Text

Monthly Operating Rept for Mar 1982
	ML20052F968
Person / Time
Site:	Cook
Issue date:	04/06/1982
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20052F946	List: ML20052F945; ML20052F968;
References
	NUDOCS 8205140197
	Download: ML20052F968 (7)
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CPERATING DATA REPORT 5'0-316' DCC'GT No.

DATI 4-6-82 Cost?LITIO SY W.T. GilIett TELI? SONG 61 A_a AA_m001 OP"KAT!NG S ATUS Donald C. Cook 2

No::s

1. Unic Name:

March 1982

2. Reporting ?:dod:

3391

3. U~WThe = 1?ower(51Wt):

1133

4. Nameplat's Racing (Cross 5tWe):

1100

3. Design Se==i=1 R::ing (Net 51We):

III8

6. 312ximuur Dependahls Cap: city (Cross 51We):

1082 T. Sime mm Dep--d-'le C:p:ci:/ (Not 51We):

8. If C.ange Oc=r in Capaci:y Rath;s (1:=ms Number 3 hcgh 7) Sine: Last Repor:. Give R:ssons:

9. Power Level To Which Res==::d.If Any (Net 31We):

10. Reasons For Ru=i::!ons.lf Any:

This 51onth

~ Yr.40 Data Cu=uh:ive 744 2160 37.224

11. Hours In Reporting P :fod 268.5 1666.1 28;.641.1

12. Numb =r of Hou:: R===:or Was Cri:i=1 0

0 v

13. Re:ctor Rese.ve Shu::iown Hou:2 254.6 1645.3 24,866.3

14. Hours Gene =ter On.Lhe 0

0 0

15. Unic R: serve S~nutdown Het=:

833,555 5,325,689 79.386.510

16. Cross The:=:1 En=rgy Cen==ted (5twH) 276,030 1.756.430 25.464.210

17. Gross E!ec=ic:!Imergy Gen-::: d f.htWH) 266,396 1,694,669 24.538.810

13. Net EIe==f=1 E=:r;y Genen::d (.'.tWE) 34.2 76.2 71.6 - -

19. Unit Service F:ctor 34.2 76.2 71.6

20. Unic Av II2bi!I:v F:c:or 33.1 72.5 67.0

21. Unit C:: ci:y 5:c:er(Using >!DC Net)

32. 6 71.3 66.2

22. Ucit Capscity F:::or(Using DER Nes) 65.8 23.8 14.9

23. Unic Fore:d Cu: ge R:te

24. Shutdowns Scheduled Over Nen 5 Ston:hs (Type. Date.:n:! Dct::fon of E:ch1:

S. If Shu: Down At End Of Report Period.Estim::ed D:te o(Scarn:p:

25. Units In Tes: S ::us (Pnor to Ce==ercist Ope =:fo:.1:

Toreest Achieved INITIA L CK!T*CAIJTY INITIAL ELECTR C(

CO.*i*. I?.C:A:. 0?SRA7:CN (58/*T )

l 8205140197 e20413 PDR ADOCK 05000316 i

R PDR

AVERAGE DAILY UNZT POWER LEVEL DOCKET-NO. 50-316 UNIT 2

DATE 4-2-82 COMPLETED BY W. T. Gillett-TELEPHONE 616-465-5901 MONTH March 1982 DAY AVERAGE DAILY POWETt LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 1091 17

~

2 1092 18 3

1085 19 4

1090 20

~

5 1091 21 6

1091 22 7

1086 23 8

1090 24 9

1090 25 10 913 25 11 384 27 12 28

~

13 29 4

14 30 15 31 3

16 l

INSTRUCTIONS On this femat list the average daily unit power level in MWe-Net for each i

day in the reporting month. Comoute to the nearest whole megawatt.

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DOCKET NO. 50-316 UNIT SilUTl) OWNS AND POWER REDUCllONS UNIT N AME D.C. Cook - Unit 2*

DATE 4-13-82 March,1982 COMPLE1ED BY B.A. Svensson REPOR I MONTil TELEP110NE (616) 465-5901 PAGE 1 of 2 e.

.$ E 3

$4 L icensee

[ v,,

Cause & Coneciive No.

Date g

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[ 6, M

Repoll #

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Preveni Recustence 6

6 108 820311 F

489.4 B

1 N.A.

ZZ ZZZZZZ A power reduction was started on March 10,1982 due to No. 23 R.C. Pump Motor temperatures being at their max-imum limit. Reactor power was held at 85%. A further reduction to 75%

was made later the same day. On March 11,1982 the decision was made to remove the unit from service due to the high motor temperature problem and indications of excessive leakoff from the No. 2 seal on the No. 23 R.C.

