Text

Monthly Operating Rept for Dec 1978
	ML17317A874
Person / Time
Site:	Cook
Issue date:	01/03/1979
From:	Gillett W; INDIANA MICHIGAN POWER CO.
To:	;
Shared Package
ML17317A873	List: ML17317A872; ML17317A874;
References
	NUDOCS 7901170245
	Download: ML17317A874 (15)
	v • d • e

~

AV RAGE DAILYUNIT POWER LEVEL DOCV=TNO. '0-315 UNIT DAr" 1-3-79 T:"~ EnHONE Decembex 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe>>Net)

I 1032 1034 DAY AVERAGE DAII.YPOWER LEVEL

(~(We Net) 899 17 1038 10 13 16 1014 1032 1032 1033

'027 1031 1042 993 1047 155 588 631 780 285 19 20 30 31 1039 1042 1022 1043 1043 1021 0

0 0

0 306 l>NSTRU~iONS On this;orat. list;he averao daily >>nit p>>>i er led! rn.'I~Ye.Net ror each day in the r.pvrtrnz;n>>nth. C>>>nPure iu'he near st whole rnemwatt.

t<ir77)

g' Q 'y

OPERATING DATAREPORT DOCKET NO.

50 315 DAiE. 1-4->>

COMPLETED BY W. X r~et I:

TELEPHONE ~~i901 OPERATING STATUS

1. UmtName Donald C.

Cook 1

2. Reporting Penod..

December 1

8

3. Licensed Thermal Power (MV/t):

4. Nameplate Rating (Gross MWe):

S. Design Electrical Rating (Net MNe):

6. Maximum Dependable Capacity (Gross MNe):

7. Maximum Dependable Capacity (Net MÃe):

3 250 1,089 1 080 044 Notes

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through r) Since Last R port. Give Reasons:

9. Power Level To which Restricted, IfAny (Net MNe):

10. Reasons For Restrictions, IfAny:

This Month, Yr:to.Date Cumulative 744 8 760 6,589.0 0

563.8 6,443.5 19,781,598 6 524 570 6 286 963 533 412 73.6 73.6 68.1 4.4 1l. Hours ln Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0

I4. Hours Generator On-Line 1S. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (MWH)

18. Net Electncal Energy Generated {MKH)

19. Unit Service Factor

75. 8

20. Urit Avaihbility Factor ':!-

22. Unit Capacity Factor {Using DER Net)

68. 0

~H. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duction of Each):

35 064 27 211.7 463 26,413.3 321 71 337 791 23 289 660 22 337 177 7

78.2 68.5 64.4 6.2

25. IfShut Down At End Of Report Period. Estimated Date of Start p:

26. Units In Test Status IPrior!o Commercial Operation):

Forec st Achieved INITIALCRITICAI.ITY INITIALELECTRICITY CO.'IDIERCIALOPERATIOi4

(')I77)

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UNITSIIUTI)0'IVNSANI)POWEIt ItEI)UCTIONS IIEI'ORThIONTII ecember, 1978 l)OCKET NO.

50-31 5 fFLEPIIONF 616 - 465-5901 Sheet 1 of 2 in>>le t

rjhK 0 il>>

g 'J ej Qj

~ Ill g l5 Ln.'c>isi.'c I!vent Rcp>>II jf CQ

~J 0'o lA V

0 cj E~

O CJ (ia>>sc &, (oiicelivc Acth>>i lii Pfcvci>l Itcclllrci<<:c 140 141 142 781212 F

781216 F

781221 F

18. 5 12 '

A 3

G 4

N/A N/A N/A CH CB zz TURBIN I

HOTORX zzzzzz Unit trip due to trip of west main feed pump turbine.

Feed pump turbine. trip was due to failure of shaft driven oil pump.

Unit re-turned to service 781212.

Unit removed from service due to No.

4 R.C.

Pump upper motor bearing low oil level.

Unit returned to service 781216.

Reactor power at 100% 781217.

Rapid load reduction to 74K power due to trip of west main feed pump turbine.

Feed pump turbine tripped when the associated A.C. oil pump was removed from service.

