Text

Monthly Operating Rept for Jan 1980
	ML17318A630
Person / Time
Site:	Cook
Issue date:	02/04/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17318A629	List: ML17318A628; ML17318A630;
References
	NUDOCS 8002200663
	Download: ML17318A630 (15)
	v • d • e

OPEKCTLIC DATAR""PORT DOCK:"T%0.

D i~ ~2--

CO~fPL~:-D - Y 1lett T-p=~i:oq-- ~1-5-5901 O? -RAT>lG STA:US Oona1d C.

Cook anuar

3. Lic nsed Then..sl Power (V<Nt)t

4. hemeohte Rnctng (Gso~~

~DVe):

S.

Design "Ie"mMR"ting (Net ED'):

6. M~tnn Dependnbfe Qyacicy (Gross.'rNe)t 7..'faxirttm De=endnble C=o"cir;. (Net bf'Ve}:

1980 3391 133 1100 1118 1082 I lotes S.

EE Chmges Oc='r in Cnpa='ty R"t.~~ (lt ms 4 vwber 3 Th:ongh I) Since Last Repor.. Give R mons:

9. Powe. f. vef To Qi"'z Res&c~, L'ny {.iet ID'):

10. R~ons For Restt."et!or>. IfAny:

This bfonth Y-...to-Dec=

CnmnLttf'/e ll. Hot s ln Reporting Period

12. Nm"..oa'OiEova R="ctor Res C.":ill ES. Re"ctor Rex~e Shntdove Ho"-.

14. Bott'

.e. tor On.~te

15. Uric R~~e Shntdown Elor=~

16. Gross tn ~of:"ne~y Cen. t~ (bf)VH)

17. Gross -"!ecacc! ""aery Genentc>

(~SfNH),

ES.

4>'et Hect>

1 "".ergy Cen.. '."'.'fair'.)

19. Unit Service Factor 744 3 0.8 0

250.7 584 404 182,750 744 320. 8 0

250.7 0

58 404 182 750 18 264 11,400.7 0

10 752.6 0

10 337 160 ZO 33.7 Uric Av"ihbifiryFcctor Urit Caoccity Fec:or (Using DER le'.)

Unit Forced Outec>> Rate 0

Shotdo-'vs Sc.'".ednfed Over Next 6 fonths !Type. D"te. "nd Dc:"cion of c chl:

33 '

21.6

61. 4

60. 4

)

f SQ'own '

c, 1d 0

+

o '" 'oG s't'"ted D~t~ ot St~ t"o

'S.

Units En Test Sts:ns f?,":or to Cc...merci'f Oc rc:ion):

For c"st Acme'ved D ET!AL CRETECA L!TY EYETEAE:-'=CTR!CE > Y CO:'.

=..C:-.-'.'

,3, )~3~, l.

~

/+AGE DAILY UNIT POWER. LEVEL ~

OQCKETNO:~

UNIT 2

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) 17 18 19 20 21 22 23 18 426 467 10 12 13 15 16 26 27 28 29 30

'1 269 663 752 827 950 995 1056 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.

UNITSIIUTI)0'IVNSAND PO)VER REI)UCTIONS REPORThIONTII January, 1980 l)OCKETNO.

2 TELEPIIONE 6

465 590 PAGE 1 of 2 N)).

l)Jlc rl IA)o I) <<J

~- n

~ Cll Liccnscc Event Rcpoft 4 c

)

p CJ Q p p

CJ>>sc A, Coffel,tlvt.

Action tI)

Pfcvent RCI.'offence

. 64

.791019 65 800120 S.

468.7 9.6 B&C N.A.

N.A.

. zz zz zzzzzz zzzzzz The unit was removed for Cycle I-II refueling outage on 791019.

The outage was extended

'on 791223 to correct discrepancies found as a

result of seismic analysis for as-built safety-related piping systems performed in accordance with I.E. Bulletin No. 79-14.

