Text

Six-Month Operating Rept 2 for Jul-Dec 1971
	ML20126F069
Person / Time
Site:	Monticello
Issue date:	12/31/1971
From:	; NORTHERN STATES POWER CO.
To:	;
References
	NUDOCS 9212300099
	Download: ML20126F069 (134)
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tGRTHERN STATES POWER C0f,PAf#

ADtd ICELLO thCLEAR GENERATI tG PLArg

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REPORT TO UNITED STATES ATOMIC ENEFGY COMMISSloy DIVISION OF REACTOR LICEN$ltn LICEtBE ID. DPR-22 i

SI X-t,0t#H OPERATI fG REPORT 10, 2 djLY 1, 1971 to DECEMBER 31,_1971 1

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11 CHf0fDLOGICAL HISTORY l

111 OPERATl fD DAT A 1

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RADIDACTIVE WA51E DAT A A.

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CHAfjGES, TESTS, AND EXPERIMEfAS i

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1 I t#f0 DUCT l0N This operating report for the Monticello Nuclear Generating Plant

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summarizes the six month period from July 1,1971 through December 31, 1971.

I t is submi tted in accordance wi th the reporting require-ments of the Provisional Operating License IPR-22 and Section 50.59 of 10 CfR 50 as described in the following paragraphs.

Section 6.6.D of Appendix A, Technical Speci fications, of the Pro-visional Operating License DPR-22 for the f.bnticello Nuclear Generat-ing Plant requires that a routine operating report be submi tted to the Diractor, Division of Foactor Licensing, of ite United States Atomic Energy Commission, at the end of each six month period. T he reports are required to contain the following information (summarized on a tronthly basis):

a.

Nuclear (1) Number of hours the plant was operated.

(2) Number of tirws the reactor was made critical.

(3) Gross thermal power generated.

(4) Operating histogram, showing the thermal power level of the reactor versus tirre for the report period.

( 5) Equivalent full Power Hours.

b.

Elect ri cal (1) Gross power generated ( i n M.Yh).

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(2) Not power cenerated (in U#h).

(3) Length of tir:n generator was on line (in hours).

c.

Shuidowns (1)

Number of scrams and shutdowns.

(2)

Duration of down time (in hours).

( 3) Feasons for outacea d.-

Maintenance (on systems or components desi ned to prevent C

or mi tigate the consequences of nuclear accidents).

(1) Nature of maintenance:.

e.E.,

routine, emergency, preventive, or corrective.

(2) he ef fect, i f any, on the safe operation of the reactor.

(3) The cause of any malfunction for which corrective main-tenance was requi red.

(4) The effects of any such malfunctions.

(5) Corrective and preventive action taken to preclude recurrence of mal functions.

(6) -lime requi red for completion, e.

Radioactive t iouid Waste (1) Total curie activi ty discharged.

(2) Total volumo (in gallons before dilution) of liquid waste m-di s charged.

(3) Total volume (in gallons) of dilution water used.

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i (4)

Average concent rat ion (in uc/cc) at ou t f all of discharge canal.

J (5) bimm concentration released for any consecutive 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during the reporting period, including timo and date.

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(6) Percentare of annual limi t released.

(7) Results of isotopic analyses and estimated curies of ca:h i denti fied nucli de released, j

(8) Total curie activi ty of T ri tium discharged.

f.

Gaseous Was 4 (1) Total curies acti vi ty-discharred separated tr.to noble j

rases, lodine, and par t i culates.

(2)

%imm activiiy released for any consecutive 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i

durinn ihe reporiinn period, i ncludinc iire and date.

(3) Por cestace o f maximum annual limi t ro' leased and f.PC

value, j

(4) Results of all isotopic analyses and estinated total j

curies of each identi fied nuclide released.

1 g.

Soli d Padioed i ve Wasie (1) Total volume (in cubic feet) of solid waste generated.

(2) Gross curie activity involved.

(3)

Dates and disposi tion o f the material i f shipped o f f-si te.

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Envi rennen 4 al 'kni to ri nn i

1 (1) A narrative summary, including correlation with ef fluent releases of the results of off-si te envi ronmental I

surveys perforned during the report period.

(2) Tabulation of the resulic of the environmental monitorinc p rog ram 7 including a figure showing location of the

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noni torinc stat ions.

(3) for any samples which indicate statistically significant levels of radioactivity above established background I

levels, a comparison with applicable 10 Cf R 20 limi ts shall be provided.-

Section 50.59,10 CFR 50, permits the holder of a license. authorizing operation of a nuclear reactor to make changes i n the facility, changes in procedures, and conduct tests or experiments, provided that the change, test or experiment does not involve a change in-4 the technical specifications or an unreviewed safety question.

T he licensee is requi red to report such changes, tests and experiements to the Commission.

i in addition to the above requirements this report includes a brief chronological-summary of the plant operating history du ri ng the report period.

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I1 CHFOfDLOGICAL HIS10HY-7/4/71 Completed 100 hour0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months warranty run.

7/5/71 Performed turbinn trip test from 100% power.

This completed all startup tests.

7/6/71 Completed ini t i al drywell inert ing.

7/7/71 High steam flow isolation setpoints set at tested value of 113%

of rated steam flow pending development, safety evaluation and review, and AEC approval of procedures for porforming tests at 140% of rated flow.

Reactor power limitedto90%ofrated.

7/14/71 While establishing steam flow to the main condenser followine a 2

reactor isolation, the water loop seal at the air ejectors discharge was lost, resulting in off car being discharged to the turbine buildi ng oucp. This resulted in the discharge of a small amount of gaseous activity (

2000 uci/sec) from the reactor building ventilation stack over a half hour period.

Modi fi cations. wo re made to procedures, the air ejector steam supply and the loop seal isolat ion cont rols to prevent a recur rence.

7/15/71 Outage to recove turbine stop valvo and intercep/demineralizer t valve startup to screens.

Replaced filter elements in condensate 7/25/71

'B' and chemically cleaned condensate /demineralizer 'C'.

7/2C/71 to

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8/7/71 Operated at 90% power.

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8/7/71 Reactor scram from condenser low vacuum due _ to cooling tower return line screens pluCE ng while going to closed circulating i

water system operation.

8/8/71 Operated at 90% power.

8/9/71-Reactor scram caused by improper opening of sensing line while calibrating condenser vacuum switches.