Operator was not aware that shaft driven oil pump was not in service.

Reactor power returned to 100K 781221.

I': Foiccd S: Scliciliilcd ltcasoii:

A-f>I>>ipnicnt Fail>>re (Iixplaii>)

Il.hlaintcniolec of Test

('. Itcfnelli>II I) Itel,>>laloiy lteslriclion Ii Operator 1'lab>hit) & Ijceilsc Iixa>ilioatii>>i I"Ad>>iiiiistialivc (j Opcialioi>ai Eiroi (Iixpl;>in)

I I Other (I'xplah>)

h'lelhod:

I-hlaniial 2 hla>>oal Sera>il.

3-Aot>>>vatic Sera>>>.

4-Other (Expiai>>)

Exhibit (j - Instr>>ctions I'or I'rcpaia><I oi I);ita LollyShccls Ii>i I.ice>>sec live>>t Rcpijrt (I.I!lt)File (Nliltl:(I

~

OI C) I )

'IixliibilI - Sa>>>c Si>>>>ce

UNITSHUTDOWNS AND POWER REDUCTIONS

~ INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition. it should be the source ofexpian-ation oi signiiicant dips in average power leve!s.

Each signi-

,"icant reducuon in power !eve! (greater than 20% reduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have be n shut down completely i. For such reductions in power level, the duration should be listed as zero, the method of reduction shouM be listed as>>'Other),

and the Cause and Corrective Action to Prevent Recurrence column should exphin.

The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.

NUMBER.

This column should indicate the seauential num-ber assigned to each shutdown or signiiicant reduction in power for that calendar year.

When a shutdown or significant power reduction begins in one report period and ends in another.

an entry should be made for both reoort periods to be sure il shutdowns or significant power reductions are reported.

Until a unit has achieved its first power generation, no num-ber shouid be assigned to each entry.

DATE.

This column should indicate the date oi the start oi each shutdown or siimiftcant power reducrion.

Report as year. month. and day.

August 14. 1977 would be reported as 770814.

When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signiricant power reductions are reported.

TYPE.

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

duled." respectivelv, for each shutdown or sign!ficant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend following discovery oi an oii-normal condition.

It is recognized that some judg-ment is required in categorizing shutdowns in this way.

In general.

a iorced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.

Se!explanatory.

When a shutdown extends beyond the end oi a report period. count only the time to the end oi the report period and pic'p the ensuing down time in th<< following report periods.

Report duration of outages rounded to the nearest tenth oian hour to faciTitate summation.

The sum oi the total outage hours pius the hours the genera-tor was on line should equai the gross hours in the reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing un the report form. Ifcategory H must be used. supply briei comments.

METHOD OF SHUTTING DOWN THE REAC iOR OR REDUCING POWER.

Categorize by number designation INote that this diiters irom the 'Edison Eie iric Institute

{EEI) deiinitions oi -Forced Partial Outage" and

-Sche.

du!ed Partial Outage."

Fur these te:n>>. EE! uses

~ cliange oi

.0 ~IW as the break point.

For larger power reactors. ~0 MW is n>>i smail a hange to warrant cxplanatiiiu.

in accordance with the table appearing on the report !orm.

Ifcategory -'ust be used. supply briei comments.

LICENSEE EVENT REPORT =.

Referenc the app!!cable reportable occurrence pertaining to the outage or power reduction.

Enter the iirst iour parts (event year. sequential report number. occ rrence code and report type) oi the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets ior Lic nsee Event Report (LER) File (NUREi'G4161).

This information may not be immediately evident ior all such shutdowns, of course, since further investigation may be required to ascertain whether vr not a reportable occurrence was involved.) Ifthe outage or power reduction will not result in a reportable occurrence.

the positive indication oi this hck of correlation should be noted as not appiicable (N/A).

SYSTEM! CODE.

The system in which the outage or power reduction originated should be noted by the two digit code oi Exhibit G

~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416l).

Systems that do not iit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.

COMPONEiNT CODE.