Following completion of low power physics testing the unit was returned to Service on 800120.

Total dura-tion of outage 2222.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Reactor/Turbine trip due to Steam Flow/Feedwater Flow mismatch coin-cident with low level in No.

2 steam generator.

The trip occurred due.to difficulties with steam gen-erator level control during low power operation.

The unit was C

in ed n Next P

r: Fof'cd S: Scllc(lulcll Reason:

A-Efluipn)cnt Failure (Explain)

I).hlaiotcnance nr Test C.Ref>>cling D.Regulatnly Restriction E-Operator 'I'raining & Ucc>>sc lixanlioation F.Adnllnislfativc G.Operational Lrror(lixplaio)

I I.Otllcf(ExplJ>>l) hiclholl:

I.hlanual 2 hlaoual Sera>>1.

3-Auloloalic Scraln.

4.0tllcf (Explain) 4 Exhibit G - Instructions for PfepllfJtlon I)l Dat J Lotry Sllccts I'or Licensee Event Rcport (I.ER) l.ile (NURI!G-016I)

'L'xllibit I - Salne Source

UNITSHUTDOWNS AND POWER R IONS INSTRUCTIONS This report should describe all plant shutdovns during the report period. h 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 2o 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 thoueh the unit may not have been shut dov n cornpletelyi.

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 shutdov:n or significant reduction in power for that calendar year.

When a shutdown or signir!cant 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.

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

DATE.

This column should indicate the date oi the start of each shutdown or signiricant power reduction.

Report as year. month. and day.

August i4. 1977 wouid 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 significant power reducuons 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.

Seif<xplanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end of the report'period and pick up the ensuing down time in the following 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 gross hours in the reporting period.

REASON.

Cateeorize by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used. supply briet comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation Note that this dift'ers t'rom the Edison Electric Institute (EEI) definitions ot'Forced Partial Outaee" and

-Sche-duled Partial Outage."

For these turin~. 1:El uses a cliange of

..0 MW as the break point.

For lareer power reactors, DO MW is tiiiismall a chance to warrant explanation.

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 aII 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 correlation should be noted as not applicable (iN/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 (NUREG4161).

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.

COMPONENT 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 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 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'REVENT 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 tenn corrective action taken. ifappropri ~

ate.

This column should also be used for a description of the major safety. related corrective maintenance performed durine the outage or power reduction including an identification of the critical path activity and a report of any single release ot radioactivity vr sinele radiation exposure specitically associ-ated with the outage which accounts for more than 10 percent oi the allowable annual values.

For long textual reports continue narrative on separate paper and reterence tlie shutdown or power reduction ior ibis nJffJtlve.

UNITSIIUTDO)UNS AND PO)UER REDUCTIONS

~J1989 I)OCKETNO.

DATF 2-11-80 coMPLFTFD Dy B.A. Svensson TELEPIIONE 616 465-5901 PAGE 2 of 2

Nil.

I);Itc PI

~98j

4) ~

c

~

Q m ~rx:

~ Vl Liceoscc I:vent Rcport 4 Cause &. Corrective Action lo Prevent Rccurrcncc 65

( ontinued) 66 800124 67.

800128 15.0 G

0

=B-N.A.

N.A.

ZZ ZZZZZZ ZZ 'ZZZZZ returned to power the same day and the power escalation test program commenced.

'urbine/Reactor trip due to low main condenser vacuum.

The low vacuum condition was caused by operator valving error.

Unit returned to Service 800125.

Reactor power in-creased to 90K 800128.

Reactor power reduced to 65K to re-move East main feedpump turbine to check for condenser tube leaks.

Re-actor power returned to 90K, 800129.

Reactor power reached 100K for the first time on Cycle II on 800131.