8/10/71 Operated at approximately 90% power, except' for brief periods to during August 11 and 12 when output varied between 50%-and 75%

8/20/71 power while. conducting tests o f-the various modes of ci rculating water system operation.

8/20/71

. Reactor scram f rom APRM Hi-Hi t rip caused by sudden increase in No. 11 recirculation pump speed.: Replaced f aulty control ampli fier.

P/21/71 Operated at 40% power.

8/22/711 Reduced power to hot standby _ to repai r-flange leak on 12-A l.p.

' drain cooler.

8/23/71 Operated at 90% power.

r to 8/25/71

. _ _ _ _ _ _ _ _ - 8/26/71 Shutdown plant to repair leak on 12-A feedwater heater.

While

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to shutdown discovered and repaired leak in generator hydrocen seal.

9/1/72 Also coplaced filtor elements in condensate /demineralizef vessels

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and

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9/2/71 Operated at 90% power, to 9/5/71 9/5/71 Low air pressure caused closure of condensate demin outlet valves which in turn caused a low suction pressure trip of the reacior feed pumps.

Peactor scram was initiated by low-water level Air covpressor loading valve repairs were completed sensors.

and additional operator training was instituted to prevent a recu r re nce.

9/6/71 Operated at 45% power while repairing foodwater pump fb.11 inboard seal.

9/7/71 Operated at 90% power.

to 9/9/71 9/9/71 Shutdown plant to test f<GIV closure reset circuit.

Ci rcui t found satisfactory.

9/11/71 Operated at 90% power except for a brief period during 9/15/71 7

to when load decreased to 50% due to a t r ip. of tb.11 reci rc pump.

9/21/71 Af ter re-connecting a loose wi re found in the reci re f.G set exciter centrol circuit, the recire pump was restarted and power was returned to 901 9/22/71 Reduced power to 50% to close 'B' steamline isolation valve -

and test HPCI system. Tesi veri fied ihat the di fferential pressure

-developed by7 the HPCI steam line flow elbow is af fected by flow in

' B' s teaml i ne.

The HPCI system was demonstrated to operato success-fully in both AUTO and !!ANUAL control with 'B' Steamlino f,G I V Shu t.

RHR service water pump No. 12 -t ripped ~ as a resul t of a short in

.t he mo t o r.

Wtor extensively damaged.

9/22/71 Operated at 90% power except for a brief period during 9/24/71 to when power was decreased to 60% io test the HPCI system.

9/24/71 9/24/71 Plant shutdown while investigating RHH Service. Water ' System flew anomal y.

Investigation revealed -that the vendor supplied flow orifico calibration-data was in error.

9/26/71 Operatedat90% power, to 9/27/71

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9/27/71 Reactor power' was reduced to 60% when No.11. 'reci rc pump ' f iel'd breaker tripped.

Cauce could not be determined.

-l 9/28/71 Restarted ib. Il recirc pump.

Reactor scrammed due to APF'A Hi-j Hi t r i p when fb. 11 reci rc pump speed suddenly incroased.

9/29/71 Operated at 60% power with one recire pump in operation while to investigation and repair of fb.11 recirc pump spoed and exei tation 9/30/71 controls were in progress.

10/1/71 Completed repairs to tb.11 recire pump controls, placed it in operation and brought reactor power to 90%.

10/12/71 Peduced power to 60% for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to replace fb.11 feedwater to pump inboard real.

10/13/71 10/16/71 tb 12 RHR Service water pump restored-to operable status with rebuili motor.

10/28/71 Reduced power to 60% for five hours to take No. 12 recire fB set out of service to replace brushes.

11/10/71

- Reduced power to 60% to take fb.11 Redire :S set out of service due to high vibration, 11/12/71 Scheduled Plant shutdown to install now design rotating assembly to in No. 12 RFP and per form general maintenance._. Tes t i ng _ and 12/31/71 inspections performed during the outage revealed that several fASIV's

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were leaking and several -torus baf fles had become detached from their-supports.

The outage was extended to repair the M31V's and to removo all torus baf fles. Other work completed during the outage included modi fication of the main steam flow res t ri ct o rs, extension of the main -steam relief valves discharge 1ines, i nstalla-tion of an of f gas loop seal low level isolation sensor, replace-ment of the set pressure adjusinent springs for the-main steam relief valves, and balancing of tb._ _11 Recire IS set.

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l i l. OPERATi tJG DATA A.

Nucl ear Year:

1971 July Aug.

Sept.

Oct.

Nov.

Dec.

.No. of hours the plant was operated.

490.1 586.2 650.5 745 289 0

++Number of tirnet the reactor was made cr itical 3

3 5

0 0

0 Gross thernal power Cenerated (UAD) 26, 399 32,027 32,299 45,694 16,PB4 0

.oEquivalent Full Power Hours 379 460 4(4 657 243 0

The plant is considered to be operating frun the initiation of control rod withdrawal to make the reactor critical, until the reactor is returned to the all-rods-in condit ion.

- This is the number of 1ines the rcactor was made er iiical fr om an ecsent ially all-rods-in condition.

Repeated critical and subtritical operations dur ire

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operator training exercises are not included.

- - Hi stograns of power oper at ion are included at the end of thi s sect ion.

B.

Elecirical Month G, o c s '/A'H Nel f/AH Hours Generating July 218,550 207,493 452 i

Aug 262,960 247,896 547 Sept 263,270 247,832 592 Oci 377,470 358,534 745 Nov 133,170 129,936 286 l

Dec 0

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Shutdowns

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Sept.

Oct.

Nov.

Dec.

Total No. Shutdowns 3

4 4

0 1

0 12 1

Hours Shutdown 253.9 157.8 69.5 0

456 744 1681.2 s

Scrams 2*

3 2

0 0

0 7

4 Ircludes Planned Scram for Turbine Trip Test.

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Durat ion of Down Shutdown Period Time.H g_g Acnson for Outage 2

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Julv 1971 i

1.

July 5,19'71 @ 0115 6.5 Scram.

Planned scram from turbine to July 5, 1971 @ 0749 t rip t est at 100% power.

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2.

July 14,1971 @ 1343 11.7 Scram. When a pressure tranunitter to July 15, 1971 @ 0130 was valved in service following i

routine calibration, a pressure

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surge occurred in the instrument sensing line.

The surge iripped the main steam line hi h flow C

swiic hos connected to the samt 1ireL cauu ng a group i isolation.

