ML17319A543

Monthly Operating Rept for Jul 1980

ML17319A543
Person / Time
Site:	Cook
Issue date:	08/04/1980
From:	Gillett B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17319A542	List: ML17319A540 ML17319A543
References
NUDOCS 8008180550
Download: ML17319A543 (8)

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OPe<<TLXC DaTA Re~ORT DOCK:-T iO. 50-315 DAT:" S-4-BO CO~IPL" =D "~ ~B.

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~t 02:-RA:T~4 G S i A iM i fores Unit i D. C. Cook Unct fan"'eporting P-":odt Ju1 3250 0~ The..al?o (I) IYt)t Naaet)late Mg (Gsoss I')DYe)t 1054 5, Design Bead R" ing (Net sbIYr'e) t 1080 6.

I~ maxim~ D MeM C='c-"e Phs UM'Ne)i:

IfCrw"es Ocar in Cape:.(.'ht y (Item (ticker S Thou~> I) Siac" Last Repor.. Give Rwonst

'" - "- 9'.-Paore~vel'opi 'z R<<s '~,If Any (';iet ADYe):

IO; R~wa'."m ~chas, IfAny:

This it)oath Yr.wo-Dat=. Ci)~L.tive.

'1; Ho ~I.". Rt~r)A-.iag P .":od 0 3 207.9 IZ. i fe"..o~~ Qf'EoGeRe"ctor Yf~w. C;:W 0 463 I~.; Re au~~~4ha<ovvn Ho'-'a I .'oa~am~~iMe 0 tR U."it5~~hatdo~ Hots 10,118,931 99 185 236

'M: Gross It)'~tR.".=~y Cene.=td PI%)

'7. Gros cia'Wm~e~ Gcaewt~ ('I)YH) 0 0 3 245 802 31 24 te. 4a'et~aJ =".=~ Geant~ ( I'IYc-.)

62. 6 1

75. 4

-'l9-. Unirlerrt"" ra):tor-- .6 75. 4 t)-.'ai~~'IaalL~L "cror

~Ua~aae~sar(Usia 60.

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MDC Her)

UriMztadg&~tor (Using DeR 4c:)

'0.3 61. 8 0 11. 6 7.3 Uni&n- Coat:e Rat

'4. Shatdo~xsSchedaied Over icxt 6."Ioa'.hs {Type. Date. aa Datcuon of E"ch)t oi Stamp A t) ~~L c.ad Of R" ort Pe:iod..Btiracted Date S. Units la Test Sea)as I P.":or to Ce......e~i l Ope-.tioa):

Foist Ac.'".ieved IliITIS,LCa.ii)C,'ITT INTIAL "=LeCTR!CITY 8 0 08

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AVERAGE DAILY UNIT POWER LEVEL DOCKET"NO.'ATE 8-1-80 COMPLETED BY W. T. Gi llett TELEPHONE 616-465-5901 MONTH Jul DAY . AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net) (MWe-Net) 17 18 19 20 5 21 22 23 24 25 10 26 27 12 28 13 29 30

-15 31 INSTRUCTIONS On this'format list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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UNIT SIIUTDOlUNS AND PO)UER REDUCTIONS DOCKET NO.

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~J1 . 1999 616 465-5901 TEI.EPilONE 9

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Llccnscc c~ Cause & (.orrc<<tlvc 99) o 9))

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No. l)ate CS 499 Event Action tl>

L o Rcpl>rt Jr C

0 ~ Prcvcnt Rccurrcncc

~ C/l g 160 800530 S 744 BII)C N.A. ZZ ZZZZZZ The Unit was removed from service for Cycle IV - V refueling outage at 2228 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.47754e-4 months <br /> EDT on 800530. The Unit remained out of service the entire month.

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4 I': For<<cd Rc Json: hlethod: Exhibit G - Instructions S: Sched>>lcd A-f<luipnlcnt Faihlrc (Explain) I -Manual I'or Prcparathn> oi Data II-hlaitttcrtance nr Test 2.Manual Scfanl. Lorry Shccts for Li<<ctlsec C-Rcfuclin(9 3-Autolnatic Scram. Event Rcport (LI!R) File (NURI.'G-D-RCI,tllatory Restri<<lion 4-Other (Explain) 016I )

E-Operator Train(I>I, &. Llccnsc Exanlhlation F-Administ rat ivc G.Operational Lrn>r (Iixplaitt) 'LXhibit I - Salne Soul<<e

())/77) II Other (Explahl)

UNIT SHUTDOWNS AND POWER REDUC i ONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report torm.

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

ation of significant dips in average power levels. Each signi ~

ficant reduction in power level (greater than 207'eduction 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 pertaining to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequential shut down cornpletelyl. For such reductions in power level, report number, occurrence code and report type) of the five the duration should be listed as zero, the method of reduction part designation as described in Item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG416l). This information may not be Cause and Corrective 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 ascertain whether or 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 or significant reduction in power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another, reduction originated should be noted by the two digit code of an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.

Exhibit G - Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num- for Licensee Event Report (LER) File (NUREG416I).

ber should be assigned to each entry. Systems that do not fit any existing 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 signiiicant power reduction. Report as year. month, and day. August i4. 1977 would be reported CO>>IPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit I - Instructions for Preparation of Data Entry begins in one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG416I).

