ML20090J053

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Monthly Operating Rept for June 1984
ML20090J053
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 06/30/1984
From: Gillett W, Might A, Will Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8407270377
Download: ML20090J053 (8)


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AVERAGE CAILY '.' NIT POWER LEVEL OCCXET NO.

50-315 UNIT 1

DATE 7/2/84 CCMPLETED BY A. Might TELEPHONE (616) 465-5901 MONTH June 1984

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DAY AVERAGE DAILY POWER LEVEL DAY (MWE-Net).,,

AVERAGE DAILY POWER LEVEL (MWe-Net) 1 1030 17 505 2

1029 13 3

1031 19 4

1030 20 5

1030 21 6

,n,n 22 10 7

1o29 23 477 8

1028 24 864 9

1021 25 1024 10 1019 25 1020 11 1028 27 1017 12 1030 23 1015 13 1030 23 1016 14 1029 20 1025 15 1029 31 16 1020 i

i INSTRUCTICNS L0n this format list the iverace daily unit pcwer level in MWe-Net for each day-in:the recortina month.

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DOCKETNO. 50-315 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook

' Unit 1 DATE 7-3-84 B. A. svensson JUNE, 1984 COMPLETER) BY HEPORT MON'lli TELErilONE 616/465-5901 PAGE 1 of I e.

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Y4 Licensee y r,,

Cause & Conective g

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n. 3 Action to No.

Dale o

3 dig Repost#

<E U Prevens Recurrence P

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3o 223 840616 F

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4 N.A.

HH HTEXCH Reactor power reduced to 58% to re-move the west main feed pump from service to check the feed pump tur-bine condenser for tube leaks. No leaks were found.

224 840617 F

121.6 A

3 84-008-0 IA INSTRU During the power ascension from the 6,

feed pump outage a reactor trip occur-IB red from 68% power. The cause of the trip was the failure of vital A.C.

instrument bus, CRID IV.

The CRID failure also caused safety injection actuation on Train A.

Following re-pairs to CRID IV and other unrelated maintenance, the Unit was returned to service on 840622 and 100% power was reached on 840624.

1 1

2 3

4 F: Fosced Reason.

Method:

Exhibit G -Instructions S: Scheduled A-Equipinens Fashue(laplain)

1. Manual for Psepasavion of Data ll-Maintenance of Test 2 Mann.1 Scrani.

Entry Sheets fos 1.icensee C. Refueling 3 Autoniatic Scram.

Event Itepusa ll.ER) File INllRI:G-D Regulasony Restriction 1-Othes (lixplam) 0161)

F-Opceasos l'saining & Iicense lixainination F-Ad ninistsalive 5

G Ope ational tissus Ilixplatn)

INlubis 1 - Same Somce 19/77) 11 Olhes I E xplain).

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UNIT SHLTDOWNS AND POWER REDUCTIONS j!NSTRUCTIONS This report sfiould descr e all plant shutdowns during the m 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 sigmficant dips a average power leve!s. Each siani.

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT. Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertainmg to the outage or powe*

should be noted, even though 'he t. nit may not have been reduction. Enter the 6:st four parts (event year, sequent:st

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shut dodn completely. For such reductions in power level, report number. occurrence code and report type) of the ttve the duration should be listed as zero, the method of reduction par *. designation as desenbed in Item 17 or, Instruccons for ihould be listed as 4 (Other) and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report l

Action ta Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause and Correcuve Acuan to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provne any n'eeded explanation to fully turther invesugation may be required to ascertam whether or describe the circumstanes 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 shoula indica:e the secuential num-the positive indication of this lack of correlation should be bet assiped to each shutdown or sient6 cant reduc'ttonin power noted as not applicable (N/A).

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

an entry should be made for both report penods to be sure reduction onginated sh'ould be noted oy the tw'o digit code of all shutdowns or sigmr. cant power reducuens are reported.