.'S I V closure caused the scram.

i 3.

July 15,1971 @ 1810 235.7 Shutdown to runove startup screens to July 25, 1971 @ 1350 from turbine stop and intercept val ves.

Augusi 1971

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August 7, 1971 @ 0906 8.5 Scram. While going to closed August 7, 1971 @ 1736 circulating water systun operation both circulating water pumps trippec due to low basin water level caused:

by plugged cooling tower return linc sc r een. - The resulting low condenser vacuurn caused ihe scram.

2.-

August 9, 1971 @ 1316 10.1 Scram.

While conducting calib--

to August 9, 1971 @ 2320 ration of condenser low vacuum scram switches, the sensing line was improperly opened-to atmos-phere resulting in a. scram, t

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of Down Shutdown Per iod Time. Hours Reason for Outane 1971 @ 2245 4.3 Scram.

Reactor recire. pump No.'ll 3.

August 20,21, 1971 @ 0303 to August suddenly increased in speed caus-ing an APRM high-high scram.

4.

August 26, 1971 @ 0905 134.9 Shutdown to repair flange leak on l

to Septunber 1, 1971 @ 1819 feedwater heater 12A, Extended outage to repair generator hydrogen seal leak i

Sent mbar 1971 1.

August 26, 1971 @ 0905 18.3 see August to September 1, 1971 @ 1819 (continued from August) 2.

Sept unber 5, 1971 @ 0743 8.8 Ser am.

Both reactor feedwater to Septunber 10, 1971 @ 1106 pumps tripped on low suction pressure when the condensate dunineralizer contrel valvec closed due to low air pressure.

Low water level cerammed the reactor.

Air compressor unloading i

valves were repaired.

3.

September 9, 1971 @ 2130 13.6 Shutdown to test MSIV closure to September 10, 1971 @ 1106 reset circuit.

Circuit found to operate properly.

4.

September 25, 1971 @ 0600 8.5 Shutdown while investigating RHR to September 25, 1971-@ 1430 Service Water System flow anomaly.

Vendor flow ori fice calibration data found to be in error.

1971 @ 0116 20.3 Scram.

Sudden increase in No. 11 5.

Sept unber to Septunber28,28, 1971 @ 2135 recirc punp speed caused an APRM High41igh scram.

October 1971 No Shutdowns November 1971

'l... November 12, 1971 @ 2400 456 Shutdown to replace 12 feedwater to end of ReportinE Per iod pump rotating assembly. Extended outage for maintenance of MSIV's runoval of torus baffles and modi f -

ication of relief valve downcomers.

Other work completed during this

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Duration i '

of Down Shutdown Poriod Time. Hourn Reanon for Outnoe outage included replacement of set pressure adjustment springs on the main st eam rol j ef valv(-s, i

installation of an off-cas loop l

seal isolation switch and control l

circuitry, and modification of the i main steam flow restrictors.

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Decmber 1471 1.

All month 744 See November

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.L.-~-.

IV MAINTEfM CE A " Routine Operating Report Maintenance Record" form, containing all of the information required by the Technical Specifications, has been established to facilitate reporting of maintenance work performed on systems or components designed to prevent or mitigate the consequences of nuclear acci dents.

The forms are completed for each item of maintenance on such systems except routine surveillance testing.

This section contains copies of the maintenance record forms for this report period.

1 s'

(

i i-i 1

l-i l

l l

4, 1

r

.,-,.,.m,.,,~.,.

.,n

,, _.. ~. _,.,

,.z_m.,~,._m, yy 7,.,,

.,,.. - w. _,,,,,,

fopT i y operm,.c prponi "A:01: s Ayo, y ug

(

( Requi red t oi

.y a or m 4 +,a a _. j

, 7. il s

prevent o r r'1 tic M a the ccan"<pornr-o f

>.1 < a i r accid nic) 1.

Sys tem or Component :

Reactor Protection System 2.

Date performed: __7/9/71 T iem rego rod for encriniinn:

3 Hours 3.

Natu re o f t he Bla i e. h r ar m :-

Pnotio" O r,.e,,mnry o,. -ven i i vr. O corrrc'iv-3 4

Brief summary of work neine ed: Replaced two High Reacj,or Pressure scram acessure swi t ches. _ _ Removed snubbers from sensinn lines for all four High Reacte r Pressure Swi tches.

5.

T he e f fec t, i f any, or, th.

m'.

operation of :h-i.,

h.

fDNE.

T he t r i p locic channels of the inst ruments were p_ laced in the t rigped condi t ion while maintenance was i n prop ress.

6.

T he cause o f any mal fun <.f i c fnr wh,ch, - r r "..;, - nain;( nance n re:p i red:

Probably due to plupped snubbers.

7.

The effects of any euo i malrunrticnc: Two of the four swiiches did not irip

._yri thin reavi red li mi ts.

The reactor high pressure scram protection was not defeated, however, since only one failure occurred in each of the two scram logic protection channels.

8.

Corrective and preven t i ve

a. t i or, t aker. t o p, cl u de-

-cur.ene o f..al func i i ons:

Manufacturers inspection showed the two swi tches to meet speci fications.

l The surveillance test frequency was increased for a time sufficient to deter-I-

mine if the problem was still in existence.

No further problems experienced since removal of snubbers.

i w

y

-..m.f

.-.~.

y y

d J

j nm i Nr nPrntJf i t1: In ?tira "AiNU eAy/ o mpp 1-t'

( Becp a red f o r < yu t,

iir c4.e.. :r. t -

i."i-r.3d in p reven i o r na i i r a ' <- i ho cm,9 <rm.o - oi o;.Ina,.-ci d,.n t 3 )

1.

System or Coeoneni: #11 Diesel Generator ate performo/18-19-20/7} im requi rr d for ennoini t en:

7 d:

20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

2.

D.

3.

Nature of the Uairdenance:

Rno t i rv 4 0 t e-r r "" v 0 " ve a v<

0 cd cre<

i ve @

4.

Brief summary of wod n<:rror md:

Char ted several relay operations during a a

start of the diesel.

Found that the start failure alarm was initiated by relay PFDI Timine out 1/2 second to soon.

Adjusted timing of the relay and made a functional test of the diesel.

J 4

5.

T he e f fec t, i f any. on the a ' e opo r e, ' i o n o f t h.

re;ctn.

fDNE 4

2

(.e i

6.

