.w: . .

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! - T'..is Stand Y:..<o.cas: . ce==!=ive

!!. Ho== != R:ponia; ?:d:d 745 7.320 59,904

12. Nu=ht.- Cf Hoc = R==:r W:s Cdd=.1 . 745 4,327.4 42,112.6

'13. R==:r R=e. e Sh:: des.n E=== . 0 0 0

14. Ec = Cc===::: Ca.! *=, 745 4,241.U 41,041.9

- 15. U:!: R::.:. e Sh=:down Ec= 0 0 0

. 16. Cross Th_._ ! I==;y C4===::d O1WE) 2,423,846 13,913,558 129,962,680-

17. Crost II :=i=!I:=;7 Gent =::d G.!WE) 792,10n _ 4,525,650 42.752,260 l 13. N :II::=i=!I:=;y Cc===::d C. WE) 763.916 4,367,243 41,220,614 l 19. Uni: Servi = .::=:r 100 57.9 71,3 I 20. Uci: Ari*.diII:7F =:or 100 57.9 71.3 l 2!. Un!: C:p:=i:/7::::r(Us!=; >!rC Ne:P . , 96.7 56.3 68.1

22. Unit Cae:d:y 7:::::(Usin; OIF. <*4:3 9J 2 54.2 66.8 0 2.6

23. Uni: For::d C ::;e R : 12.8

4. Sh:: downs 5d:de!:d Cver Nc.u 5.%=:h (Type. 0:::.:=d 0==:n of 2:si: .

Surveillance and maintenance outace scheduled to start 12/22/84.

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Estimated duration - two weeks l

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e41212o106 841031

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-316 ' -

UNIT 2 DATE 11/3/84 COMPLEiEDBY climer' TELEPHONE 616-465-5901 MONTH october 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 1065 17 1065 2 1035 18 1072 .

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1064 1080

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1068 3077 20' 5 1069 21 1079 6 1072 22 1074 7 1069 23 1065 8 1067 24

~ _1076 9- 1054 .

25 1048 10 1066 25 818 11 1068- 791 27 12 1073 798 28 13 1071 813 29 1074 14 860-30 15 1066 31 1082 16 1053 -

INSTRUCTIONS On this famat list the average daily unit pcwer level in MWe-Net for each Cemnnea +, -

__ day in t.5e reportinn mnnv% _

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DOCKET NO. 50-316 ,

UNITSilUTDOWNS AND POWER REDllCTIONS UN8T NAME D.C. Cook - Unit 2 DATE 11-12-84 October, 1984 COMPLETED RY B.A. Svensson KEPORT MONTil TELEPilONE 616/465-5901 "L -

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- ,E E 3 Licensee h f., Cause & Cinacclive No. Date h Eg  % )YE {gE livent y?

idO 3 Action to Psevent Recmrence P

$$ gE j iy3 g Rep.HI # g b

151 841025 F 0 F 4 84-028-0 ZZ ZZZZZZ Reactor power was reduced to 80% as a precautionary measure due to a 17%

i deficiency in available au:tiliary feedwater flow under certain accident conditions involving a feedwater line break. A further reduction to 75%

for additional conservatism occurred on 841026. On 841029 the Unit was released to increase reactor power to 80% based on analysis performed by Westinghouse. Following the NRC's review of the analysis, the NRC 1 authorized the Unit to be returned to 100% power. The reactor power was restored to 100% on 841031.

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i 1 2 3 4 1: l'os ceJ Heason: Method: Exlubis G - Instinctions j- A-Equipmesa Failme(Explain) 1 Manual for Pseparalism of Data S: Scheiluleil ll-Maintenance of Test 2 Manual Scram. Entiy Sheels fm 1.icensee C Refueling .l Automatic Scram. liven Repost (I I!R) File INllRl!G-D Regulatoiy Restsiccion 4-Othes ( Explain) 0161) l li-Opesatos l'eaining & ljcense lixaminalion F Administsative 5 a'

G Operational linor (lixplain) lixtuliit I - Same Somce 19/T1) 11 Other (Explain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the :n accordance with the table appearmg on the report form.

report period. In addition,it should be the source of explan. If category 4 must be used. supply brief comments.

ation of signincant dips in average power levels. Each sieni.'

ficant reduenon in power level (greater than 20% reduction LICENSEE EVENT REPORT =. Reference the applicable in average . daily power level for the preceding 24 hnurs) reportable occurrence pertainmg to the outage or power should be noted, even though the unit may not have been reduction. Enter the Erst four parts (event year, sequent:21 shut down completelyl . For'such rrductions in power level, report number. occurrence code and report type) of the rive the duration should be listed as zero,the method of reducnon part designation as desenbed in Item 17 of instruenons for should be listed as 4 (Other) and the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Acnon to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause and Correcuve Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully further investigation may be required to ascertam whether ur describe 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 occurrence.