I F: Forced S: Schcdolcd Reason:

A-EI)uiplncnt Failure (Explain)

I)-hiahltcnance or Test C-Refueling D-Regulatory I(cstriction E.Operator Training & Lice>>sc Lxamhiation F-Administ rat ivc G Opcratio>>al Lrror (I'.xplaio)

I I.Other (Explain) 3 hlcthod:

I-Maoual 2 Manual Sclaot.

3-Aulonlatic Scranl.

4-Other (Explain)

Exhibit G - Inst ruclioos for Preparation of Data Lntry Shccts for Licensee Event Report (I.I'.R) File (NURI!G-OI6I)

Lxhlblt I SaoII. Sour<<

UiLITSHUTDOWNS AND POWER R IONS 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 20k 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 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 colulnn 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 should be made for both report periods to be sure J~l 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.

August i4. 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 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 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 forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.

Self<xplanatory.

When a shutdown extends beyond the end ot a report period, count only the time to'the

'nd of" the report period and pick up the ensuing down time in the following report'eriods.

Report duration 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.

Categorize hy letter designation in accordance with the table appearing on the report form. Ifcategory H must he used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize hy numher designation INole that this difters lrnm the Edison Electric Institute IEEI) definitions of -Forced Partial Outage" and

-Sche-duled Partial Outage."

F>>r these tern>>. EFI uses a cllange ol'.0 MW as the break point.

For larger power reactors.SOMW is I>>'> small a change to warraill explanati>>>l.

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 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 of Exhibit G

~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

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.

CO1>IPONEiilT 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-related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release ol radioactivity or single radiation exposure speciticaily associ-ated with the outage which accounts for more than 10 percent oi the allowaole annual values.

For long textual reports continue narrative on separate paper an>I reference tile shutdown or power reduction ior this narrative.

(9/ I

DockNo.:

Unit Hame:

Completed By; Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 R,.S.

Lease (616) 465-5901 February 14, 1980 lof 4 MONTHLY OPERATING EXPERIENCES -- JANUARY, 1980 Hi hli hts, At the start of the reporting period, this unit was still out of service from its first refueling outage which had started 10/19/79.

All refueling items had been completed by 12/23/79.,'ut the Unit was still on "HOLD" from start-up while analysis of hangers and restraints to safety related piping systems was being made.

After low power physics testing of the core, the Unit was returned to service 1/20/80.

All of this is detailed in the summary.

There was one other short outage during the reporting period.

This is also detailed in the suranary.

Total electrical generation for the month was 182,750 Mwh.

~Summar 1/06/80 -- Source Range Nuclear Instrument N-32 was inoperable for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period due to loss of high voltage.

1/07/80 -- Containment Radiation Monitors R-11 and R-12 were in-operable for a 14.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for piping modifications.

1/08/80 -- Containment Radiation Monitors R-ll and R-12 were in-operable for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for repairs.

The High Demand Fire Pump was made inoperabl,e to allow relocation of a hose station.

This pump was again operable 1/15/80.

1/12/80 -- All required modifications to hangers and restraints of safety related piping systems were completed,,and.the Unit was released for start-up.

The Reactor Plant en-tered Mode 4 at 0846 hours0.00979 days 0.235 hours 0.0014 weeks 3.21903e-4 months .

Containment Radiation Monitors R-ll and R-12 were in-operable for a 2.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period while a Leak Rate Test was performed.

Dock No.:

Unit Name:

Completed By; Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit g2 R.,S.

Lease (616) 465-5901 February 14, 1980 2of 4 1/13/80 -- The Reactor Plant entered Mode 3 at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months and was at full temperature and full pressure at 1342 hours0.0155 days 0.373 hours 0.00222 weeks 5.10631e-4 months .

During the Heat-up, Auxiliary Feedwater was injected into Steam Generators 21 and 24 at several temperature points.

This was to test the Thermal Stress on the feedwater piping connected to the steam gen'erators.

The piping to the 24 Generator is equipped with a Ther-mal Sleeve and preliminary data indicates it reduces the stresses greatly.