The cause o f any mal funci ior r e wh o h. e r e, t i 1,-

co r.h r.ance w v re tp i red

c Spee_d N nsing relay not.operatine_ soon enouc,_h.

i i

3 7.

The effects o f-any such mal h,nn t icr :

Nuisance alarm.

R.

Correct i ve and p r ever.t i ve A.-. t i o n t ahr. to pr< -lodo e n, u r r en e,. nr mi f unc t i ons :

Not applicable.

.R g.

A w

w y

--is-

,----gi

.+y-,-+yr&wp-ywn,. re wp e -,

.g

-,.gwvi,

,r%.+e+*y-a ny to,-

yy, vee v-%,wr i-

+-_2, u.,,.,

i 4

follT I NF f,prPA1 i tr nrN>ni f'A i y1i "Aari r r r ahp 3

i

(-

(Requi rod f or

.y o n oi. o m io....n t.

.t<.,

,,ad 'n provent or u.i t icai n i hn <.m e, u pon< m: of in lonr acciden!n) l.

System or Component:

All & 412 diesel ceneratorn.

i 2.

Date performed: 7/19/71 T i re ragii rod fo r e n p l <, t inn:

2 days 3.

Nature of ihe Mair lenanc.e:

Routino Erro r c c.nc y 0.

ve n. i vt 8. co r r e.4 i er> 0 4.

Brief summary o f wor k per for md: Performed factory recommended modi fications on diesel penerator blower bearines.

A s

l l

s- -

i i

5.

The effeci, i f any, on the a re oper a t i on ra f t h.

'occ nr: None, Peactor was shutdown.

(

4 J

6.

T he cause o f any mal fun..i i n-for wh t c h. o r r r - +, -. >;in.<nanc< wne reg n i red:

4 7.

The ef fects o f any 3och mal func.t ions :

4 t

6 R.

Correct ive and preve

i ve c tion iakon io p i q ud.,, ecu r t one - o f r al fur,e t i ons:

4

.I

... ~. -

FOllT I NI ('iPIRAT 1 to prPr)RT r.%I NTr B'Atrr - rfropn

(~

( Req.o rod t o r sy:,tonn or en monenis d.wigned to p reven t o r mi t ir a t < t he cn%orper con o f ret. loar ac<:i de ni s )

1.

System or Componen t:

No. #13 & #14 RHR pump suction relief valves.

2.

Date perforrred: 7/20/71 Tine requi rnd for encel. t ion:

1 Day 3.

Nature of ihe P/ainl.: nance:

Rou I i or-Erm e conc y C ' mv n i i va- @ Corrective 0 -

4 Brief summar y of wor k per fored:

I nstal_ led new relief valve springs.

Set relief valves at 150 psie.

PONE, reactor was 5.

The ef fect, i f any, on the af-opo rM i nn s t h<.

r shutdown.

F 6.

The cause o f any mal fontIior ent wh! c h < o. r -

i,a. -,,

en w1 reyn red:

l

(

7.

The ef fec ts o f any m.d mal F.,nr t ions:

i t

l l

R.

Correct ive and praven t i ve

ion t al<<to in p r ~:li.do r-..,m o f + sii ronc t i ons:

i-I

B9JEl% JFSMlli4 JWSJG. M!!iMh6% f/i'iMD (Requi.wl for 4rstou-i or caop oonts dnigned ta

(

prevent oc mitigato the conannoncea of nunlear accidents) 1 System oe Component:

Core Spray Test valve LO 1749 2.

Date performeil 7/27/71 Tie required for coop 13 tion:

2 Days 3.

Nature of the thintenance: Routine O smeegenerL; Prevantive fx] Corrective O 4.

Brief sunnry of work performo1:

Removed notor f rom valve operator.

Checked motor on the bench - appeared to be ok.

Ru n mo to r on t he ben ch - cu r r en t no rmal.

w 5.

The effect, if any, on the asf a op+.'sblon of Gie reactoe:

None, maintenance did not af fect system operabili ty.

(

6.

The cause of any m1f'nnetton for which correcti.ve ;raintenance was required:

7.

The effects of any such malfunctions:

1 8.

Corrective and proventive action t&n to precl:de rec +ccence of malfunctions:

(._

.. _.. _ _... -. -. _ _. _ - -. _. _.. _. _ _. ~. -.. ~ _.... _.. _

,i i

i 4

i fO ll i NF OPrR Al i f p Rrpor.1- '/A (!D r tIA trr nr.rnpr3 t

( Requi red t'or sys t er.c or cocoont.rd a d-n m,riod i n i

prevent nr mi tiriain ihn c.n nw ponc.on o f nu c l ea r accidents) 1.

System or Component: Of f Gas fil ter F-3A 4

I 2.

Date performed: 7/27/71__T we requi red for r.nre l td i co:

1 Dav i

3.

Nature of the flaintenance.:

P.ouisen Ernrerncv O 'Pr,-v..niiv~ O correciive x 4

Brief commary of wor k per fnt n,.d:I nstalled new filter cartridce in off pas t

j filter F-3A to_rmdace previous filier which was damaged 1 moisture during t

_oreaa testinc.

QDT E:

Fil ter F-3B has been __in service durinc p_lant operation i

to date).

l-4 l

i l

5.

T he e f f ec t, i f any. on the a fo c per at i on o f i h.

r m 4-b, BDNE, Reactor -

4 was shutdown.

l i

(-

i I

i 6.

The cause o f any mal f unciire. foe whi r h < rs t m t i w r a i n ! <-r ancr> wrc reepir.wh Leaking loop seal-fill valve on off gas line.

I I.

l l

The ef fecis of any voch mal fund icra.:

Damaged iiller.

7.

i t

~ ;

l R. - Corrective and proven.C vo a.jior. -takan 'o pre t.lude r ecurrence o f tal funct ions:

Repai red valve.

N

-j-as e

e e-g

.,9,-

,-s,-.,,

4,-.9.m

,,,cyg_.

,y, y,gy.pg,.y%m,-#,y-w.w,%i,.-,-w,,.m..r-

% 3 p

p.=-,s

t

[0UT I Nr oprRATI rg, r;rpora ffA;;JT"Qfp f;rColg (flequi red for sys tens pr c orgson<:n i r J.:ni; nod to proveni nr mitirato t he-rw iwpnne.on o f regi,,ar

sr., i den i n )

1.