Pump. The unit was out of service at 1328 hours0.0154 days 0.369 hours 0.0022 weeks 5.05304e-4 months on March 11, 1982. A two-week ice condenser. ice basket weigh-ing surveillance outage had been scheduled for early in April. This was. rescheduled to the present outage.

The No. 2 and 3 seals were replaced on No. 23 RLP and the No. 23 RCP 1

2 3

4 1:: Foiced Reason:

Method:

Exinbit G. Instructions S: Sthed uled A I?<luipinesis Failine(1.xplain)

1. Manual for Prepasation of D.na 11 Maintenance or Test 2 Manual Scram.

Enuy Sheets fos 1.icensee C. Refueling

_l Automatic Saam.

Event Repose (1.ER) File INtlRIL-D Regulatoiy Resisiction 4-Oihes ( Explain) 0161) lEOpenalor l'saining & l.acense 1:xamination F Administrative 5

G Opesanonal liiins (Explain) lixinbit I - Same Somce pl/D) iI Othc (lixplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should descr:be all plant shutdowns dunng the in accordan:e with the table appearms on the report form.

report penod. In addition. it should be the source of explan.

If category 4 must be used. supply brief comments.

anon of sigmEcant dips :n average power levels. Each signi.

fi:2nt reduction m power level (Jreater than 20% reduction LICENSEE EVENT REPORT :. Reference the applicable m average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportaole occurrence pertammg to the outage or power abould be noted, even thouah the umt may not have been reduction. Enter the first four parts (event year, sequent:a!

shut down completely. For'sucn reductions in power level, report number occunence code and report type) of the tive l

the duration should ce listed as zero, the method citeducuan part designation as desenbed in item 17 of Instruccons for should be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Entry Sheets for Licensee Event Report Acuan to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This inforestion may not be Cause and Correenve Acnon to Prevent Recurrence column immediately evident for all such shutdowns. of course since should be used to provide 2ny needed explanation to fully turther mvest:gation may be required to ascertam whether or desenbe 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.

NU5t BER. T!us column should indicate the sequentral num, the positive mdication of this lack of correlation should be ber. assigned to each shutdown or sigmncant reduction m power noted as not applicable (N/A).

fc!r that calendar yer.r. When a shutdown or sigmficant power reduction begms m one report penod and ends in another.

SYSTE31 CODE. The system in which the outage or power an entry should be made for both report penods to be sure reduction onginated should be noted by the two digit code of.

all shutdowns or sigmncant power reducuens are reported.

Exhibit G. Insuuctions for Preparation or Data Entry Sheets Unt:1 a unit has ach:eved its first power generation, no num.

f r Licensee Event Report (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that do not 6t any existmg code should be designs.

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 signidcant power reducuon. Report as year. month. and day August 14.1977 would be reported CONIPONENT CODE. Sele:t the most appropnate component as 770814 When a shutdown or significant power reducuan from Exhibit i. Instruenons for Preparation of Data Entry begms m one report pened and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG4161L be made for both report penods to be sure all shutdowns usmg the following entiena:

or sigmficant power redu nons are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-Juled." respe:tively, for each shutdown or significant power B.

If not a component failure, use the related component:

reducuon. Forced shutdowns include those required to be e.g.. wrong valve operated through error; list valve as mitiated by no later than the weekend fo! lowing dis:overy component.

of an off-normal condition. It is recognized that some judg.

ment is regtured in categonzmg shutdowns in this way. In C.

If a cham 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 desenbed action was taken.

under the Cause and Correcuve Act:on to Prevent Recur.

rence column.

DURATION. Selfexplanatory. When a shutdown extends beyond the end or 2 report penod. count only the time to the Components that do not fit any existmg : ode should be de-end of the report penod and pick up the ensuing down :tme signated XXXXXX. The code ZZZZZZ should be used for m the followmg report penods. Report duration of outages events where a component designation is not applicable.

rounded to the nearest tenth of an hour to fac:litate summation.

The sum of the total outage hours plus the hours the genera.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

tor was on line should equal the pass hours in the reportmg RENCE. Use the column in a narrative fastuon to ampitfy or penod.

explam the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut.

wn r 4mt am Mwn ucu n an imme ate and REASON C4teaunee bv 'etter destanattun in accordance

- - d with the table appearms on the report form. If category H

"" ' """ *'" " **""* ' *EF' E"'

must he used suppiy bnet comments.

ate. This column should also be used for a desenption of the maior safety-re!ated correcuve mamtenance performed dunna SIETHOD OF SHUTTING DOWN THE REACTOR Ofs the outaae or power reduction me!uding an identification of

d M "W *"d * E " # 20Y ""b '*5# #,

REDUCING POWER. Categonze ev number designatzun radioaeuvity or single radianon exposure speettiestly associ.

