ML17318A627

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)

Text

OP" %<TLiG DATA R" oORT

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DOCK:"7 iO. 50-315 OAT" COifPL~~:-D "-Y TnL:-?HOT'""

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~~9O1ett OP=."->cto Rcsc ve Snts dovvn Ho" >>s 463

14. Hours Generator On-Line IS. Unit R~rve Shutdown Hovw 0 lo. Gross Thermal Energy Cene. ted (%IVAN..) 980 650 980 650 90 046 955

17. Gross Lscc ac"I ""ncrgy Generated (i'f>YH} 33,10 323,510 29,480,850 IS. i>'ec Beet;; I:"1ergy Cenesa: "= {.'I'iVH) ,308,581 l9. Unit Scrvi" Factor 45.8 45.8 7Q Uric Av"iiabiliry Factor 45.8 45.8 74.6 Uni. Caoacitv Factor (Usirg ~!DCNet}

7'7 Unit Capacity F ctor (Using Dc~ Yet) 39. 7 39. 7 61. 6 "S. Unit Forced Ovtace Rat 54. 2 54. 2 8.1 Snvtdo -'ws Scheduled 0:cr Next 6 .'fon:hs (Type. Date:and Dv.=cion of F ch1:

"S. If Sh: Do-n At "-nd Of R= or: P clod.:"s!Imatcd Date of Startuo:

S. Units la Test Status IP> oa to Cc ~~ r ~ c" I Oo not }t Foe>>>>>>st Ac> 'Icved

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GE DAILY UNIT POWER LEVEL aeltETND:

UNIT DATE

~2-4-80 COMPLETED BY W. T.. Gi llett TELEPHONE 616-465-5901 MONTH JANUARY 1980 DAY . AVERAGE, DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net) (MWe-Net) 17 248 18 993 19 1039 20 1038 21 1042 22 1044 23 1040 24 925 25 1043 10 1030 27 691 12 28 519 13 29 =

. 656 30 687 15 31 980 16 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.

DOCKET NO.

UNIT SIIUTDO'lUNS AND POlUER REDUCTIONS REPORT hIONTII 80 TELEPIIONE 61 6 465-5901 PAGE 1 of 2 W>>

4 I ~l/1 Llccoscc CJ Cause & (.oriel.t lvc O

No. DJIc >>>>>>

Event Q O Action lll

>>J Itcpolt + C O Prcvcnl Rccurrcoec 155 791224 F 396.2 H 79-065/01T-0 SE SUPORT Outage -continued from previous month Cont'd 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

156 800124 0 B N.A. ZZ ZZZZZZ, 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

'later.

157 800127 7.2 A N.A. CH Zzzzzz 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

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I'. Folccll Iteasoo: Method: Fxhibil G - Instructions S: Schellulcll A-EI)uipntcnt Failure (Explain) I -hi antral lor Preparation ol'Data D.hlalotenance or Test 2 Manual Scraln. Lotry Sheets for Licensee C-Rcfueliog 3-Autoloat tc Scraol. Event Rcp< rl (LI:R) Fil (NUItl!G-D.Regulatory Restriction 4 Other (Explaul) OI 6I )

I -OpcfJlof Tralnlog & Liccosc I:xamioation F-Adollotsll:Illvc G.Operational Llror (I'.xplaio) 'L'xhibit I - Same Source (9177) I I Olllcr (f xplain)

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 of explan- If category 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi-ficant reduction in power level <greater than 207o reduction LICENSEE- EVENT REPORT ='. Reference the applicable in averaee 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 completely . 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 (NUREG416I). 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 t'urther 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 wiII not result in a reportable occurrence.

i%UMBER. This column should indicate the sequential num. the positive indication of this lack of correlation should be ber assigned to each shutdown or sienificant reduction in power noted as not applicable (N/A).

for that calendar year. - When a shutdown or significant power SYSTFM 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

~JI 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 significant power reduction. Report as year. month, and day. Aueust i4. 1977 would be reported COI>IPONENT CODE. Select the most appropriate component as 770814. When a shutdown or sienificant 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 {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 follow'ing 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 mai-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'he report period and pick up the ensuing down time events where a component designation is not applicable.

in the followine report periods. Report duratit>n of outages rounded to the nearest tenth of an hour to facilitate summation.