System or Compon9nt:

Core Sorav Test Valve LO _1749 2,

Date perf ormed:, R/5/71 Ti e r. + ired fer coi..ploiino:

2 Hours 3.

Nature of the Vair.ienance:

Roolin~ O I ""r"on< v 0 P v< ra i ve-O cc rrecii v-E 4

Brief cunvrar y o f wei l nnr f or mod:

T ightened all looseJ, ants in the-limi t

_swl tch _driys_gstar assembly _ anci ad iosied_limii swiichs.

1 w

5.

T he e f fect. i f any. on the afo egerr.flon of ih-

r..,c ' c :

fDNE, maintenance did ned af fect system operabili ty.

~

(~

6.

The cause of any mal funct ior for which ei s + > s.

a i n h -n an n w na regiired:

I l

Faulty Installation.

l l-I 7.

The ef fects of any such mal fond ienc:

Valve'would not open.

l l

8.

Corrective and preventivn amtion labn.to;pr(.ind? r ecu rr ence o f y.n1 funct ions:

~

I.

(

/

- ~.

t l

l L

_,.. ~.

j 9

i FOllii M* GPrt?AT ! ?f: f(Pl'il A!',1iTA J'r frrnpp l

[

(Reclui red f or e.ys t r 0 5 nr utanonnot-ke :

r..id i o prevent or u lica'" i be. ci o r.m pn, t,n. l eia, arejdenic) 1.

Sys tem o r Componen t :

Drywnli Vacuum Breaker Valve 23R2__H 4

j-2.

Date performed:8/9/71 Tine rerpurnd for enemini,on:

4 Hours e

i 3.

Nature of the thinionnoco:

Pnoli m O r.

,ren. 2 o : s.> v.,.n., v, o c:e r rec., v, c.

(

l 4.

Brief summary o f wot k nor forwd: Repaired broken air -1ino to test operator 1

for Valve AD 2382H.

t t

r.i.

inr: PONE.

Reactor S.

T he e f f cci, i f any, on t he.

.a!-

opera t i on o f e b.

was shutdowa.

?

(~

t i

6.

The cause o f any mal fun = l i n: for M

<5+rn t<

".ir

.r nn ~ w v reon rod:

[

- Air line movement daring relief valve blowdown:io torus caused a 90 copper 1

ell to break.

I-f.

7.

Ti.e e ffects o f any such mal h.nat ienc: The test operator would not function, ii-f.

k l

8.

Corrective and proveniivn aD ion - t aken + o pr ~.!nd,, %u r ene or :.al fnnet ions:

i Replaced missing pipe clamps to restrain air li!

avement.

i i

~

G l:

l I

.-..m.,

. - - ~, -

e,~.,

--....-,.,,,.,,.,,.~,_.,-c%m........,4.,.-,-%,.

J

,m w -, ~,,

fOlT I NF ODFRAT I TT. f<fPORT f/AI N1 f f'AfTJ i:IT.Ol@

f'

( Requ i red t o r s ys l en.a o r coconnentr deniened bi proveni or mi tipat e t he co%orpenrns of re;c l ea r accidenic) 1.

System or Component: Steamline Drain Isolation Valve NO 2374 2.

Date performed: 8/9/71 T iw recpi red for conpleiino:

3 Hours 3.

Nature or ihe */ air.lenance:

Rnuiine lentonory 0 P ev'rtiv-O correctiv-G I

4 Brief summar y of wor k per rnr med: Valve f ailed to open.

Found relay 421F in MCC 31306 was not closine fully.

Adjusted airgap. operat t on satisfactorv.

1

a > oporaiion of the, r'uw ! n '

tDNE - Reacto r 5.

T he e f feet, i f any, on the r

was shutdown.

i 6.

T he cause o f any mal func.i i ca - for wh i r.h en r r a. ve

.ii rii erance ws re cp i red:

improper relay adjustment.

d 7.

The ef fects of any tsuch aal f'onclinns:

Prevented valve from reqpening.

8.

Correct i ve and prevent i ve t ion Ialnn to pee; hob eerur on,e nf malfunc.tions:

Not applicable.

4 R0f f.E O?WI A. '.REPORI W.N.T.6'%. W..s.P N.O.R.D.

l 4

t s

si (Repini for Jystm or coop iicata de11gned ta prwent oc mitigate the coonmonces of naclear accidents) r R

t Cl l

l ti Vl M0 2398

.....e.a.c..o.r..e.a.n.uP...s.o..a...o.n...a..v.e........................

1.

Syston oc Couponent:

2.

D1te 7erformed : _8.-9_-71..

Tim : e1uired Sr eoo;d 9 Ann s 2.h.r.....

4 3.

Natuae of the Msintoonnce: Roatino O energeonyi Prerentive

' corrective x 4.

Brief mnney of vark wTor.ul:

....i r.e..c.h. e.c. k. e. d., t. h. e.. c. l o. s. i n. E. 9o. n. i..r. 9 }. 9w. l' t. 9. t....

W h

4

.f o un.d..t.h.a.t..c.o.n.t.r.o. l..w. i. r, e..#1. 5..w.a. s.. i. n. e e. r. j e. d.. s. o.. f. a. r.. )' n. t o.. t. h. e.. t e. r. m. i n.

k v

i.

l M.C.C. 3.1.3.0.9..t.h.a.t.t.h.e..w. i.r.e_.w.a. s.. s.e.c.u. r.e. d..b. y. t h.e..w. i. r. e.. l' n. s. u. lat. l' o. n. t.

. -. s.. s. e.c u. r. e. d.. ' n.. t. h. e.. t e. r. m. l' n.a. l. b. l.o. c. k..

i l

La.n_de.d..w..i r.e. s.o..t.h.a.t..t.h.e..c.oRRe. r 5.

Tne sfrects ir an.<s on t'w nfe o.n.4 stun or the reactoc: _... N. o. n. e. : _r e. a. 9. o. r..

f

-.a. s..s.h.u.t.d.o.w.n..,.

w 6.

Tnn caus 3 of any ulrunctbn for which corrective nintennace vuc required:

1 Faulty installation.

7.

The effects of any such mnifunctions:

i

.T..h. e..va. l.v. e.. f.a. i. led.. t. o.. c.,l o. s. e.. o. n.. a. n.. i. s. o. l a. t..i o.,n. s. i. E n. a. l..... _.....

