ML17326A717

Monthly Operating Rept for Jul 1980

ML17326A717
Person / Time
Site:	Cook
Issue date:	08/04/1980
From:	Gillett B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326A716	List: ML17326A715 ML17326A717
References
NUDOCS 8008150355
Download: ML17326A717 (11)

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OPEK<TLNG DATA REPORT DOCK:"T YO. 50-316 DAT5E 8-4-80 .

COifPL TED BY TE ~~HOKE ~~901t

~R. G11

- -:--- . OPERATIC!G~iA i L~S D: C. Not s

l. Unit )lame:

2 Reporting Period: Jul 1980

3. Lfcaxsed The~sl Pov)er (liiY/t)t 3391 a

4. Nmnephtc R ting (Gross fDVe)t S. Desi@a EiewU Mn~ (Net s)DVe) t 1100

6. 5f~am DepentLtble Cspnc!Cy (Gross MYejt 1118

~sfamcaum XLa=~&McCnuociry fHer b.'sYe)r

8. IfCh~~esOcmrinCxFtci..r 8 t'~(items Yumbe SThrocgh I) SinceLsstReport. GiveRewonst

'"9 ~oeMevel"Fa Vhi"'t Rester ct~, If Any (Net MEVe):

'O ReswsSorKschtfons, L Any:

&month Yr.-to-Dat= Cumulative II. Ho) f's lÃRep'6rautt'Period. ~ 744

'IX Nu'r'nb~ OH.bT)~ Re ctor Yfw CririM 1S. Re"cps?'geese'e Sh'6:doves H os 0 0

= N~. Homs~~tttr Or)Zine 431. 9 '4 175.3 kZ U."dt RMMe Sittittfttwn Ho~

5, 0

" 16: GraSG Tlat'nGEn~y Gene. t ~'{bf>VH) MKB.K9= '5'5 M~ZOMZ6

'5 555 55 CamLas~.

T7. GrowEhe<~~c~y Gene~t& (i IWH} .

I8. i aerie"~Mal ~m"~ Gener't d (s'I'fVH) 427,116 4,285,826 14 053 238 l9. Unit'Sere') c:-"F'sctol 58. 0 73. 0

"~0-. Un~~'hbil~nuctor 58. 0 81 ..7. 73. 0 I. Un?~Xc af Octo'L (Usinan M+C Yet)

. UalrCtsafofO sar sos (Usfn ORR Nos/

~. Un@ ~ asa-d'Oasaoa Ros- 0 1.4 10. 3

~ '. Shutdowns Scheduled Over Next 6!tfonths (Type. Dote. cn Du:stion of'cch It

. ffShaMere Sad Of R="o:5 f:tfod, Bsi5nnsod O so of Ss-::oo: ~

S. Units ln Test Situs IPrior to Ccw-.-erchl Ope. tion): Forec" st Achieved Ib ITIAL CRIT)ICALITY I YITIAL ELEC ) R SCI~) ~

"CO.'t.'IERCIAL OPE:.ATION 355 .' 008150

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO'.

UNIT COMPLETED BY W. T. Gill tt TELEPHONE 616-465-5901 MONTH Jul v 1 80 DAY , AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net) (MWe-Net) 17 1020 18 980 19 368 20 1013 21 1018 22 1022 23 1044 8 24 1042 25 982 10 26 910 27 1042 12 28 1051 13 157 29 1031 14 994 '30 1036 15 1016 31 1032 16 1031 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.

l)OCKET Np.

UNIT SIIUTI)p)VNS AND Pp'SUER REDUCTIONS UNIT NAhII D C Cook-Unit 2 DATE 8-6-80 Cph(PLETED I)y B. A. Svens son REPpRT MpNTll JUlY s 1980 PllpNE 6 65-590 P)

Liccnscc Cause &. CoflccI Ivc 0Vl O Ds Action to l)atc Event Q J

RcPort Jr 2

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~ Prcvcot Rccurrcoce Cr 78 800627 N.A. zz zzzzzz Outage, continued from previous month.

Primary purpose for the outage was to complete auxiliary feedwater system modification. Unit returned to ser-vice 800713. Reactor power at 100%

800714.

79 800719 7.9 N.A. zz zzzzzz Reactor/Turbine trip. The reactor tripped due to low-low level in No. 1 steam generator. The low steam gen-erator level was caused by an appar-ent loss of steam supply to the east main feed pump turbine. The Unit was returned to power the same day.

Reactor power increased to 1005 800720.