Select the most appropriate component I'rom Exhibit I - instructions ior Preparation of Data Entry Sheets for Li<<ensee Event Report (LER) File (NUREG4!61).

using the followingcritieria:

A. Ifa component failed, use the component directly invoived.

B. If not a component failure, use the related component:

e.g..

wrong valve operated through error: list valve as component.

C.

If a chain of failures occurs, the first component to rnai-function should be listed. The seouence of events. includ-ing the other components. which fail. should be described under the Cause and Correcrive Ac'.!on to Prevent Recur-rence column.

Components that do not tit any existing code snould be de.

signated XXXXXX Tne code ZZZZZZ should be used for events where a

component designation is not applicable.

CAUSE 8c CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in a narrative iashion to ampiiiy or explain the circumstanc s of the shutdown or power reduction.

The column should include the specific cause ior each shut-down or significant power reduction and the immediate and contemplated long term corrective action taken. if appropri-ate.

This column should also be used ior a description oi the major safetv-rehted corrective maintenanc periormed during

he outage or power reduction including an identification of the critical path ae:ivity and a report oi any single release oi'adioactivity ur single radiation exposure speciiicaily associ
~
ated with the outage which accounts ior more than 10 erc n!
or the allowaole annual values.
For long textual reports cominue narrative on separate paoer and reierence the shutdown or power reduct tun iui tlui iiJ rrJ ttve.
19 I
UNITSI IUTI)01UNS ANI)P01UElt ItEI)UCTIONS ltEPOltT hlONTII December, 1978 l)OCKET NO.
UNITNAME l)ATE COMPLETE!) I)Y TFLEI'IIONE 50-315 1-10-79 616 - 465-5901 Sheet 2 of 2 l)JIC gr, Q
II J p
cl p
~ r/)
Llee llscl.')vc>>l ltcporl Jf
\\I p 0 Q p p
( ause Ec ( or)cclivc Aclio>> lo Pcc <<c c
143 781225
/F S=108
~ 3 F= 40.9 B/A N/A zz zzzzzz Unit removed from service-for scheduled outage to perform hydrau-lic snubber inspection, inspection of ice condenser lower inlet doors and miscellaneous maintenance.
Discontinued startup 781229 due to non-isolable steam leak on No.
3 main steam line drain valve re-quiring R.C.S.
cooldown.
Unit re-turned to service 781231.
I': I'ofccJ S: SCIICJ>>lcJ Itcas)>>I:
A-I:<Iuip>>)cnl I'ail>>re (Explai>>)
II-hlai>>ic>>a>>cc oi'I'esl
('-ltefucll>>g l).lteyilalofy Iteslriclll>>)
I: Opcfalor Ifal>>>>li'c I.u;c>>sc I:xa>>u>>al>>>>I I -AII>>)i>>isllalive (I Oi)c)JI>>)>>Ill I:i)of(I)xpla>>II II ()ll)cr(I:xplJI>>l hiclif>>J:
I -/via>>ual 2.hia>>ual Sef a)>>.
3.A>>lo>>)a lie Serai>>.
0 Olllcr (ExpIJI>>l I:xl>>bll G - Inslruel)o>>s fof Prep'Iral)I>>l ol')ala L>>lry Sl)eels for I.lcc>>scc I:Ve>>I [tepr)rl (I.l)lt)I )IC INllltl.'(s~
016ll
'Iixllii)i)I
~ Saloc S))u) cc
UNITSHUTDOWNS AND POWER REDUCTIONS LRSTRUCTIONS This report should describe all plant shutdowns during the report period.
In addition. it should be the source oiexpian-ation oi signiricant dips in average power leveh.
Each signi ~
icant reduction in po~er level (greater than
)0~(; reduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completely>.
For such reductions in power level, the duration should be listed as z ro, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.
The Cause and Correc:ive Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstanc s of the outage or power reduction.
NUMBER.
T'nis column should indicate the sequential num-ber assigned to each shutdown or signiticant reduction in power for that calendar year.
When a shutdown or significant power reduction begins in one report period and ends in another.
an entry should be made for both report periods to be sure Jl shutdowns or signittcant power reductions are reported.
Until a unit has achieved its first power generation, no num-ber shouid be assigned to each entry.
DATE.
This column should indicate the date of the start of each shutdown or signiiicant power reduction.
Report as year. month. and day.
August 14. 1977 would be reported as 770814.
When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signirlcant power reductions are reported.
TYPE.
Use "F" or -S" to indicate either "Forced" or "Sche-duled," respectivelv, for each shutdown or significant power reducuon.