CAUSE 5, 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 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. Categt>rize by letter designation in accordance contemplated long term corrective action taken. if appropri ~

with the table appearing on the report form. 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 SHUTTliNG DOWN THE REACTOR OR REDUCING POWER. Cateenrize by number designation the critical path activity and a report of any sinele release or single radiation exposure specitically associot'adioactivity

~

IN>nte that this differs irnm the Edison Electric Institute ated with the outaee which accounts for more than 10 percent

{EEII definitions of -Forced Partial Outaee" and -Sche- oi the allowable annual values.

duled Partial Outage.- F>>r these turin~. EEI uses a chance oi'0 For long textual reports continue narrative on separate paper

~IW as the break p<>int. Fi>r larger power reactors. ~0 l>IW and ret'erence t lie shutdown or power reduction tnr tl.is is t>>(> sli>Jil a chance tn warrant cxplanaiinn. I>JffJtlve.

(9/77

DOCKET NO. 50-315 UNIT SIIUTD01VNS AND PO1VER REDUCTIONS UNIT NAME 00 - n1t DATE 2-11-80 nuary 1980 COhlPLETED DY B.A. Svensson REPORT hIONTII ~ TELEI'IIONF. 616 465-5901 PAGE 2of2 rrI r)) e

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O 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.

4 I: For cell lteason: hlethod: Exllibil G ~ Instr>><<tio>>s S: Scllcdulcll A-fr)oil)l>>cnl Failure (Explai>>) I Ma>>>>al for Preparati))>> ot'Data II-hlaintcnancc or Test 2.Manual Sera)>>. L>>lry Sllccts for Li<<c>>see C-lhc fuel i>> I) 3-Anti>>>>atic Sera)>>. Event Report (I.I R) File INUItl:G.

D.lect)ulatoly Rcslfi<<lion I Olllcf (Exp)J>>)) OI6 I )

E-Opcralof Tfainint' Ltcc>>sc Exanllnallo>>

F-A~nlllllstlatlve G.Opcfatio>>al Llror (Iixplai>>) 'Exllibil I - Sal>>e So>>r<<e I I Olllcr (Explai>>)

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 of explan- Ifcategory 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each sieni-ficant reduction in power level (greater than 207>> reduction LICENSEE EVENT REPORT =. Reference the applicable in averaee 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 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'orrelation 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 shouid be made for both report periods to be sure all shutdowns or sienificant 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 (N>>UREG4161).

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 signittcant power reduction. Report as year. month. and day. Aueust i4. 1977 would be reported CO>MPONENT CODE. Select the most appropriate component as 770814. )Vhen 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 (NUREG4161).

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. Self~xpianatory. 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 where a component designation is not applicable.

in the followine report periods. Report duration of outages rounded to the nearest tenth ofanhour to facilitate summation.

CAUSE &, 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 amplify or tor was on line should equal the cross 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 >Iesignation in accordance contemplated long term corrective action taken. if appropri-with the tabie appearing on the report form. 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 durine the outaee or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER. Categorize by number designation the critical path activity and a report of any sinele reiease of radioactivity ur single radiation exposure speciiically asso<<i-N>oie that this differs irom the Edison Electric Institute ated with the outaee which accounts for more than 10 per<<ent IEEI) detmitions of -Forced Partial Outaee" and -Sche. of the allowable annual values.

duled Partial Outage.- For these tern>>. I;El uses a <<hange For long textual reports continue narrative on separate paper as the break point. F>>r larger power reactors. 30 MW ot'0!>IW and ret'eren<<e tlie shutdown or power redu<<tion ior ti!>>

is t>>o small a <<hence ti> warrant <<xplanati>>n. iia!'rative (a)/77

Dock (o.: 50-315 Unit Name: D. C. Cook Unit b'1 Completed By: R.,S. Lease Telephone: (616) 465-5901 Date: February 14,',1980 Page: 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 <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period for revision to piping.

