Text

Monthly Operating Rept for Jan 1980
	ML17318A627
Person / Time
Site:	Cook
Issue date:	02/04/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17318A626	List: ML17318A625; ML17318A627;
References
	NUDOCS 8002200634
	Download: ML17318A627 (15)
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50-315

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~~9O1 OP=."-~~>cto Rcsc ve Snts dovvn Ho">>s~~

~~14. Hours Generator On-Line IS. Unit R~rve Shutdown Hovw lo. Gross Thermal Energy Cene.~~
~~ted (%IVAN..)~~
~~17. Gross Lscc ac"I ""ncrgy Generated (i'f>YH}~~
IS.
i>'ec Beet;;
I:"1ergy Cenesa:
"= {.'I'iVH) l9. Unit Scrvi" Factor TEs Month 744 346. 8 0
980 650 33,10 45.8 Y-.:to-Dat=
744 346.8 980 650 323,510 45.8 Cu...Qiatsve 44,568 33,308.5 463 90 046 955 29,480,850
,308,581 7Q 7'7 "S.
Uric Av"iiabiliry Factor Uni. Caoacitv Factor (Usirg ~!DCNet}
Unit Capacity F ctor (Using Dc~ Yet)
Unit Forced Ovtace Rat Snvtdo -'ws Scheduled 0:cr Next 6.'fon:hs 45.8
~~39. 7~~
~~54. 2 (Type. Date:and Dv.=cion of F ch1:~~
~~45.8~~
~~39. 7~~
~~54. 2 74.6~~
~~61. 6 8.1 "S. IfSh: Do-n At "-nd Of R= or: P clod.:"s!Imatcd Date of Startuo:~~
S. Units la Test Status IP> oa to Cc
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GE DAILY UNIT POWER LEVEL aeltETND:~
UNIT DATE 2-4-80 COMPLETED BY W.
T..
Gillett TELEPHONE 616-465-5901 MONTH JANUARY 1980 DAY AVERAGE, DAILY POWER LEVEL (MWE-Net)
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 10 12 13 15 16 17 18 19 20 21 22 23 24 25 27 28 29
=
30 31 248 993 1039 1038 1042 1044 1040 925 1043 1030 691 519
. 656 687 980 INSTRUCTIONS, On this format )ist the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawa'tt.
REPORT hIONTII 80 UNITSIIUTDO'lUNS AND POlUER REDUCTIONS DOCKET NO.
TELEPIIONE 61 6 465-5901 PAGE 1 of 2 No.
DJIc 4 I O
>>J W>>
Llccoscc Event Itcpolt +
~l/1 CJ Q
O CO Cause &(.oriel.t lvc Action lll Prcvcnl Rccurrcoec 155 Cont'd 156 157 791224 800124 800127 F
396.2 H
0 B
7.2 A
N.A.
ZZ N.A.
CH 79-065/01T-0 SE SUPORT
~~ZZZZZZ, Zzzzzz Outage -continued from previous month to correct discrepancies in piping supports on safety-related piping systems as a result of IE Bulletin No. 79-14.~~
Unit returned to Service 800117.
Reactor power increased to 100K 800118.
Total duration of outage 570.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .
Reactor power reduced to 605 to per-mit removal of one main feedwater pump.
One feedpump removed at a
time for cleaning of feedpump turbine condenser tube sheets.
Reactor Power returned to 1005 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 
'later.
Reactor/Turbine trip caused by Steam FlotU/Feedwater Flow mismatch coin-cident with low level in No.
4 steam enerator due to trip of West main d
n Next Pa e
I I'. Folccll S: Schellulcll (9177)
'I Iteasoo:
A-EI)uipntcnt Failure (Explain)
D.hlalotenance or Test C-Rcfueliog D.Regulatory Restriction I -OpcfJlof Tralnlog & Liccosc I:xamioation F-Adollotsll:Illvc G.Operational Llror (I'.xplaio)
I I Olllcr(fxplain)
Method:
I -hi antral 2 Manual Scraln.
3-Autoloat tc Scraol.