NUMBER. This column should indicate the sequential num- the positive indication of this lack of correlation should be ber assigned to each shutdown orsigmticant reduction m power noted as not applicable (N/A).

, for that calendar year. When a shutdown or significant power reduction begins m one report penod and ends m another, SYSTEM CODE. The system in which the outage or power

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an entry shomd be made for both report penods to be sure reduction onginated sh'ould be noted oy the two digit code of all shutdowns or sigmilcant power reductions are reported. Exhi.ott. G . Instructicas for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num. f r Licensee Event Report (LER) File (NUREG 0161).

ber should be assigned to each entry.

Systems that do not fit any existmg code should be designa.

ted XX. The code ZZ should be used for those events where DATE. This' column should ;ndicate the date of the start a system is not applicable, of each shutdown or signincant pcwer reducnon. Report as year. month, and day. August i.t.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or sigmficant power reduction from Exhibit i . Instructions for Preparanon of Data Entr>

begms m one report pened and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NCREG.0161).

be made for both report periods to be sure all shutdowns using the followmg cdtiena:

or sigmncant power reductions are reported.

TYPE. Use "F" or "S" to indicate either "Forerd" or " Sche-duled." respectively, for each shutdown or signifcant power B. If not a component failure, use the related component:

reduction. Forced shutdowns include those rest. ired to be e.g wrong valve operated through error: list valve as initiated by no later than the weekend following discovery comoonent.

of an off-normal condition. It is recognized that some judg.

ment is required in categorizmg shutdowns in this way. In C. If a chain of failures occurs. tne first component to mai.

general a forced shutdown is one that would not have been function should be listed. The sequence of events.includ.

3_ completed in the absence of the condition for which corrective ing the other components which fail, should be desenbed action was taken.

under the Cause and Corrective 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.

end of the report penod and pick up the ensuing down tune signated XXXXXX. The code 777777 should be used for in the following report penods. Report duration of outages events where a component designation is not applicable.

j rounded to the nearest tenth of an hour to facilitate summation.

The sum of the total outage hours plus the hours the genera. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-

• tor was on ime should equal the gross hours in the reportmg RENCE. Use the column in a narrative fashion to amplify or penod. explain the circumstances of the shutdown orpower reduenon.

The column should include the specific cause for each shut.

• n r5 n cant power %cdon and the immdate and REASON. CateEonze by letter deugnattun in accordance with the table appearing on the report form. If category H contemolated long term correenve action taken. if appropn.

must be used, supply bnet comments. ate. This column should alsc be used for a desenption of the l

major safety related corrective maintenance performed durma i

METHOD OF SHUTTING' DOWN THE REACTOR OR the outage r p wer reduction including an identification ot}

REDUCING POWER. Categonze bv numner designation the entreal path activity and a report of any single release et l_

radioactivtry or smgle radiation exposure speettically assoet-INote that this differs trom the Edison Electric insuture 3t'd *'th the outaae which accounts for more than 10 percent (EED dermitions of " Forced Panial Outage" and " Sche. of the allowsole annual values.

duled Partial Outage." For these terms. eel uses a shange of For long textual reports continue narrative on separate paper 20 MW as the break pomt. For 1.irger power reactors.30 MW and reference the shutdown or power reduetton fue im, l :s w small a Shange to wanant esplanation. narrative.

19'77 l

Dockht No.: 50-316

• ^ Unit Namas D.C. Cook Unit 2 Completed By: D. A. Bruck Telephone: (616) 465-5901 Date: 11-14-84 Page: 1 of 2 MONTHLY OPERATING ACTIVITIES - OCTOBER, 1984 HIGHLIGHTS:

The Unit entered the reporting period.in Mode 1 at 100%

of reactor thermal power. A major power reduction occurred because of a discrepancy in the Auxiliary Feedwater flow calculations resulting in a deficiency of approximately 17%-

in auxiliary'feedwater flow under certain accident conditions.