Exhibit G. Instructions for Preparation of Data Entry Sheets Until a unit..as achieved its fint power generation, no num.

for Licensee Event Report (LER) File (NCREG.0161).

ber should be assiped to each ent y.

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

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ted XX. The code ZZ should be used for those events where DATE. This column should in4cate th$ date of the start a system is not applicable.

of each shutdown or signincW.' power' reduction. Report as year. month. 2nd day. August A 1977 would be reported COMPONENT CODE. Select the most appropriate component as 770314 When a shutdown or sigm0 cant power reducuan from Exhibit ! - Instructions for Preparanon of Data Ent:3 begms in one repor' pened and, ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG4161).

be made for both report periods to be sure all shutdowns using the following critieria:

or sicmfcant power reductions are reported; A. If a component failed.use the component d:rectlyinvolved.

TYPE. Use "F" or "S" to indicate either" Forced" or " Sche.

duled." respectively, for each shutdown or signincant power B.

If not a component fatlure, 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. normal condition. It is recognized that some judg-ment is required in categorizr4s shutdowns in this +ay.

In C.

If a chain of failures occurs, the first component to mal.

~. Zeneral a forced shutdownponq that would not have been function should be listed. The sequence of events.includ.

completed in the absence of the condition for which corrective ing the other components which fail. shoula be desenbed

. accon was taxen.

under the Cause and Corrective Actio to Prevent Recur.

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retice column.

$URATION. Self explanator'y. When a shutdown extends (tyond the end of a report penod count only the time to the Components that do not tlt any existmg code should be de.

er!d of the report penod and pick up the ensuing down time signated XXXXXX. The code ZZZZZZ should be used for m the followtng report periods. Report duratPm of outages events where a component designation is not applicable.

rounded to the nearest tenth of an !"ur to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours p1us the hours the genera.

tor was on line should equal the grcss hours in *he reportmg RENCE. Use the column in a narrative fashion to ampitfy or j

penod.

explain the circumstances of the shutdown orpower reduction, The column should' include the specific cause for each shut.

REASON. Categortze 5r letteh destgatica 5 secordance down or significant power reducticn and the immediate and with'the table appearms on the inprt for t.- If cam 3ory H e ntemolated long term c trective acnon taken if approprn e

      • This column should also be used for a desenption of the must be used. supply br$f co'mments.)

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maior safety.related corrective maintenance performed dunng THE$ REACTOR OR the outase or power reduction includ!ng an ident Scation ot; i

METHOD 'OF SHUTTiM/ DOM *by number designation REDUCING POWER. Categonze the entreal path actinty and a report of any smgle release of t

radioactivuy e single radiation exposure specidesily assoet.

I I Note that this differs trom the Edisors Electrie lasutute ated with the outage which a: counts for more than 10 percent IEEI) detinitions of " Forced Partial"Optaee" anu " Sche.

of the allowable annual values.

Juled Partial Ourag" For these terms. stEl uses a shange of For long textual reports continue narrative on separate paper 10 MW as the break pomt. For larger power reactors. M.W

.md referena the shutdown or power redu tron for ini, is too small a shange to warrant.nplanativ9 narrative.

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Docket No.:

50-315 Unit Names D. C. Cook Unit 1 Completed By:

G. J. Peak

. Telephone:

(616) 465-5901 Date:

7/5/84 Page:

1 of 2 i

MONTHLY OPERATING ACTIVITIES - JUNE 1984 Highlights:-

The Unit. entered-the_ reporting period in Mode 1 at 100% rated thermal-power.

The Unit tripped and a Train.A Safety Injection

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. occurred on June 17, 1984 due to'the' failure of the'CRID IV inverter.

.The CRID IV' inverter failure was caused by a blown

. capacitor.' _The Unit was1 subsequently returned to service and as the reporting period came to an end the Unit was operating at 100% power.' A major power. reduction occurred to remove the West Main Feedpump1 from service for a condenner tube leak check.