Fore d shutdowns include those required to be initiated by no later than the weekend following discovery of an oif-normal condition.
It is recognized that some judg-ment is required in categorizing shutdowns in this way.
In general.
a iorced shutdown is one that would not have been completed in:he absence of the condition for which corrective action was taken.
DURATION.
Se!explanatory.
When a shutdown extends beyond the end oi a report period, count only the time to the end oi the report period and pick up the ensuing down time in the following report periods.
Report duration of outages rounded to the nearest tenth oian hour to facilitate summation.
The sum oi the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.
REASON.
Categorize by letter detugnation in accordanc.
with the tabie appearing on th>> report t'orm. Ifcategory H must be used. suppiy briet cominents.
METHOD OF SHUTTINC DOWN THE REACTOR OR REDUCING POWER.
Categorize by number designation INoie that this diiiers irom the Edison Eie tric Institut (EEI) detmitions of -Forced Partial Outage" and
-Sche-duled Partial Outage."
F()r these te: n~. EEI uses
~ change oi
0 MW as the break p()int.
For iar(.ef power reactors. 30 MW is t((() smail a change to warrant cxpianatio)).
in accordance with the table appearing on the report form.
Ifcategory 4 must be used. supply briei comments.
LICENSEE EVENT REPORT =.
Reierenc the applicable reportable occurrence pertaining to the outage or power reduction.
Enter the first iour parts (event year. sequential report number. occurrence code and report type) of the five part designation as described in Item 17 oi Instructions for Preoaration of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416!).
This information may not be immediately evident for all such shutdowns, of course, since iurther investigation may be required to ascertain whether or not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.
the positive indication of this lack of correlation should be noted as not applicable (N/A).
SYSTEM CODE.
The system in which the outage or power reduction originated should be noted by the two digit code oi Exhibit G - Instructions for Preparauon of Data Entry Sheets for License. Event Report (LER) File (NUREG4161).
Systems that do not fit any existing, code should be desiana-ted XX. The code ZZ should be used for those events where a system is not applicable.
COMPONENT CODE.
Select the most appropriate component horn Exhibit I
~ Instructions for Preparation of Data Entry She=ts for Licensee Event Report (LER) File (NUREG4161).
using the followingcritieria:
A. Ifa component failed, use the component directly involved.
~
B.
If not a component failure, use the related component:
e.g..
wrong valve operated through error: list valve as component.
C.
If a chain of failures occurs, the first component to mai-function should be listed. The sequenc oi events. inc!ud-ing the other components which fail. should be described under:he Cause and Corrective Action to Prevent Recur.
rence column.
Components that do not fit any existing code should be de-signated XXXXXX. The code ZZZZZZ shouid be used:or events where a
component designation is not applicable.
CAUSE k, CORRECTIVE ACTION TO PREVFNT RECUR-RE)(ICE.
Use the column in a narrative fashion to amplify or explain the circumstanc s of the shutdown or power reduction.
The column should include the specittc cause for each shut-down or signiticant power reduction and the immediate and contempiated long term corrective action taken. ifappropri-ate.
This column should also be used ior a description ot the major safety.related corrective maintenance periorrned during the outage or power reduction including an identification of the critical path activity and a report of any single release oi radioactivity or single radiation exposure speciticaily associ
~
ated with the outaae which accounts ior more than 10 percent oi the ~allowable annual values.
For long textual reports continue narrative on separate paper md.et'(.rence the shutdown or power reduction ioi ttii) llaffatlve.
(()t7
Docke o.:
Unit Name:
Completed By:
Telephone:
Date:
50-315 D.
C.
Cook Unit tl R.
S.
Lease (616) 465-5901 January 9,
1979 OPERATING EXPERIENCE -- DECEMBER, 1978 y'1' I Hi hli hts There were three outages during this period.