1/7/80 The "CD" Emergency Diesel Generator was inoperable for a 17.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 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 <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 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 <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period for revision to piping.

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Do~t No.: 50-315 U~ Name: ,D. C. Cook R. S. Lease Unit Pl Completed By:

Telephone: (.616) 465-5901 Date: February 14, 1980 Page: 2of4 1/1'1/80 Meteorological'nstruoients for, wind speed and direction were out.of service'.for -a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. 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 <br />0.401 hours <br />0.00239 weeks <br />5.490615e-4 months <br />.

At 2028 hours0.0235 days <br />0.563 hours <br />0.00335 weeks <br />7.71654e-4 months <br /> 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 <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />.

Heat-up was again initiated with the Reactor Plant entering Mode 3 at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />.

1/17/80 -- Full temperature and pressure was obtained on the Reactor Coolant System at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />.

The reactor was returned to criticality at 0725 hours0.00839 days <br />0.201 hours <br />0.0012 weeks <br />2.758625e-4 months <br />.

The Turbine/Generator was: rolled at 1121 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.265405e-4 months <br /> and paralleled to the system at 1212 hours0.014 days <br />0.337 hours <br />0.002 weeks <br />4.61166e-4 months <br />.

1/18/80 -- The Unit was load to 100/ power by 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />.

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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />'period while'.repairs were made;to a oil ring in one of the motor bearings. 'talled 1/19/80-- The Middle Heater Drain Pump was removed from service at 1980 hours0.0229 days <br />0.55 hours <br />0.00327 weeks <br />7.5339e-4 months <br /> for repairs to the Inboard Pump, Seal.

This pump was again operable 1/23/80.

1/23/80-- Control Rod Drive Ability failed at 0425 hours0.00492 days <br />0.118 hours <br />7.027116e-4 weeks <br />1.617125e-4 months <br /> 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 <br />0.234 hours <br />0.00139 weeks <br />3.207615e-4 months <br />.=

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D t No.: 50-315 t Name: D. C, Cook Unit 81 Completed By; ,R.,S, Lease Telephone: (616) 465-5901 Date: February 14, 1980 Page: 3of4 1/23/80-- Power was reduced to 60% over a two hour ramp starting (Cont.) at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ramp starting at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />.

1/25/80 Loop 3 b T and Tavg Channels were inoperable for a 10.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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 <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.,

1/27/80-- The Unit tripped from 100% power at 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> 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 <br />0.594 hours <br />0.00354 weeks <br />8.13509e-4 months <br />.

The Turbine/Generator unit was paralleled with the System at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

1/28/80 Power was increased to 48% by 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> 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 <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />. 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for replacement of several electrical relays.

1/31/80 The "CD" Emergency Diesel Generator was inoperable for a 7 hour period for replacement of several'lectrical relays.

Dock No.: 50-315 Un'ame; .D. C. Cook Unit Pl Comple ed By; R..S. Lease Telephone; (616) 465-5901 Date: February 14, 1980 Page: 4of4 1/31/80 -- The West Hain Feed Pump was returned to service (Cont'd) at 0147 hours0.0017 days <br />0.0408 hours <br />2.430556e-4 weeks <br />5.59335e-5 months <br />.

The Unit was loaded to 1005 power by 0652 hours0.00755 days <br />0.181 hours <br />0.00108 weeks <br />2.48086e-4 months <br />.

DOCKET NO. 50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 2-1 -80 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 PAGE 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.