. Total electrical generation for the month.was 607,910-MWH.

Summary:

6/7/84 The East Motor Driven' Auxiliary Feedwater-Pump was inoperable'from 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />.on 6/7/84 to 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> on 6/9/84 for work on the~ suction. safety valve.-

The CD Diesel Generator was-inoperable for a 5;5' hour 1

period:for work on.the; governor.-

6/10/84 The East Motor. Driven Auxiliary Feedwater.. Pump was

' noperable for a 6. hour > period due to an'inproperly.

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functioning emergency leak off-valve.

' 6/13/84 The CD Diesel Generator.was inoperable for a 20 hour-i

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period due to problems yjth the governor.

6/16/84 A powar. reduction to 58% at 5% per hour began at 2230' hours to remove the' West Main-Feedpump from service forL

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.a condenser tube 1eak check.

i 6/17/84' The 58% powernleveliwas' reached at'0745. hours.

The West I-Main Feedpumpl Turbine Condenser wasileak checked and.a" powerfincreasecstarted at 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />.

'During'this power-p increase at about 68%-'at.2034 hours0.0235 days <br />0.565 hours <br />0.00336 weeks <br />7.73937e-4 months <br />.the Unit. tripped and aLTrainlA'SafetyfInjection occurred.. TheJcause was the-

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failure ofithecCRID-.IVJinverter-which failedidue to a i

i blown capacitor.-

)

- 6/22/84

-The reactor.w'as made. critical again at'1423 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.414515e-4 months <br /> - Mode l-t l

was entered'at 2047 hours0.0237 days <br />0.569 hours <br />0.00338 weeks <br />7.788835e-4 months <br />.;;The Main. Turbine was rolled-

'at 2118 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05899e-4 months <br />.- = The Main Generator:was paralleled :atJ 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />.

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Docket No.:

50-315 Unit Name D. C. Cook Unit 1 Completed By:

G. J. Peak Telephone:

(616) 465-5901 Date:

7/5/84 Page:

2 of 2 l'

-Summary:

(continued) 6/24/84 The Unit reacted 100% power at 2040. hours.

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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 backup CO system for the Control Room 2

Cable Vault remains operable.

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l ;. f DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 7-3-84

_. A. Svensson COMPLETED BY B

TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JUNE, 1984 M-1 East Motor Driven Auxiliary Feed Pump test valve, #FRV-255, was found to be leaking through. Upon removal of the valve bonnet, pieces of metal were found holding the valve plug open. The piping was cleaned and inspected using a Bore-scope. FRV-255 was then reassembled installing a new plug, cage and gaskets.

M-2 East Motor Driven Auxiliary Feed Pump discharge check valve,

  1. FW-128, was observed to be leaking through. Inspection of the seating surfaces after disassembly failed to reveal any discrepancies. The piping was checked for foreign material, none was found. The valve was then reassembled and returned to service.

M-3 The ice condenser top deck door above Bay II was allowing air flow to enter into the ice condenser which caused ice build-up on the intermediate deck doors. Tape was replaced on the top deck door to prevent air / moisture leakage.

C&I-1 CD Diesel's inverter failed. Two l2) bad capacitors were found to be the problem. The capacitors were replaced.

C&I-2 During installation of RFC-12-1858 (renlacement of CRID in-verter commutating capacitors C-2) a laaking C-1 was found in CRID'I inverter. All capacitors 1. the bank were re-placed.

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IMOIANA & MICHIGAN EMLCOMLNY conald C. Cook Nuclear Plant P.O. Son 458, Bndgman, Mchgan 49106 July 3, 1984 Director, Office Of Management Information and Progran 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 June,1984 is submitted.

Sincerely, N-t4D W. G.

mith, Jr.L Plant Manager UGS:ab Attacbments cc:

J. E. Dolan i

M. P. Alexich R. W. Jurgensen

-NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Hierzwa 1R. 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 ANI. Nuclear Engineering Department

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