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

or signiticant power reductions are reported.

A. Ifa component failed,use the component directly involved TYPE. Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power B. If not a component failure, use the related component:

reduction. 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 categorizing shutdowns in this way. In C. If a chain of failures occurs, the first component to mal-general, a forced shutdown is one 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, should be described action was taken. under the Cause and Corrective Action to Prevent Recur-rence column.

DURATION. Seifwxplanatoiy. When a shutdown extends Components that do not fit any existing code should be de.

beyond the end of a report period, count only the time to the

,signated XXXXXX. The code. ZZZZZZ should. be used .'or end oi the report period and pick up the ensuing down time events where a component designation is not applicable.

in the folio'wing report periods. Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.

CAUSE Sc CORRECTIVE ACTION TO PREVENT"RECUR-The sum of the total outage hours plus the hours the genera- RENCE. Use the column in a narrative fashion to ampiify or tor was on line should equal the gross hours in the reporting explain the circumstances of the shutdown or power reduction.

period. The column should include the soecific cause for each shut ~

down or significant power reduction and the immediate and REASON. Categorize by letter designation in accordance contemplated long term corrective action taken. if appropri-with the table appearing Un the report t'orm. If category H ate. This column should also be used for a description of the must be used. supply briei'comments.

major safety. related corrective maintenance performed during the outage or power reduction including an identification of METHOD OF SHUTTINC DOWN THE REACTOR OR REDUCING POWER. Categt>rize by number designation the critical path activity and a report of any single release of radioactivity L>r single radiation exposure speciiically associ ~

INoie that this differs i'rom the Edison'Electric Institute ated with the outage which accounts for more than 10 percent (EEI) definitions of -Forced Partial Outage" and -Sche- oi the allowable annual values.

duled Partial Outage." F>>r these tLrnis. I:Fl uses a change of For long textual reports continue narrative on separate naper

..0 NIW as the break pL>int. FL>r larger pL>>ver reactors. 30 MW and reference tlie shutdown or power reduction for tins is u>>> small a change t>> warrant cxpianatiL>>i. lla rfa tive.

(L)/7 I

cket No.: 50-315 Unit Name: ,D.,C. Cook Unit 81 Completed By: R, .S. Lease Telephone: (616) 465-5901 Date: August 7, 1980 Page: lof 1 MONTHLY OPERATING ACTIVITIES -- JULY, 1980 Hi hli hts The Unit has been shut down the entire reporting period for its fourth Refueling Outage. The time of shut down was 2228 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.47754e-4 months <br /> 5/30/80.

Electrical generation for the month was 0.

Summary 7/2/80 -- Reactor Head was set on the vessel at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />.

7/9/80 -- The Reactor Plant entered Mode 5 with the initial bolting of the reactor head.

7/20/80 -- Safety Train "A" blackout testing was successfully completed.

7/21/80 -- Safety Train "B" blackout testing was successfully completed.

7/23/80 Filling and venting of the Reactor Coolant System, from the ~~ loop level was initiated at 1812 hours0.021 days <br />0.503 hours <br />0.003 weeks <br />6.89466e-4 months <br />.

7/26/80 A steam bubble was formed in the Pressurizer at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />. System pressure was increased to 325 psig for hand rotation of the four Reactor Coolant Pumps. The 0'14 pump would not rotate when the maximum recommended manual force was applied.

7/27/80-- Reactor Coolant System pressure was reduced to 0 and the system drained to the 4 loop level by 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />. This was to allow inspection of the thrust bearing of the 5'14 Reactor Coolant Pump.

7/30/80 Filling and venting of the Reactor Coolant System was initiated at 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and completed at 1928 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.33604e-4 months <br /> 3/31/80.

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DOCKET NO. 50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 8-6-80 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1980, M-1 The stem on DG-227C,'1CD diesel jacket water sample valve was broken with the valve open. The valve was replaced.

NSW-244-3, non-essential service water containment isolation check valve failed Type C leak test. Seat and disc were lapped and valve reassembled.

NSW-415-2, non-essential service water containment isolation check yylye failed Type C leak test. Yalye body cleaned and new disc in-stalled.

M-4 No. 1 steam generator blowdown regulating valve, DRV-311, had a body to bonnet leak. Disassembled valve, repaired steam cuts and re-assembled with new gaskets. Had valve tested.

The reciprocating charging pump discharge valve, CS-386, was leaking by. Disassembled valve and lapped seat. Reassembled with a new stem and plug.

M-6 The sample pump for radiation monitors R-11 and R-12 would not run.

Replaced the pump and had it tested.

The motor driven auxiliary feedpump was inspected to check condition

,of the outboard pump bearing. Replaced the rotating assembly and tested the pump.

M-8 The west centrifugal charging pump had a broken shaft. Replaced the rotating assembly and retested the pump.

Safety injection check valves on the lines to the reactor coolant hot legs of all four loops, SI-158Ll, L2, L3 and L4 had body to bonnet leaks. Replaced bonnet gaskets in all four valves.

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