The first one, due to the loss of the East Main Feed Pump, lasted from 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months to 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months December 12, 1978.
The second one was due to loss of lubricating oil in the 84 Reactor Coolant Pump and lasted from 0538 hours0.00623 days 0.149 hours 8.895503e-4 weeks 2.04709e-4 months to 1808 hours0.0209 days 0.502 hours 0.00299 weeks 6.87944e-4 months December 16, 1978.
The last one was a scheduled outage which lasted from 0124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months December 25, 1978 until 0539 hours0.00624 days 0.15 hours 8.912037e-4 weeks 2.050895e-4 months December 31, 1978.
Summar 12/01/78 The Unit entered this reporting period operating at 995 power and 1070 megawatts electrical.
At this time we were experiencing a problem with Overpower/
Overtemperatureh T Indication Loop 3.
This power level was held at 99/ while the condition was being investigated.
The Turbine Driven Auxiliary Feed Pumo was inoperable for a 6.2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period to repair a steam trap isola-tion valve.
Radiation Monitors R-11 and R-12 were inoperable for a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period for installation of RFC-1375.
12/02/78 83 Steam Generator Stop Valve Dump Valve MRV-232 was inoperable for one hour to repair a leak.
12/03/78 Power was reduced to 855 for testing of Main Turbine control valves and the Unit returned to 995.
This power ascension was over a period of 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .
12/06/78 The CD Emergency Diesel Generator was inoperable for a
9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months period to work on by-pass lube oil filters and other minor repairs.
12/07/78 -- The North half of "A" Condenser was out of service for a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period to repair tube leaks.
The Engineered Safeguards Fan HV-AES-2 was out of service for a 16.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period to repair rollamatic filters.
12/08/78 The Engineered Safeguards Fan HV-AES-1 was out of service for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period to repair rollamatic filters.
Docket Unit Name:
Completed By:
Telephone:
Date:
Page:
50-315 D.
C.
Cook Unit 81 R.
S.
Lease (616) 465-5901 January 9,
1979 (2) 12/10/78 The Unit load was reduced to 905, 940 megawatts electrical, for a 13 hour1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months period to repack 813 Circulating Water Pump.
A spare temperature indica-tor on Reactor Loop 3 was placed in service which solved the Overpower/OvertemperatureT indication and the Unit was returned to 100% power, 1072 mega-watts electrical.
12/12/78--
12/15/78--
12/16/78--
The Unit tripped from 1005 power at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months from low steam generator levels after the West Main Feed Pumps had tripped due to loss of oil pressure.
Investigation found the shaft driven oil pump to have failed.
This shaft driven pump was removed with the intent of running the Turbine on the motor driven auxiliary.
The Reactor was returned to critical at 1529, the Unit paralleled at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months and power level increased to 65% until the West Feed Pump became available, 655 megawatts electrical.
The West Main Feed Pump was returned to service after performing overspeed tests on the Turbines.
Power was increased to 100K starting at 1155 hours0.0134 days 0.321 hours 0.00191 weeks 4.394775e-4 months .
At approximately 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months the bearings reservoir low level alarm on g4 Reactor Coolant Pump started alarming.
This was identified to be the upper reservoir.
This level could be monitored by tele-vision.
By 0300 hour0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months s-on December 16, 1978.
the level indicated it had dropped 0.5 inches.
The Unit was started down in power at 0322 hours0.00373 days 0.0894 hours 5.324074e-4 weeks 1.22521e-4 months and tripped at 0538 hours0.00623 days 0.149 hours 8.895503e-4 weeks 2.04709e-4 months .
The 4'4 Reactor Coolant Pump was removed from service.
The oil leak was found to be a loose fitting on the vent line between the oil cooler and the reservoir.
The leak was repaired and the oil level returned to normal.