80 800725 0 N.A. zz zzzzzz Reactor power reduced to 60Ã to re-move the east main feed pump turbine from service to check for feed pump turbine condenser tube leaks. One tube was plugged. Reactor power was returned to 'lOOX 800726.

3 I': Forced Reason hictbod: Exllibit G - Instructions S: Sclled<<lcd A-Erluipo)cnt Failure (Explain) I.Maoual f))r Preparatio>> of Dala Il.hlalotcoance or Test 2.hlaoual Scraln. I;otry Sllccts I'or Liccosec C-Rcfucliog 3-Autoo)atic Scralo. Event RePort (LI!R) File (NURI!G-D.Rcgolatory Restriction 4-OII!cf (Exl)IJn)) 016I )

E.OPeratl)r Training & License Lxaollolltloo F-Adolioistrative G Operational Llror (I:xplalo) 'Iixllibit I - Salo<<Soulce

(')/77) I l.ot lier (Lxl)IJul)

Ui fIT SHUTDOWNS AND POWER REDU ONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

report period. In addition, it should be the source ofexplan- 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 2'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 completelyl. 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 (NUREG4161). 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 futly 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 shutdov:n or signiiicant reduction in power noted as not applicable (N/A).

for that calendar year.. When a shutdown or significant power SYSTEiM 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 <<ode of an entry should be made for both report periods to be sure Exhibit G - Instructions for Preparation of Data Entry Sheets Jl shutdowns or significant power reductions are reported. for Licensee Event Report (LER) File (NUREG4161).

Until a unit has achieved its first power generation, no num-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 signiticant power reduction. Report as year. month. and day. August 14. 1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit I - Instructions for Preparation of Data Entry beginsin one report period 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 significant 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 oif-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. Selfwxplanatory. 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 for end ot'the report period and pick up the ensuing down time events wnere a component designation is not applicable.

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

CAUSE &, CORRECTIVE ACTION TO'PREVENT RECUR-The sum of the total outage hours pius the hours the genera- RENCE. Use the column in a narrative fashion to.amplify 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 specific 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 on the report I'orm. If category H ate. This column should also be used for a description of the must he used. supply briei'omments.

major safety.rehted corrective maintenance performed during the outage or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR the critical path ac:ivity and a report of any single release of REDUCING POWER. Categorize by number designation radioactivity vr single radiation exposure spe<<itieally associ-I Note that this differs i'rom the Edison Electric Institute ated with the outaae which accounts for more than 10 percent IEEI) definitions ot'Forced Partial Outage- and -Sche- of the allowable annual values.

duled Partial Outage." Fiir these tern>>. EEI uses a change oi'0 For long textual reports continue narrative on separate paper 4IW as the break poini. For larger power reactors.30 MW and reterenee the shutdown or power reduction t'or this is i>>o small a change t<> warrant explanatii>>i. liJ frJtlvc.

ket No.: 50-316 Unit Name: D. C. Cook Unit g2 Completed By: R. S, Lease Telephone: (616) 465-5901 Date: August 7, 1980 Page: Page 1 of 3 MONTHLY OPERATING ACTIVITIES -- JULY, 1980 Highlights The Unit entered the reporting period in a Cold Shutdown (Mode 5) outage. The Unit had been removed from service at 2307 hours0.0267 days <br />0.641 hours <br />0.00381 weeks <br />8.778135e-4 months <br /> 6/27/80 and cooled to Mode 5 by 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> 6/28/80.

The primary purpose for this outage was to permit comple-tion of the auxiliary feedwater modification, which will give each unit its independent auxiliary feedwater system.

The Unit was returned to service 7/13/80 which is detailed in the su@vary.

There was one other outage 7/19/80 when the flow reduced fromione'of the Mai'n Feed Pumps. This is also detailed in the summary.

Total electrical generation for the month was 443,530 MWH.

Summary 7/5/80 -- The Emergency Diesel Fire Pump was inoperable for a 29 hour3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> period, starting at 0647 hours0.00749 days <br />0.18 hours <br />0.00107 weeks <br />2.461835e-4 months <br />. This was for cleaning of the discharge strainer.

7/ll/80 After completion of outage work, Unit Startup was ini ti ated at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />.

7/12/80 -- The Reactor Plant entered Mode 4 at 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br />.

The Reactor Plant entered Mode 3 at 1912 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.27516e-4 months <br />.

7/13/80 -- The Reactor was critical at 1235 hours.