1%e that this differs trom the Edison Electne Insutut, ated with the outage wluch accounts for more than 10 percent tEEI) derimtions of " Forced Parnal Outage" anc "Sene.

of the allowaole annual values.

Juled Partial Outae For these term >. I El uses 4 hange or For long textual reoorts contmue narrative on separate racer

.t0 SIW as the break pmnt. For larger puwer reactors. 30 5tW aid referen e the shutdown or power redu. nun rm nu, is im smJll J shJn$e to *Jr ant v\\plJOJt!OH.

Marrauve.

N#77

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50-316 DOCKEINO.

UNITSiluTDOWNS AND POWER REDUCTIONS D.C. Cook - Unit 2-UNII N AME DATE 4-13-82 COMPLE1ED llY B.A. Svensson REPORT MONTil March. 1982 TEl.EPilONE (616) 465-5901 PAGE 2 of 2 "i-

.E e E

,EM i s.censee e

f C,

f5 3 Len 5 g *,

c4 Cause & Corsective Action to N"-

DJ'c R

E@

Ss5 livent a?

jis g Report #

N0 E'

Prevent Recussence 6

108 Continued motor temperature problem was cor-rected by cleaning the RCP motor air coolers and the lower containment air coolers. The unit was returned to service on March 31, 1982 and reached 100% on April 2,1982.

I 2

3 4

17: 1 osceil Reason:

Methoti:

Exlabie G Instsuctions S: Sthetinleil A-Equipmer.: 1:ailuie (Explain) 1 Manual for Psepas.iiion of Data 11 Maintenance or Test 2 Manual Sesam.

Entsy She. ;., noi 1.icensee C Refueling 3 Automatic & ram.

livent if.posi (i.l!R) File iNURI'G.

D Regulatoiy Restricsion l Othes (lixplain) 0161) 110pesaios haining & License lixamination 1;- Athninist sative 5

G Opesational licor (lixpliin) lixhibit 1 Same Somce F1/77) 11 Olhes (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns dunng the in accordance with the tacle appearmg on the report form.

report penod. In addition. It should be the source of explan-If category 4 must be used. supply brief comments.

atton of signiScant dips m average power levels. Each signi-Scant reduction m power level (Steater than 20% reduction LICENSEE EVENT REPORT =. Reference the applicable m sverage daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportaole occurrence pertammg to the outage or power should be noted even thoudt the urut may not have been reduction. Enter the Srst four parts (event year, sequential shut down completely. For'such reduccons m power level, report number occurrence code and report type) of the tive l

the duration should be listed as zero, the method of reduction part designation as desenbed in item 17 of Instruenons for should be listed as 4 (Other), and the Cause and Correenve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG 0161).

T'us information may not be r

Cause and Correenve Acnon to Prevent Recunence column immediately evident for all such shutdowns, of course, smce should be used to prov de any needed explanation to fully rurther investigation may be required to ascertam whether ur desenbe 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 reportaole occurrence.

NU5tBER. This column should indicate the sequential num-the positive indication of this lack of correlation should be ber assigned to each shutdown or sigmricant reduction m power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmficant power SYSTE31 CODE. The system in which the outage or power reduction begms m one report period and ends m another.

an entry should be made for both report penods to be sure reduction ongmated sh'ould be noted 'oy the tw'o digit code of all shutdowns or siam $ cant power reducuons are reported.

EWmt G Instrucuans for Preparauon of Data Entry Sheets Until a unit has sch'ieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG-0161).

ber should be assigned to each entry.

Systems that do not fit any existmg 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 applicaele, of each shutdown or sigmScant power reducuen. Report as year. mcnth. and day. August 11.10"7 would be reported COSIPONENT CODE. Select the most aopropriate component as 770314. When a shutdown or sigmficant power reduccan from Exhibit ! - Instructions for Preparanon of Data Entr3 begms m one report penod and ends m another, an entry should Sheets for Lleensee Event Report (LER) File (NCREG 0161 L be made for both report periods to be sure all shutdowns usmg the followmg cntiena:

or sigmficant power reductions are reported.

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

duled." respectively, for each shutdown or signincant power B.

If not a component failure. use the related component:

reducuon. Forced shi.tdowns include those required to be e.g.. wrong valve operated through errort list valve as mitiated by no later than the weekend following discovery component, of an off. normal condition. It is recognized tha: some judg.

ment is required in categorizmg shutdowns in this way. In C.