4 8.

Coraective.ud peeraativc actbn babo to,oco.n vlo racceence e malrunctlann:

.tht.oppl iq@ k.....

(-

i

=

e

.g y e e p g

,ga, a e g g

,,,,,.ag 4

,g

,e

.4

.g

.g r

3

,-..,m

(

Ror r ar2.o.n. o rr.a.ct.n_P.P.O.RJ(.W_..N.T.e.gp4 ry. qo.gg 1

(Requini.Sc Jy staa i or coup "1.wt3 designed t) j prriant oc mitigate the coongoness of ndalear accidents) 1.

Systoa oc Coup. mot:...F3.P.S. Ci rcu.i t.Stecker. 56-CM b..

2.

Dite performed:.9dQML, Tie req tired Sr coa.MMoo:

3.

Nstilas of t,ho h iitentace: Routino C 9ne gency(X Prer30tivs Correct!vi i

4.

E-lef swmry of vark pm formo1:

, yj r 9, had, hpr ped, p f f, from, the, J oad, p,i,de,,,,,,.,,

_tm i ce L 9 f. i be. c i rc u i t. br eak9r,,, M, 9 f f, phar t pd, wi r e;. installed, pew lpg. pn the, l

wice;.cleeced.termicel. stud.9f.tb9. AQS,,,Qbepbed,,sygg, fpr. Erpund,

4 o

I

.........,.................................. ~..

5.

Tno afreet, ir any,,o t w nf 3 op. wet,n or two rume:

i s

Aloc e.. t be. r eact o r. m ovbo r i t i gal. and au. a f fec t ed. sy.st m s..w.e,r,e,,i n,,t he,,t,r,i pp,e,d,,.,

.cooditions........................,..............

6.

Tnn enas 3 of any.nicanettan for which correauve nin',emtace vue required:

T.br. wi r e. conn.ec<i. pr..at.. t he.. AC. B..,Te.rm..i n. a..l. w. a.s. n. o.t. t.,i g.ht..e.n.e.d..e.n.o. ugh.. '.t.o..s.o.l.i.d.l y..s.e.c.ur.e

,itm. wi r e,.

1.0c.M bes,t j rig 9999r ied, f.e.sp1i i ng,,i p,,eyentpa,1,, bur,n,i ng, o f, _t he,,wi,r e,.,,,,,

J

_........ ~.,....._......._............~.......

7.

The erfects or any such m11 function:1:

Lpsa p.f. PcFpr...t.o..th.e...A..ch1a.nP.e.l..o.f..the RPS r esul t ed - i n a hal f scram.

Loss of ppppT..tp..i P) A iop..r el,ay,s,. e,s,u,1,1,e.d,,i n, a,ut om,at,ic,,i,sola,t ion of, re,act or, bui l,d,i,ng,,

F t

4 J9n.t.i.la.t.ipp. En.d,1h.er.e.f.or e3.,a,1,1, af f,c,c,t,e,d, sy,s,1, ems,, wen,1,,1o,,1h,e.,",saf,e,",,f,ai,1 u.r,e,,mo,d,e.,

h 8.

Cor"ecMye and p.m.uative a Man tha t3 preal ide r arecem af.ulrunct.nos:

JJs.ed a. barruly comp.r.eAs.i.on.l.ug,on,t.h.e.,w,i,r,e.,an,d,,1,ight,en,ed,,t,he,,st u.d. n,u,1 s.,o.n,,t.he,,,,,

.ACB..t.emi rA1,................................. -............................

f

?

I-f01IT I NF-Oprr:A1 i fJ; r<rP0f;T !!AI N1( NATJir f:( r.Ol<D

( Requ i red f o r s y:.. ' wei o r < oconnen t : J ' a m.ed i$

provent or miligato ibe com,orpenene el nuc t.ia r acci den t e )

1.

System or Component:

RHR sys t em -

2.

Date performed:

A/20/71 Tine requi rod for com. Int ion:

2 Hours 3.

Nature of the flaininnance:

Pnu l i re Enervenry [] - P c.ve r:l i va

' Correcii vd 8 4

Brief sunnary of wnil enr for wd: Adjusted position indicating switches on valves 60 2010 and LO 2008.

s i

None, Maintenance l

5.

'ihe effect, i f any. nn ths ' a re Dr+ r a t i on rIf 4ho r, ar ' g,

did not affect system operability.

i

(

i l

6.

The cause o f any nal funolior

'or which.4vro, t iu

,i <. ;i.nanec w, re gii r ed:

Faulty insiallation.

P

7.. The ef fecis o f any such malf on..lione:

Imgoper valve posi tion indication.

s A.

Corrective and p reven t ivy.ti ion t akwn - to p r od ods recer<enen of "al funct ions:

No't applicable.

l r

I h

I k.

i

, -,...,,,. ~,. -,,,.,,. +.., -.,,,, - - - -..

1,

4 1

2

{0U18 Nr OprRA11 Po f:rpori "A! N1rNATr Is tymn

{

(Requi red f or sys t ors or componon t d<nienod in provent o r m i qi,,i r-t he rm. orpon. or o f nu.- ! oar ac ci don i c )

i l

1.

System or Compononi: RHR A loon, 2.

Date performnd: 8/23/71 Tinn rnqui red for conploiinn:

1 dav 3.

Nature of ihe Maininnanc.e: Routine f enrm nry [] P' cvoni i vn @ Corret i i ve O--

4 Brief cummar y o f wot t per t or md:

Installed new springq_in relief valves i

j RV-1990 and RV-1992.

Sei.r_cl i e f volygs, ai._11Q..pni.n,_

i l

i 4

5.

T he ef fec t, if any. or, the afo opera $ inn o f she

r..u t r :llone, t he co re 4

sprays, containment cooline, doiset penerators and remainine LPCI components 2

l were operable during the maintenance period.

6, T he cause o f any malinnd ioo for w h i r.h. r r r e, ' + m<.. co n i..r:r c r-w et rerpired:

i 7.

T he e f fect s o f any s u c h mal tb nr. l i er.n :

1 l

t 8.

Correct i ve and p reven t i ve a t.or. taken to pt:.iodo i currenc.- of m1fonctions:

1 4

4 1

t

.t

.n

,,y e,,

,.w-y n.a,

..w.,.

7

,--v, y

,.--yg,.