4 Other (Explaul)
Fxhibil G - Instructions lor Preparation ol'Data Lotry Sheets for Licensee Event Rcp< rl (LI:R) Fil (NUItl!G-OI 6I )
'L'xhibit I - Same Source
INSTRUCTIONS This report should describe all plant shutdowns during the report period.
In addition. it should be the source of explan-ation of significant dips in average power levels.
Each signi-ficant reduction in power level <greater than 207o reduction in averaee 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 zero, 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 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.
i%UMBER.
This column should indicate the sequential num.
ber assigned to each shutdown or sienificant 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
~JI shutdowns or significant power reductions are reported.
Until a unit has achieved its first power, generation, no num-ber should be assigned to each entry.
DATE.
This column should indicate the date of the start of each shutdown or significant power reduction.
Report as year. month, and day.
Aueust i4. 1977 would be reported as 770814.
When a shutdown or sienificant 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 significant power reductions are reported.
TYPE.
Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power reduction.
Forced shutdowns include those required to be initiated by no later than the weekend follow'ing discovery of an off-normal condition.
It is recognized that some judg-ment is required in categorizing shutdowns in this way.
In general.
a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.
DURATION.
Selfwxplanatory.
When a shutdown extends beyond the end of a report period, count only the time to the end ot'he report period and pick up the ensuing down time in the followine report periods.
Report duratit>n of outages rounded to the nearest tenth ofan hour to facilitate summation.
The sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.
REASON.
Categt>rize by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used. supply briei'comments.
METHOD OF SHUTTliNG DOWN THE REACTOR OR REDUCING POWER.
Cateenrize by number designation IN>nte that this differs irnm the Edison Electric Institute
{EEII definitions of -Forced Partial Outaee" and
-Sche-duled Partial Outage.-
F>>r these turin~. EEI uses a chance oi'0
~IW as the break p<>int.
Fi>r larger power reactors. ~0 l>IW is t>>(> sli>Jil a chance tn warrant cxplanaiinn.
in accordance with the table appearing on the report form.
Ifcategory 4 must be used, supply brief comments.
LICENSEE-EVENT REPORT
='.
Reference the applicable reportable occurrence pertaining to the outage or power reduction.
Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).
This information may not be immediately evident for all such shutdowns, of course, since t'urther investigation may be required to ascertain whether or not a reportable occurrence was involved.) Ifthe outage or power reduction wiII not result in a reportable occurrence.
the positive indication of this lack of correlation should be noted as not applicable (N/A).
SYSTFM CODE.
The system in which the outage or power reduction originated should be noted by the two digit <<ode of Exhibit G
~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).
Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.
COI>IPONENT CODE.
Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File {NUREG4161).
using the following critieria:
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 sequence of events. includ-ing the other components which fail, should be described under the 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 should be. used for events where a
component designation is not applicable.
CAUSE 5, CORRECTIVE ACTION TO "PREVENT RECUR-RENCE.
Use the column in a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction.
The column should include the specific cause for each shut-down or significant power. reduction and the immediate and contemplated long term corrective action taken. ifappropri ~
ate.
This column should also be used for a description of the major safety related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any sinele release ot'adioactivity or single radiation exposure specitically associ
~
ated with the outaee which accounts for more than 10 percent oi the allowable annual values.
For long textual reports continue narrative on separate paper and ret'erence t lie shutdown or power reduction tnr tl.is I>JffJtlve.
(9/77
UNITSIIUTD01VNS AND PO1VER REDUCTIONS REPORT hIONTII ~ nuary 1980 DOCKET NO.
UNITNAME DATE COhlPLETED DY TELEI'IIONF.
PAGE 50-315 00 - n1t 2-11-80 B.A. Svensson 616 465-5901 2of2 l)alc rrI
)) er
~
I))
Ltcc>>scc livenl ItcpofI 4
)))~
OC Q
O r ~
O C a>>sc k, Cl)ffc<<live Aetio>> tr)
Prevent Rccurrc>><<c 157
( ontinued) feedpump turbine.
The feedpump turbine trip was due to pump coupling failure.
Unit returned to service the same day.
Reactor power was held at 685 until 800131 due to West feedpump being out of service.
Reactor power reached 100K 800131.