If a chain of fatlures occurs. the first component to mal-general, a forced shutdc,wn is one that would not have been function should be listed. The sequence of events. mciud-completed in the absence of the condition for which corrective ing the other components which fail. should be desenbed action was taken.

under the Cause and Corrective Action to Prevent Recut-rence column.

DURATION. Self explanatory. When a shutdown extends beyc.nd the end at a report penod. count only the tune to th Components that do not fit any existmg code should be de-Signated XXXXXX. The code 777777 should be used for end o,t the report penod and pick up the ensumg down time m the followmg report penods. Report duranon of outages events where a component designation is not applicable.

rounded to the nearest tenth of an hour to factlitate 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 ampitfy or tor was on line should eqtal the gross hours in the reportmg explam tf e circumstances of the shutdown or power reduction.

penod.

The column should include the spectfic cause for each shut-down or signtricant power reduction and the immediate and REASON. Categonee b) etter deugnation in accordance contemplated lona term corrective action taken, if appropn-with the table appeartng on the report form. If category H ate. This column'should also be used for a descnotion of the must be used suppiy bnet comments.

maior safety.related corrective maintenance performed dunna

\\lETHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identincation ot}

REDUCING POWER.

Categorue by number designanon the entteal path aennty and a report at any smgle release et radioactivity or smale radiation exposure speettiesily assect.

INote that this differs from the Edison Electnc Institute ated with the outage which accounts for more than 10 percent (EEI) derimt:ons of " Forced Parnal Outare" and " Sche, of the allowable armual vslues.

,2aled Partial Outage." For these terms. eel uses a shange or For long textual reports contmue narrative on separate paper

.0 Slw as the break pumt. For targer power reserors.30 5tw and rererense the shutdown or power redustion for ui>

s rmi small 4 shange to wanant oplaNtion.

narrative.

19'7"

]

~~

o Docket No.: 50-316 Unit Nrme:

D. C. Cook. Unit #2 Completed By:

C. E. Murphy Telephone:

(616) 465-5901

.Date: April.8, 1982 Page:

1 of 1 MONTHLY OPERATING ACTIVITIES - MARCH, 1982 Highlights:

The Unit entered this reporti:g period operating at 100% power. At 0052 hours6.018519e-4 days 0.0144 hours 8.597884e-5 weeks 1.9786e-5 months on March 10, 1982,-a power reduction of 3% per hour was begun in an-attempt to reduce the temperature on the #3 reactor coolant pump motor, which was approximately 145'C.

The power reduction was stopped at 84.5%

at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months on March 10, 1982. During this time, intermittent alarms were being received on the #3 reactor coolant standpipe which indicated that the #2 seal on the #3 reactor coolant pump was leaking excessively.

At 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months on March 10', 1982, further power reduction was started -

reactor power was at 75% at 2335 hours0.027 days 0.649 hours 0.00386 weeks 8.884675e-4 months on March 10.

At 0901 hours0.0104 days 0.25 hours 0.00149 weeks 3.428305e-4 months on March 11, 1982, it was decided to shut the Unit down and go to Mode 5 for the purpose of repairing the seals and checking the motor windings on the #23 reactor coolant pump. The Unit was removed from ser-vice at 1328 hours0.0154 days 0.369 hours 0.0022 weeks 5.05304e-4 months on March 11, was in Mode 5 at 0319 hours0.00369 days 0.0886 hours 5.274471e-4 weeks 1.213795e-4 months on March 12, and the RCS was at 1/2 Loop by 0130 hourc on March 14.

Filling and venting of the reactor coolant system was commenced at 0433 hours0.00501 days 0.12 hours 7.159392e-4 weeks 1.647565e-4 months on March 26; the reactor was made critical at 0650 hours0.00752 days 0.181 hours 0.00107 weeks 2.47325e-4 months on March 30.

Trouble was then encountered with a broken guide bearing on the #23 steam generator stop valve. Therefore, at 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months on March 30, the reactor was made subcritical and the Unit returned to Mode 3.

At 1917 hours0.0222 days 0.533 hours 0.00317 weeks 7.294185e-4 months on March 31, repairs were completed to the #23 stop valve, and the reactor was taken critical at 2015 hours0.0233 days 0.56 hours 0.00333 weeks 7.667075e-4 months on March 31.

The Unit was paralleled with the system grid at 2255 hours0.0261 days 0.626 hours 0.00373 weeks 8.580275e-4 months on March 31.

At 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months on March 29, while in Mode 4, an accidental safety injection signal was received on Train 'A' only. This was caused by the failure to block the steamline isolation S.I. signal during the performance of the start-up STP's.