+c n,,. ~

E0 r.f.N.E. 0.?.c.t.l'.'I.N.C.R.FR.M...W.N.T.E.'{WF-.89'.G. t.D.

s t

si.

(Requi.*wl he antaa4 or conti naats do11 nerl ta 6

prenant oc mitigato the coonmoocco of n.tolear accidents)

)

1.

Systen oc Couponnott.

. ).PQ l $yste.St eorp.dteio pot. level. sw. 23-90............

2.

Date performel:,_S-2,J,n,

Tte -e.]ulte,1 Sr nNastbn 3.ht..

3.

Natue of the Listeqance: Routino C hoegency'. Prersativa

. Corcentive U

,, Fjew k9. lgaqip. t9, } 9ypt,3,j tqh. f rorp.........

d 4.

Brief suanry of vark priormi:

L' un.c.t. i.o.n. b.o.x..

)

i

............ +....

Nnp......

i 5.

Tne effects t r an.<> w th 3 th m. Oton of t.he reactoe:

9 i

. ~... --- -.

1

.r I

6.

Tnn caaaa oc sn.e mirunction for which corrective nirneonane vue em. ired:

1 Wr.o.n..a.t.y.p.e..o f.w..i.r.e.. i.n.s,ul.a..t.o.r) wa.s.u.s.e....H. t che. r.. e,m. p..er. a. vr e. w. t. r. e. i n. spl e n.on..is..

n l

_re.9o.i..r.e.d b.e.c.a.u.s.e..o.f..t.h.e..h.e.a.t..c.o.n.d. u,c.t e.d,.t o..t h.e. 19Y91. 4w.1' t.h.

I i

l 7.

The effects bf any such m afunctions:

. Con.d.en.s.a.t.e..d.r.a i n..v.a.l v.e,.S.V. 2.0.4. 3..w.a. s..o.P. e.n...an.d..c.o. n. d. e. n..s. a. t e. d. r. a. l' n..P. o. f. h.1' 0n.l e. v

_al.a.r.m..w.a.s.. i.n. i,t. i.at e.d..

i

-....,............................,....-.4 t

i' 8.

Cor?.'ective and pNraative aWon tsin t3 prec12de ract ceow af xG rund17nn:

.R e.w. i.r.e.d..w. i.t.h..cl.a.s.s.. i.n. s.u. l.a.t.e.d..w. i.r. e..

...-..........,.... w......

(~

=-"

=-

.e,

,,-y,.,.

.,y

..-,.p

,y

-,,e,_.,

,,y,,

30lEf35.!?QtMI4G RF#041jQtjT(hf{g$,jp}'tMD (Re.pini for a toai or coup nauts dooigned ts

(

prevant oc mitigato the cuanmences of nuclear accidents) 1 System or Corsponent:

Plant Protection System 2

Date performed: 9/1/71 Tim required for complation:

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.

Nature of the thintenance: Routine C Emerga^

_j Prevantive fX] Corrective []

4.

Brief surinry of work poeforan1:

Replaced the sixteen Main Steamline High Flow i solat ion Swi tches, (0-200 psid) wi th lower range units (0-70 psid).

This was done to provide ins t ru-monts with a more appropriate range for the existing JP vs steam flow response.

5.

The effect, if any, on t'w nfe op.wshion of the reactoc:

tDNE, Reactor was shutdown.

6.

The cause of any adfunction for which corrective asinteonnce was required:

tbt Appli cable.

7.

The effects of any such adfunctions:

Not Applicable.

8.

Corrective and provent.tve action takaa - t) proclide recircence of malfunctions:

Not Applicable.

(

3

..~. -... -_.

,-,._--c i

1

+

i f{XIT I Nr OprRAT i f,r; prp0RT '/AI NTrNA*rr r Ecopp f

(Requi red for sys t on.n or comonenin d.' signed to prevent or mitigata t he conscrpenc os o f nuclear acci donis) l.

System or Componeni: 412 Diesel Generator 2.

Date performed:9/5/71 T i rre recpi red for concle t ion:

2 Hours.

3.

Nature of the Maintenance:

Routino Enercency 0 Pr-veroive corrective 4.

Brief sunrr.ary of work per fnr *d:

Disassembled air pilot valve 7031 and cleaned.

5.

The ef fect, i f any on the afe operation <>f pho re nfor: fDNE.

Redundant starting system remained operable during maintenance.

(

6.

The cause of any mal funciior for which eo<rc

i v" n..onierance w'r re tp i red:

Piece of dirt between valve seat and disk.

l l

7.

The e f fects o f any euch mali'on t r er.c :

In time enough air pressure would build up to engage the starter pinnons and start the diesel.

1 i

R.

Correct i ve and prevent ive a lion 'aken~to p e r.i..ie " co r mn.. o

.si fonc t icr.c:

r p

FDNE 1

4 1

.i.

i I

lf) i FOUTI NF OPFRA7 i ff: PrPORT 2%i NTr NATV Pf CohD (Requi red for sys f ctra or corpor enti; dou cnod in proveni or mi t inato ine consoquonrnn o f nviloar acci dent s) 1.

System or Component: ECCS I ni tiatinn Low-Low Reactor-Water Level Swi tch I

2.

Date performed: 9/9/71 Tirte regu red for couplet ion:

1 Hour f

3.

Nature of the Vaintenance:

Routirm O Ennreency 0 P-vent ivo

. corrective O

]

4 Brief summary of work per for md:

Switch failed to operate during routine l

surveillance test and was, t he re fo re, immedi ately replaced.

5 i

4 7

1 e

4

]

5.

The e f fect, i f any. on the

--afo operctinn r;.f slw reocint:

f0NE-The l

ECCS ini tiation logic coatrolled by the switch was. maintained in the l

tripped conci tion while the instrument ~was out ' for maintenance.-

6.

T he cause o f any mal funriior for which co s M ' v'- run nit-nave v a. regii red:

r Fau l t y W rcu ry swi t ch.

4 Althoujh the switch failed to operate 7.

The effects of any euch mal ranct ien::

du r i ng the surveillance test, the remaining reactor Low-Low Level-Switches were functioning and would have ini tiated ihe ECCS: systems -

had a low-low level condition occurred.

i#~

H.

Correct i vo and p revent. vec m..t i on lakon to prre.b.da i %ure nner o f n.al fune t i ons:

Not applicable.

i.

6

., ~.