I: For cell S: Scllcdulcll lteason:
A-fr)oil)l>>cnl Failure (Explai>>)
II-hlaintcnancc or Test C-lhc fuel i>> I)
D.lect)ulatoly Rcslfi<<lion E-Opcralof Tfainint' Ltcc>>sc Exanllnallo>>
F-A~nlllllstlatlve G.Opcfatio>>al Llror(Iixplai>>)
I I Olllcr(Explai>>)
hlethod:
I Ma>>>>al 2.Manual Sera)>>.
3-Anti>>>>atic Sera)>>.
I Olllcf(Exp)J>>))
4 Exllibil G ~ Instr>><<tio>>s for Preparati))>> ot'Data L>>lry Sllccts for Li<<c>>see Event Report (I.I R) File INUItl:G.
OI6 I )
'Exllibil I - Sal>>e So>>r<<e
INSTRUCTIONS This report should describe all plant shutdowns during the report period.
In addition, it should be the source of explan-ation of significant dips in average power levels.
Each sieni-ficant reduction in power level (greater than 207>> reduction in averaee 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 completelyl.
For such reductions in power level, the duration should be listed as zero, 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 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 sequential num.
ber assigned to each shutdown or significant 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 shouid be made for both report periods to be sure all shutdowns or sienificant power reductions are reported.
Until a unit has achieved its first power generation, no num-ber should be assigned to each entry.
DATE.
This column should indicate the date of the start of each shutdown or signittcant power reduction.
Report as year. month. and day.
Aueust i4. 1977 would be reported as 770814.
)Vhen 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 signiticant power reductions are reported.
TYPE.
Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power reduction.
Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off-normal condition.
It is recognized that some judg-ment is required in categorizing shutdowns in this way.
In general.
a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.
DURATION.
Self~xpianatory.
When a shutdown extends beyond the end of a report period, count only the time to the end ot the report period and pick'up the ensuing down time in the followine report periods.
Report duration of outages rounded to the nearest tenth ofanhour to facilitate summation.
The sum of the total outage hours plus the hours the genera-tor was on line should equal the cross hours in the reporting period.
REASON.
Categorize by letter >Iesignation in accordance with the tabie appearing on the report form. Ifcategory H must he used. supply briei'<<omments.
METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.
Categorize by number designation N>oie that this differs irom the Edison Electric Institute IEEI) detmitions of -Forced Partial Outaee" and
-Sche.
duled Partial Outage.-
For these tern>>. I;El uses a <<hange ot'0!>IW as the break point.
F>>r larger power reactors. 30 MW is t>>o small a <<hence ti> warrant <<xplanati>>n.
in accordance with the table appearing on the report form.
Ifcategory 4 must be used, supply brief comments.
LICENSEE EVENT REPORT =.
Reference the applicable reportable occurrence pertaining to the outage or power reduction.
Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).
This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.) Ifthe outage or power reduction will not 'result in a reportable occurrence.
the positive indication of this lack of'orrelation 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 of Exhibit G
~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (N>>UREG4161).
Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.
CO>MPONENT CODE.
Select the most appropriate component from Exhibit I
~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).
using the following critieria:
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 mal-function should be listed. The sequence of events. includ-ing the other components which fail, should be described under the 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 should be used for events where a
component designation is not applicable.
CAUSE &, CORRECTIVE ACTION TO'PREVENT RECUR-RENCE.
Use the column in a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction.
The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated long term corrective action taken. ifappropri-ate.
This column should also be used for a description of the major safety-rehted corrective maintenance performed durine the outaee or power reduction including an identification of the critical path activity and a report of any sinele reiease of radioactivity ur single radiation exposure speciiically asso<<i-ated with the outaee which accounts for more than 10 per<<ent of the allowable annual values.
For long textual reports continue narrative on separate paper and ret'eren<<e tlie shutdown or power redu<<tion ior ti!>>
iia!'rative (a)/77
Dock (o.:
Unit Name:
Completed By:
Telephone:
Date:
Page:
50-315 D.
C.
Cook Unit b'1 R.,S.