The North Safety Injection Pump was inoperable for' 26;-5 hour period starting at 1227 hours0.0142 days 0.341 hours 0.00203 weeks 4.668735e-4 months while a weld repair was made on the pump casing vent.

1/15/80 Control Rod Drop Tests were completed at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months .

1/17/80 -- Initial criticality of the new reactor core was obtained at 1654 hours0.0191 days 0.459 hours 0.00273 weeks 6.29347e-4 months .

1/18/80 The West Containment Spray Pump was inoperable for an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period to do required maintenance.

1/19/80-- After completion of Low Power Physics Tests, Reactor Power was increased to 4/ at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months , and Unit start-up commenced.

The Turbine/Generator Unit was rolled at 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months .

The Turbine/Generator Unit tripped at 2324 hours0.0269 days 0.646 hours 0.00384 weeks 8.84282e-4 months due to high water level in 821 Steam Generator.

The reactor also tripped because power was greater than 10'A.

1/20/80 -- The reactor was returned. to criticality at 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months .

The Turbine/Generator was rolled at 0532.

The Turbine/Generator was Overspeed Tested with the 110% trip operating at 1985 RPM and the 112Ã trip operating at 2011 RPM.

At 0857 hours0.00992 days 0.238 hours 0.00142 weeks 3.260885e-4 months , while recovering speed from the last Overspeed Test, the acceleration rate used was too great.

This caused the steam generator levels to rise, resulting in a Turbine Trip and also a Reactor Trip because turbine power was indicated greater than 10/.

I

(

Docket Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.,C.

Cook Unit 82 R.

S.

Lease (616) 465-5901 February 14, 1980 3of 4 1/20/80--

(Cont'd)

The Reactor was returned to criticality at 1050 hours0.0122 days 0.292 hours 0.00174 weeks 3.99525e-4 months .

The Turbine/Generator Unit was rolled at 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months and paralleled to the system at 1240 hours0.0144 days 0.344 hours 0.00205 weeks 4.7182e-4 months .

One more Turbine Trip and Reactor Trip occurred at 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months .

The reason for this was Steam Flow/Feed Flow mismatch coincident with low steam generator level.

The Reactor was returned to criticality at 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months .

The Reactor tripped at 1912 hours0.0221 days 0.531 hours 0.00316 weeks 7.27516e-4 months due to l,ow level in 823 Steam Generator.

We do not normally have this amount of trouble, but our start-up feedwater control is manual through the normal large Feedwater Regulating Yalves, and level control can be difficult.

The Reactor was returned to criticality at 2029 hours0.0235 days 0.564 hours 0.00335 weeks 7.720345e-4 months .

The Turbine/Generator Unit was rolled at 2109 hours0.0244 days 0.586 hours 0.00349 weeks 8.024745e-4 months and paralleled to the system at 2223 hours0.0257 days 0.618 hours 0.00368 weeks 8.458515e-4 months .

1/21/80

-, - Reactor power was increased to 44.5X by 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months .

Reactor power was increased to 49'A by 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months .

The West Containment Spray Pump was inoperable for a 13 hour1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months period to perform required maintenance.

1/24/80-- The Unit and Reactor tripped from 494 power at 1846 hours0.0214 days 0.513 hours 0.00305 weeks 7.02403e-4 months due to low vacuum in "B" Condenser.

Both air offtakes had been inadvertently valved off, allowing non-condenables to collect.

The Turbine Driven Auxiliary Feedwater Pump failed to start on the Unit Trip.

Thi s was traced to a mechanical latch problem.

This was repaired and proven operable prior to returning the Reactor to cr itical.

1/25/80 -- The Reactor was returned to criticality at 0558 hours0.00646 days 0.155 hours 9.22619e-4 weeks 2.12319e-4 months .

The Turbine/Generator was paralleled with the system at 0940 hours0.0109 days 0.261 hours 0.00155 weeks 3.5767e-4 months .