The Reactor was returned to critical at 1516 hours0.0175 days 0.421 hours 0.00251 weeks 5.76838e-4 months , the Unit paralleled at.1808 hours0.0209 days 0.502 hours 0.00299 weeks 6.87944e-4 months and loaded to 49K power by 2120 hours0.0245 days 0.589 hours 0.00351 weeks 8.0666e-4 months .
It was held at this level due to an indicated quadrant Power Tilt in excess of 2X.
12/17/78 At 0007 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months the quadrant Power Tilt had diminished to less than 2X and loading of the Unit was started reaching 100'A at 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months .
12/19/78--
The diaphragm failed on Containment Isolation Valve YCR-21.
This is one of the glycol valves in the supply system to the Ice Condenser.
Glycol was isolated for a period of 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months while repairs were made.
Docket Unit Name:
Completed By:
Telephone:
Date:
Page:
50-315 D.
C.
Cook Unit 5'1 R.
S.
Lease (616) 465-5901 January 9,
1979 (3) 12/21/78 -- The Unit power was rapidly reduced to 75/ when the West Main Feed Pump Turbine tripped.
This was the Turbine that did not have its shaft driven oil pump and the control operator had not been informed.
He attempted to stop the running motor driven auxiliary oil pump.
The West Main Feed Pump was returned to service and the Unit returned to 100Ã power by 1940 hours0.0225 days 0.539 hours 0.00321 weeks 7.3817e-4 months .
12/24/78 The Unit was started down at 2132 hours0.0247 days 0.592 hours 0.00353 weeks 8.11226e-4 months for a
scheduled outage and tripped from 155 power at 0124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months December 25, 1978.
The Unit was cooled down to Node 5.
Major work accomplished during the out-age was Ice Condenser Inlet Door Surveillance, snubber inspection, replacement of pressurizer relief tank rupture diaphragms and repair of a stator cooling water leak.
12/28/78 Heatup.of the Unit was started and it passed into Mode 4 at 0350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months .
12/29/78 Full temperature was obtained and the Reactor was critical at 0920 hours0.0106 days 0.256 hours 0.00152 weeks 3.5006e-4 months .
The West Main Feed Pump Turbine had been repaired by replacing the shaft driven oil pump and this Turbine was speed tested.
At 1344 hours0.0156 days 0.373 hours 0.00222 weeks 5.11392e-4 months cooldown of the Unit was initiated because of a severe bonnet leak on a main steam line drain valve which was upstream of the 5'3
'team Generator Stop Valve.
The Unit was in Mode 4 at 1924 hours0.0223 days 0.534 hours 0.00318 weeks 7.32082e-4 months .
12/30/78--
The leaking valve was repaired and heatup started at 0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months .
Mode 3 was reached at 1133 hours0.0131 days 0.315 hours 0.00187 weeks 4.311065e-4 months ..
Let-down divert valve HARV-303, which directs the letdown flow to the volume control tank and diverts it to CVCS holdup tanks was found to be stuck in the divert position.
This valve was repaired by 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months December 31, 1978.
12/31/78 Necessary dilution was made and the Reactor was cri-tical at 0407 hours0.00471 days 0.113 hours 6.729497e-4 weeks 1.548635e-4 months .
The Unit was paralleled with the system at, 0639 hours0.0074 days 0.178 hours 0.00106 weeks 2.431395e-4 months .
Power level was increased to 50Ã by 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months .
At this time the Main Conden-ser was operating at maximum allowable temperature rise of the circulating water.
Repairs to 41 Circulating Water Pump had been started during the outage and it had not yet been returned to service.
At this time 412 Circulating Water Pump was giving indications of very low flow.
Investigation found the discharge valve of this pump to be 105 open and the valve operator failed.
The
$ 11 Circulating Water Pump was returned to service at 1728 hours0.02 days 0.48 hours 0.00286 weeks 6.57504e-4 months which reduced the
Docket Unit Name:
Completed By:
Telephone:
Date:
Page:
50-315 D.
C.
Cook Unit 81 R.
S.
Lease (616) 465-5901 January 9,
1979 (4) 12/31/78 temperature rise across the Condenser to be normal (cont.)
for two pumps for two pumps operating.
Unit loading was not started at this time due to a Waste Gas situation within the plant.