At 0450 hours0.00521 days 0.125 hours 7.440476e-4 weeks 1.71225e-4 months .on March 31, 1982, an ' Unusual Event' was declared due to de-i tection of Hydrazine levels of greater than 2 ppm in the Auxiliary Build-ing. The Auxiliary Building was evacuated by a P.A. announcement and the requisite parties were informed of the Unusual Evet.t.

The event was term-inated at 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months on March 31, 1982.

Total electrical generation for this month was 276,030 mwh.

Summary:

i l

03-02 The Auxiliary Cable Vault CO Fire Suppression system was 2

inoperable for a 0.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period for repairs.

03-09 The West Centrifugal Charging Pump was inoperable for a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months period to change oil.

DOCKET N0.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 4-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1982 M-1 Alternate charging line check valves, CS-328L1 and CS-329L1, had body-to-bonnet leaks.

Replaced the bonnet gaskets in both valves.

M-2 Boron injection tank bypass valve, SI-125 had seat leakage.

Repaired valve seat and replaced valve bonnet assembly.

M-3 The ESW flange and pipe at the outlet of the west CCW heat exchanger had indications of wall thinning as determined by NDE. Replaced the flange and pipe.

Had necessary NDE performed and completed a hydrostatic test.

M-4 The No. 2 seal on the No. 23 reactor coolant pump had greater than normal leakoff.

Replaced the No. 2 seal ring and runner, the No. 3 seal ring and runner, and the No. I seal insert.

Reassembled using new o-rings and gaskets. Also, realigned the pump to the motor.

M-5 The east containment spray pump drain valve, CTS-101E was leaking by.

Replaced the valve bonnet assembly.

M-6 One fan belt on the north control room air handler, HV-ACRA-1 was broken.

Removed the unit from service and replaced the belts.

Had the unit tested.

M-7 Safety injection check valve, SI-142L3 had a body-to-bonnet leak.

Dis-assembled, cleaned, lubricated and reassembled valve.

M-8 No. 4 steam generator blowdown regulating valve, DRV-341 had a body-to-bonnet leak.

Replaced the gaskets and had the valve reassembled.

M-9 Auxiliary feedwater check valve, FW-183-3 had a body-to-bonnet leak.

Replaced the bonnet gasket.

M-10 Pressurizer spray control valve, NRV-164 was leaking by.

Replaced the valve trim assembly and gaskets.

Had the valve tested.

M-11 RHR check valve, SI-170L3 had a body-to-bonnet leak.

Replaced the l

bonnet gasket.

i M-12 RHR motor operated containment isolation valve, ICM-111 had a body-to-bonnet leak.

Replaced the bonnet gasket and had the valve tested.

1 i

, - ~ -

DOCKET N0.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 4-13-82 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-590,l_

PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1982 M-13 No. 4 steam generator power operated relief valve, MRV-243 had a body-to-bonnet leak.

Replaced bonnet gasket and had valve tested.

M-14 CVCS letdown orifice valve, QRV-160 air operator was leaking. Replaced the air operator diaphragm and had the valve tested.

M-15 The linear ball bearing had become displaced on MRV-230, No. 3 steam generator stop valve.

New bearing retainers were fabricated and in-stalled and the valve was tested.

C&I-l The No. 3 steam generator 10-10 level alarm was in with normal levels in the steam generator. The bistables were recalibrated to within specifications.and returned to service.

C&I-2 Annunciator 5 Drop 22 RWST level at 35,000 gallon alarm was in with 97% level indicated.

Investigation revealed that the current re-peater and bistable unit had both drifted out of specification; both were recalibrated and the loop was returned to operation.

C&I-3 Discrepancy exists between the two lower containment sump level in-dications (NLI-311 and NLI-310).

Both transmitters had lost part of the fill. The lower sensors and capillary tubing were replaced on both. After filling the systems, both transmitters were calibrated and returned to service.

C&I-4 Containment Hydrogen Monitoring System regulator valve, ERV-41 would not regulate pressure below 25 psi. The valve's plug and seat were lapped-in and new gaskets were fabricated to restore pressure regulation.

C&I-5 Safety valve, SV-38 in the Nuclear Sampling Room sampling cabinet was leaking-by. The valve was found to lift at 77 psi.

SV-38 was then re-placed with a newly-recalibrated safety valve to restore the correct lift pressure.

C&I-6 New mounting brackets have been installed on the main turbine stop valve static limit switches. These new brackets should greatly reduce the failure rate due to vibration.

C&I-7 Detector ' A' in the incore flux mapping system had a defective drive position encoder readout.

The drive unit's power supply was changed out to correct the counter readout.

.u

__

ML20052F968

Text

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