The Turbine Generator Unit was rolled at 1418 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.39549e-4 months <br /> and placed in parallel with the system at 1613 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.137465e-4 months <br />. Loading was increased to 100Ã power by 0510 hours 7/14/80.

7/17/80 -- The "CD" Emergency Diesel Generator was inoperable for a 7.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for replacement of a faulted thermocouple.

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ket No.: 50-316 nit Name': .D. C. Cook Unit ¹2 Completed By: .R. S, Lease Telephone: ('616) 465-5901 Date: August 7, 1980 Page: Page 2 of 3 7/19/80-- The Unit tripped at 0004 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to Low-Low level in ¹1 Steam Generator. This was caused by reduced flow from the East Main Feed Pump which was seen to be losing speed. Power level at time of trip was near 100'A. An attempt was being made to reduce loading to match the reduced feed-water flow.

Early analysis of the feed pump problem was that steam pressure regulating valve ARV-ll, which supplies steam to the feed pump turbine, had malfunctioned. Thorough check-out of the feed pump turbine and its steam supply could not identify any problem, and this pump was returned to service with the Unit.

The Reactor was retur ned to criticality at 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br />.

4 The Turbine Generator Unit was rolled at 0626 hours0.00725 days <br />0.174 hours <br />0.00104 weeks <br />2.38193e-4 months <br /> and placed in parallel with the system at 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br />.

The Unit was loaded to 50! power by 1159 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.409995e-4 months <br /> and held at this point while check-out of the East Main Feed Pump was taking place.

Unit loading was initiated at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />.

7/20/80 -- Unit was loaded to 100$ power by 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br />.

Valve IMO-910 (suction from Refueling Water Storage Tank to Charging Pumps) was inoperable for an 11.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period when the valve failed to stroke with power.

7/21/80 -- Containment Radiation Monitors R-11 and R-12 were inoperable for a 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> period while repairs were made to the filter paper drive.

7/23/80 -- The East Residual Heat Removal, System was inoperable for a 17 hour period for preventive maintenance.

7/25/80 -- The Fire Detection System of Engineered Safety Feature Ventilation Charcoal Filter HV-AES-1 was inoperable for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for necessary repairs.

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cket No.:~ 50-316 nit

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Name: D. C. Cook Unit k2 Completed By; ,R.,S. Lease Telephone: (616) 465-5901 Date: August 7; 1980 Page: Page 3 of 3 7/25/80 Unit loading was reduced to 604 over a 1.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting. at 2157 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.207385e-4 months <br /> to remove the East Hain Feed Pump from, service to check its,condenser for a:tube leak.

7/26/80 -- After plugging one -leaking tube in the Condenser of; the East Hain Feed Pump, the pump was returned to service and the Unit Loaded to 100/ power over a 5.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />.

7/30/80 -- The "AB" Emergency Diesel Generator was inoperable for a 5.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period for cleaning of relays.

Hain condenser halfs were out of service, one-half at a time, for a total of 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> during the re-porting period for location and repairs to circu-lating water leaks.

Prioi to the cold outage at the start of the report-ing period, the Unit was operating non-reheat due to,tube leaks in some of the reheater coils. Dur-ing the outage, four of the eight reheater coils were identified to have tube leaks. The leaking tubes were removed and tube sheets plugged.

Several attempts have been made to place the'oils in service but this has been unsuccessful. The Unit continues to. operate non-reheat.

DOCKET NO. 50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE ~8-6-80 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 PAGE MAJOR SAFETY-RELATED MAINTENANCE JULY, 1980 No. 1 steam generator blowdown regulating valve, DRV-312, had a body to bonnet leak. Lapped the valve seats and replaced all the gaskets.

Had valve tested.

M-2 A weld leak was detected downstream of a newly installed test valve on the discharge of the motor driven auxiliary feedpump. The 1" socket weld connection was rewelded and NDE was completed.

CS I-l Loop 3 protection channel II High Steam Line Flow status light was periodically received. MFP-130 calibration was performed and returned to service.

CSI-2 ILA-121, accumulator level indication was cycling between 50 and 60 percent. The redundant channel ILA-120 was remaining constant.

Transmitter ILA-121 was calibrated and returned to service. Normal control room indication was restored.

CRI-3 FRV-240, steam generator No. 4 feedwater regulating valve, was sticking in various positions. The valve actuator was replaced and proper valve operation verified.

C&I-4 The axial power distribution monitoring system failed to print the data. The power supply for the printer had failed. A spare power supply was installed and normal operation of the printer was verified.

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