The total Waste Gas volume was at its maximum and release could not be made due to frozen weather instrumentation.
The required dilution to load this Unit would have only forced abnormal pressure on the Waste Gas System.
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 315 D. C.
Cook - Unit No.
1 1-10-79 BBB. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE DECEMBER, 1978 No.
3 S/G stop valve dump valve, MRV-232 was leaking by.
Replaced valve gaskets and seat and retested valve.
Governor cooling water safety valve, SV-140, for the turbine driven auxiliary feed pump leaked by.
Revised piping to allow disassembly and disassembled valve.
Lapped seating surface, reassembled and had valve tested.
M-3 M-4 The blowdown regulating valve for 84 steam generator, DRV-341 had a body to bonnet leak.
Replaced the gaskets and had valve retested.
The blowdown regulating valve for 44 S/G, DRV-342 was leaking.
Dis-assembled valve, replaced gaskets and reassembled.
Retested and re-turned to service.
M-7 M-8 M-10 C8tI-1 No.
4 reactor coolant pump motor had an excessive oil leak.
Located leaking fitting on upper bearing oil cooler.
Tightened fitting and added oil to upper bearing reservoir.
No.
4 steam generator blowdown control valve, DRV-341, had a bonnet leak.
Bonnet gaskets were replaced and retest was satisfactory.
HARV-ill, loop 4 letdown isolation valve, developed a bonnet leak.
Gaskets were replaced and bonnet face rabbet fit was dressed by filing.
Operational retest was satisfactory.
MPP-222, instrument isolation valve for P2 steam generator pressure leaking badly.
A new valve bonnet was installed.
MS-153-3, steam lead 83 drain valve, had body to bonnet leak.
The valve body was repaired and a new bonnet installed.
MPP-240, instrument isolation valve for ~4 steam generator pressure developed a bonnet leak.
A new bonnet was installed.
During surveillance testing of pressurizer pressure protection set III, the lead/lag instrument PY-457B was found to be out of specification.
The static gain of the instrument was determined to be low.
Instru-ment calibration was performed.
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 315 D. C.
Cook - Unit No.
1 1-10-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE DECEMBER, 1978 The cold leg RTD of aT-Tavg Protection Set III was removed from service and the spare RTD wired to the input of TY-431B.
The resistance to voltage converter TY-431B calibration was performed based on the spare RTD calibration curve.
Surveillance test procedure was performed to verify the calibration of the loop.
Glycol valve VCR-021, failed to the closed position.
The diaphragm of VCR-021 had failed and required replacement.
Following the diaphragm replacement, the valve was stroked, limit switches adjusted and the closure time recorded as 3.2 sec.
Rod position indication system for control bank D, rod H8 indicated 13 steps from the demand position.
The secondary coil voltage was measured and verified correct.
The signal conditioning module was adjusted to provide proper indication.
During the performance of the Logic Channel Surveillance Test of Train B
Solid State Protection
System, most of the logic failed the test.
A faulty tester card was identified and replaced.
The logic was retested by performing 1
THP 4030 STP.045.
ITY-412, current repeater for loop 1
aT Tavg-Tavg deviation alarm, failed.
The filter capacitor of the modules input circuit had shorted and required replacement.
The 150 foot wind speed, indication failed.
The failure of the wind speed transmitter was the result of ice buildup and weather conditions.
The 150 foot primary transmitter began to function as the rain removed the ice.
The secondary 150 foot wind speed transmitter has a cup missing and determined to be inoperable.
VCR-10, glycol valve, would not close.
The valve was stroked several times until correct operation was achieved.
The closure time of the valve was measured and recorded.
The rod position indication for part length rods F-4 and D-6 and full length control rod K-6 indicated greater than 12 steps from demand position.
The secondary coil voltages were measured to verify the rod positions.
The calibration of the signal conditioning modules was checked and the modules were recalibrated for correct panel indication.

ML17317A874

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