Lease (616) 465-5901 February 14,',1980 lof4 MONTHLY OPERATING EXPERIENCES -- JANUARY, 1980 Hi hli hts The Unit entered the reporting period in the "Cold Shutdown" con-dition.
The Unit had been shutdown 12/24/79 when Design Analysis had shown design deficiencies in the Containment Hydrogen Skimmer System.
The Unit was started and electrical generation was again obtained 1/17/80, details of which are in the summary.
There was one more Outage 'during the reporting period and this is also detailed in the summary.
Total electrical generation for the month was 323,510 Mwh;
~Summa r 1/2/80 -- Normal 4KV Auxiliary Power Bus 1-C was.deenergized for a 5:5 hour period for testing of the Bus.
Safeguards 4KV Bus T-ll-C was also;deenergized during this period.
1/4/80 -- The "AB" Emergency Diesel Generator was inoperable for an 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months period for modification to the Generator Field Flashing Circuit.
Vent Stack Radiation Montors R-31 and R-32 were in-operable for a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months period for revision to piping.
1/7/80 The "CD" Emergency Diesel Generator was inoperable for a 17.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for modification to the Generator Field Flashing Circuit and installation of Jacket Water Temperature Detection Wells.
1/8/80 -- The "AB" Emergency Diesel Generator was inoperable for a 9.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for installation of Jacket Water Temperature Detection Wells.
Containment Radiation Monitors R-ll and R-12 were inoperable for a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months period,,for, revision to piping.
1/9/80 -- Containment Radiation Monitors R-11 and R-12 were inoperable for a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period for revision to piping.
<J
~'fl', la)[
K ~
ci
Do~t No.:
U~ Name:
Completed By:
Telephone:
Date:
Page:
50-315
,D.
C.
Cook Unit Pl R.
S.
Lease
(.616) 465-5901 February 14, 1980 2of4 1/1'1/80 Meteorological'nstruoients for, wind speed and direction were out.of service'.for -a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . period for,repairs:
These instruments are common to both units.
1/14/80-- Required modifications to hangers and restraints of safety related piping systems were completed and the Unit was released for start-up.
The Reactor Plant entered Mode 4 at 1443 hours0.0167 days 0.401 hours 0.00239 weeks 5.490615e-4 months .
At 2028 hours0.0235 days 0.563 hours 0.00335 weeks 7.71654e-4 months Source Range Nuclear Instrument N-32 failed to the point that it required replacement of the Detector.
This did not prevent heat-up,
~~however, the Reactor Plant was held in Mode 4 until replacement was assured.~~
1/16/80 -- A new Source Range Detector,was.,installed and,made oper able at 1850 hours0.0214 days 0.514 hours 0.00306 weeks 7.03925e-4 months .
Heat-up was again initiated with the Reactor Plant entering Mode 3 at 1610 hours0.0186 days 0.447 hours 0.00266 weeks 6.12605e-4 months .
1/17/80 -- Full temperature and pressure was obtained on the Reactor Coolant System at 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months .
The reactor was returned to criticality at 0725 hours0.00839 days 0.201 hours 0.0012 weeks 2.758625e-4 months .
The Turbine/Generator was: rolled at 1121 hours0.013 days 0.311 hours 0.00185 weeks 4.265405e-4 months and paralleled to the system at 1212 hours0.014 days 0.337 hours 0.002 weeks 4.61166e-4 months .
1/18/80 -- The Unit was load to 100/ power by 1010 hours0.0117 days 0.281 hours 0.00167 weeks 3.84305e-4 months .
The South Hotwell Pump tripped due to a grounded motor lead.
Repairs were made the same day.
The West Component Cooling Water Pump was inoperable for 4.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 'period while'.repairs were made;to a
'talled oil ring in one of the motor bearings.
1/19/80--
1/23/80--
The Middle Heater Drain Pump was removed from service at 1980 hours0.0229 days 0.55 hours 0.00327 weeks 7.5339e-4 months for repairs to the Inboard Pump, Seal.
This pump was again operable 1/23/80.
Control Rod Drive Ability failed at 0425 hours0.00492 days 0.118 hours 7.027116e-4 weeks 1.617125e-4 months due to a "Urgent Failure" in the Drive Control.