The Unit ended the reporting period at 100% rated thermal power.

Total electrical generation for the, month was 763,916 MWH.

SUMMARY

10-01-84 #2 CD Diesel was inoperable at 0507 hours0.00587 days <br />0.141 hours <br />8.382936e-4 weeks <br />1.929135e-4 months <br /> due to a failed inverter. The diesel was returned to service at 1844 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.01642e-4 months <br /> on 10-01-84.

10-01-84 #2 AB Diesel was inoperable at 1853 hours0.0214 days <br />0.515 hours <br />0.00306 weeks <br />7.050665e-4 months <br /> due to an injector problem. The diesel was returned to service at 0328 hours0.0038 days <br />0.0911 hours <br />5.42328e-4 weeks <br />1.24804e-4 months <br /> on 10-02-84.

10-09-84 #2 E Essential Service Water Pump was inoperable at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> due to low discharge pressure. The pump was returned to service at 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> on 10-11-84.

10-13-84 Turbine Driven Auxiliary _ Feed Pump was inoperable at 0350 due to trip and throttle valve not latching.

The pump was returned to service at 0912 on 10-13-84.

, 10-19-84 Turbine Driven Auxiliary. Feed Pump was inoperable at 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br /> due to steam leaks. The pump was returned to service at 1356 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.15958e-4 months <br /> on 10-19-84.

10-25-84 At 2039, power was reduced to 80% as a precautionary measure due to a 17% discrepancy in available auxiliary feedwater flow under certain accident conditions involving-a feedwater line break.

10-26-84 A further reduction to 75% occurred at 1814 for the same reason.

10-26-84 At 1855, power was reduced because:#24 accumulator boron concentration was out of specification. The accumulator was declared operable at 0055 on 10-27-84.

, 10-27-84 Power reduction stopped at 63% at 0123. Power then-returned to 75% at 0435.

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'[ Dockst No. ' 50-316 Unit Namn D.C. Cook Unit'2 Completed By: D. A.:.Bruck Telephone: (616) 465-5901 Date: 11-14-84 l- Page: 2 of 2 10-29-84 At 1630, the. Unit was released to-increase. power to 80%.

'10-30-84 At 1800, the NRC authorized.the Unit to return to 100%

power. The power increase started at 2048, delayed due a chemistry hold. ,

10-31-84 At 0025, power.was returned:to 100%.

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 2 system remains operable.

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, e DOCKET NO. 50 - 316 UNIT NAME D. C. Cook - Unit ~No. 2 DATE 11-13-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 -

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MAJOR SAFETY-RELATED MAINTENANCE" OCTOBER, 1984 M-1, Replaced fuel injector and fuel line on #1-F cylinder of 2-AB Emergency Diesel Generator. The engine was test.run to verify oil leakage had been eliminated.

M-2 No. 3 B. A. Transfer Pump was replaced by a rebuilt unit. De-fective pump will be rebuilt and returned to stock for, spare.

C&I-l The CD diesel inverter failed and C&I found one diode and~two" SCR's shorted. Replaced all four diodes and all four'SCR's.

Tested on load bank and placed in service.

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C&I-2 An intermediate range trip signal was being received from the Solid ~ State Protection System. An isolation board and memory board were replaced in the demultiplexing cabinet.of SSPS.

C&I-3 Terry' turbine trip and throttle valve solenoid operator would not latch up. The coils on trip solenoid 20X TDTV were found open preventing the latch-up. The coils were replac'ed.

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$zy,,, _ IN0iANA & MICHIGAN ELECTRIC C]MPANY Donald C. Cook Nuclear Plant P.O. Son 458, Bridgman, Michgan 49106

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' November 13, 1984 Director, Office Of Management Information and Program Contrel-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 l.6, the attached Monthly Operating Report for the Month of October, 1984 is submitted.

S*ncerely, bd- A W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc: J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee (NSAC)

R. C. Callen S. J. Mierzwa R. F. Kroeger B. H. Bennett P. D. Rennix J. H. Hennigan Z. Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department ges4

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