Unit power was increased to 65% by 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months and, held at this point, due to the West Hain Feed Pump not being available for service.

Docke~.:

. 50-316 Unit A&e;,D,,C. Cook Unit.g2 Completed By;

. R,,S.. Lease Telephone:

('616) 465-5901 Date:

February 14, 1980 Page:

4 of 4 1/27/80 -- The West Main Feed Pump was placed in service at 1500 and Unit power was increased to 80/.

1/28/80 -- The West Essential Service Water Pump was inoperable for a

5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for repairs to the pump strainer.

Unit power was increased to 905 by 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months .

Power was reduced to 65K over a 1.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months ramp starting at 1741 hours0.0202 days 0.484 hours 0.00288 weeks 6.624505e-4 months to remove the East Main Feed Pump from service to check for suspected tube leaks in the condenser.

Power was returned to 904 over a 4.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months .

1/29/80 -- Containment Radiation Monitor R-ll was inoperable for a 22 hour2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months period due to filter drive failure.

The East Component Cooling Water Pump was inoperable for a 50.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period,,starting at 0629, to install addi-tional bracing to the discharge line.

Power was increased to 93K by 2334 hours0.027 days 0.648 hours 0.00386 weeks 8.88087e-4 months .

1/30/80 The "CD" Emergency Diesel Generator was inoperable for a 7.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to repair Jacket Water Leaks.

The North Safety Injection Pump was inoperable for a 7.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to perform required maintenance.

Pressurizer Pressure Channel IV was inoperable for a 3.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to replace the transmitter.

1/31/80 Power was increased to 97%%d by 0428 hours0.00495 days 0.119 hours 7.07672e-4 weeks 1.62854e-4 months .

The South Safety Injection Pump was inoperable for a 7.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for necessary maintenance work.

The Unit was loaded to 100/ power by 2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months .

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 D.

C.

Cook - Unit No.

2 2-11-80 B. A. Svensson 616 465-5901 1 of

MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1980 M-2 M-3 M-8 CSI-1 Turbine driven auxiliary feedpump discharge check valve to No.

4 steam generator, FW-138-4, leaked by.

Machined disc, lapped and blued seat, and reassembled.

No.

4 boric acid transfer pump was leaking.

Disassembled and in-spected pump.

Reassembled using new gaskets and replaced mechan-ical seal.

Had pump tested.

2AB2, diesel fuel oil transfer pump check valve leaked by.

Lapped valve seat and replaced gasket.

'The 2W RHR pump mechanical seal was leaking.

The seal was replaced.

Pump retested.

The 650'ontainment airlock inner door lock did not operate properly.

The shaft and door locking gear were replaced.

Retest was satisfactory.

The vent on the 2N safety injection pump was found cracked.

The crack was repair welded.

Necessary NDE performed.

The 2S safety injection pump discharge safety valve, SV-98, leaked by.

Valve was rebuilt.

CRI adjusted set point and valve was reinstalled.

Turbine driven auxiliary feedpump would not start.

Adjusted the latch for the trip and throttle valve and tested satisfactorily.

The trip coil for the turbine driven auxiliary feedpump was arcing across the cover.

The coil had been damaged and required replacement.

The cover was not reinstalled.

The cover had previously caused the failure of the coil.

C&I-3 CLI-4 NTR-240, reactor coolant loop 4 cold leg temperature indication failed low.

A fuse had failed on the power supply for the resistance to current converter.

The fuse was replaced and the instrument loop returned,to service.

h CCRP inverters frequency began to change between 60 and 63 Hertz.

The oscillator control potentiometer R-5 was adjusted for the correct frequency during the inverters operation with a reference AC source.

The flux mapping system detector A failed.

A spare detector was in-stalled into the drive unit.

The drive unit was re-zeroed and tested for proper operation with the new detector assembly.

~

1I

ML17318A630

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