A failed solid state card was replaced and the ability to move rods by the drive system was obtained at 0843 hours0.00976 days 0.234 hours 0.00139 weeks 3.207615e-4 months .=
I lf It
(
tt J
I
D t No.:
t Name:
Completed By; Telephone:
Date:
Page:
50-315 D.
C, Cook Unit 81
,R.,S, Lease (616) 465-5901 February 14, 1980 3of4 1/23/80--
(Cont.)
Power was reduced to 60% over a two hour ramp starting at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months to remove the West Feed Pump from service for hand cleaning of its condenser.
After cleaning of this condenser, the two feed pumps were exchanged for hand cleaning of the East Feed Pump Condenser.
1/24/80 -- Power was returned to 100% over a 4.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 0445 hours0.00515 days 0.124 hours 7.357804e-4 weeks 1.693225e-4 months .
1/25/80 Loop 3 b T and Tavg Channels were inoperable for a 10.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period while a spare RTD was connected in place of a failed one.
1/26/80 -- Power was reduced to 90% for testing of Main Turbine Control Valves, total time below 100% power was 4.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months .,
1/27/80--
The Unit tripped from 100% power at 1550 hours0.0179 days 0.431 hours 0.00256 weeks 5.89775e-4 months due to Steam Flow/Feed Flow Mismatch coincident with low lev'el in 84 Steam Generator.
The cause of the low level was that the Coupling between the West Feed Pump Turbine and the Pump failed.
This is a Disconnect Coupling and indication was that the last engagement had not been full.
The Reactor was returned to criticality at 2138 hours0.0247 days 0.594 hours 0.00354 weeks 8.13509e-4 months .
The Turbine/Generator unit was paralleled with the System at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months .
1/28/80 Power was increased to 48% by 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months and held at this point due to an indicated quadrant Power Tilt.
Power increase was resumed at 0815 when it was determined that the tilt was within allowable limits.
The Unit was loaded to 62% by 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months .
The Unit had returned to service with only the East Main Feed Pump while repairs were being made to the West Hain Feed Pump.
The power level was slowly increased to 68% by 1/29/80.
1/30/80 -- The "AB" Emergency Diesel Generator was inoperable for a 6.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for replacement of several electrical relays.
1/31/80 The "CD" Emergency Diesel Generator was inoperable for a
7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months period for replacement of several'lectrical relays.
Dock No.:
Un'ame; Comple ed By; Telephone; Date:
Page:
50-315
.D.
C.
Cook Unit Pl R..S.
Lease (616) 465-5901 February 14, 1980 4of4 1/31/80 -- The West Hain Feed Pump was returned to service (Cont'd) at 0147 hours0.0017 days 0.0408 hours 2.430556e-4 weeks 5.59335e-5 months .
The Unit was loaded to 1005 power by 0652 hours0.00755 days 0.181 hours 0.00108 weeks 2.48086e-4 months .
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 315 D.
C.
Cook - Unit No.
1 2-1 -80 B. A. Svensson 616 465-5901 Qf 1
MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1980 Containment isolation valve in glycol supply line, VCR-10, would not close.
Straightened stem and replaced valve diaphragm.
Had valve tested.
The reciprocating charging pump was leaking.
Replaced two plungers, packing and adapters.
Reassembled with new gaskets and tested.
Reactor coolant system letdown valve, HARV-ill, had a body to bonnet leak.
Replaced gaskets and had valve tested.
A Reactor Coolant Pump No.
2 undervoltage reactor trip was received.
The 0.5 second time delay agastat relay was found to have an open coil.
The coil was replaced and the relay was timed.
The Delta T-Tavg Protection Set I, indicated a value of'avg 3
F lower than the other protection sets.
The calibration of the resistance to voltage converters and the voltage to current converter of the pro-tection set were tested.
The instruments as found data did not in-dicate the source of the 3
F error.
A problem on the cable to the hot leg RTD was found.
The resistance on one lead indicated a higher value which affected the R/E lead compensation circuit.
The wiring problem was resolved and the protection set returned to normal opera-tion.

ML17318A627

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