._~

t fotil t Nr OpfRAT i ti: f:rPOPT P3Al tJ1ra;Affr f$r:nnn

~

( Requ i red i o r s ys t on.c o r cotronen t : i tirrnni To proveni or na 1irato I hr-co ri',o r pe nent ef nuuloar acci doni c )

1.

Sys tem o r Componen t :

HPCI 2.

Date performed: 9/21/71 Tine reqto red for conpint ion:

1 Day 3.

Nature of the Mainionance:

Routin-O tem"rncv 0 t'-ven'iv-r<. corrociive 4

Brief summary of wor k ror fo r ned: I nstalled a new disk in HPCI exhaust rupture element PSD 2033.

5.

The e f fect, ir any, or-the af-operation r. f t h<: r oa,. t, r : PONE, Reactor was shutdown.

t 6.

T he cause o f any 9.al f uni.i i r.r for whi-h.e-ro.'iv.

ma i r. :, r ance-w n.

re rp i rnd:

7.

The ef fects o f any such nallonc t ions:

R.

Correctise and preven t i vn i aLen to p r <.c.i ode r ew r, nn.m n r sal fune t inns:

.- t ion l

i 1

I

- -.. ~.

l i

l fulTI NF OPFAAT I FD RrPORT t'Ai NTrNAmr nFcopp-p;

( f'equ i r ed fo r s ys t ens o r componente de : c nad t o p roven t o r mi t ic, air-t he e.nnsorpcnce.r. o f nuclear acci donic) i l.

System or Component:

RHR Service Water 2.

Date performed: 9/23/71 Tine requi red for cocple t ion:

18 days 3.

Nature of the f/aintenance:

Fou l i e,e O Erar""acy 0 P' < ve"4 i va O corrective a 4.

Brief summary of wor k por fne ned: Removed No. 12 RHR Service Water Pump and S or for motor rebuilding and pump inspection.

t 5.

T he e f fect, i f any, on the.afe oper at i on o f t hn r uu. ' e r :

N)NE, the remaining-three RHR service water pumps were operable.during the maintenance period.

6.

The cause o f any malfunct ion ine which corre<'t e

.r. i n i.,nanro war regsi red:

Improper loading of bottom-motor bearinc.

7.

The effects of any such mal F.inclinna:

The-bearine overheated and seized 4

with a subsequent fi re in the motor.

4 8.

Correct ive and preven t i ve w ;oo t ak4n to pre 61 ode s ecur.nne.+ nf calfunc t ions:

Installed bearine correctly and measured thrust float on the other pumps.

1 i

~

h

r

,1 0

', A,

f l:

FMITI Nr OpfRATi ff; RrPORT '/AI NirNA*ff ffCnHD

p (Requ i rod f or sys l on.n n r coqinnonis donicnod to preveni or miticato the consnqunna: n o r nue.loar acci den ts ) --

1.. Sys tem o r Corrponen t :

12 Diesel Generator 2.

Date perforrrdd:9/27/71 Tinn regu red for couplet ion:

2 Hours 3.

Nature of the Mair. int ero:

hou t i e o i;rm pfney ri vent ; v, O corrective 8 :

4. - Brief sunwnary o f wot l rer for md:

Disassembled air pilot valve 7031 and cleaned..

[

w L

5.

The ef fect, if any. on the M.

op r st : nn o f i h.

tDNE, redundant '

,rcc en,.

starting system remained operable during maintenance.

f 6.

The cause of any mal funct n. > for whi ch r or r :, i iw n e.i r h ratre wn' r e,pii rod.

A piece of dirt between the valve seat and the disk.

7.

The e f f ect s o f any ei.ch mal f un.I t er.u :

Ai r was blowing by and out the valve vent.

=

a-R.

Correct i ve and p reven' i ve-t i oc, t akon in pi e.,i nd. i.tu r -4nce, o

,ni f unc t i one :

r Filiers were cleaned and air lines were blown clean, w

'4 b{

b,-

fDt 11 NF OPTRAT 1 ff; ffrW1' Al'a rt' ate r t enig

. (' '

( Re qu i red. I o r. s yt. ! tum :n r e omponon t r - Jo icnod t o -

c provynt or mi t in in thet convupor W. oI nuclhar accidonts)--

n

1.. Sysiem or Component:.

RX cleanup ' oui 3oi valve-LO 2398

2. - Daie perforrmd: 9/28/71 1 i ne-re-trp i rr3d ' fo r conp iei i on:

3 Hours 3.

Nature of' the Maintenanco: -Rnutine f ~r o cen< y 0 " e v^ve Q 4

.Brief summary of wor t per for wd: Removed mechanical interlock and reinstalled oronerly.

5.

Tne effect, i f any, on the a re opr r a t i nn o f t hu veceint:

fD NF Reactor u

was shutdown.

.f-l-

6.

The cause of any mal funciior for which iorr% i i e ne riterance w1.

rensired:

_ Mechanical interlock assembled wrong.

7.. The ef fects of any such mal rone.f ieno:

Restricted the operation of the Valve Motor Con t ro l le r

?

8.

' Corrective and preverd ivn v..iion laken tn'precind, 'etureencs of 4,al funct ions:

e.

B91LIfJiG N.6'GU.Ti.MMI.3 Wit 4%G.JFi' M4

/

(Relutnl for Jpta:21 or co@ Hmts do11gned-t) p-prevent oc mitigato the conn rluencos of nunlear accidents) 1.

System or Coraponont:

Main steam Line-Abniter B 2

Date performed: 10/7/71 Timo required for co vlation:

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.

Nature of the lhintenance: Roution C Emorgency[j Prevsntivo f] Corrective @.

4.

Brief sinnry of work pectormnl:

Found loose wi re on nuter.

Also a screw in one of the capacitors was too long so that the capacitor was not properly mounting on -the circuit board.

I 5.

The effect, if any, on the 3sfs opest.lon of the reactoc t None, i ns trunent channel i n t ripped. condi t ion during Maintenance.

6.

The cause of any ent'unett,n for wideh corrective innintenance vaa required:

Vendor aseembly errors.

l 7,

The effects of sny such mufunctions:

Intermi ttant downscale spikes.

i 8

Corrective and pcovaative action Ldan to proal vie recceence of.2dfunctions:

All similar moni tors checked.for same condi tion and' repaired as necessary.

d

~

i l

1 follT I Nr oprDAl t f t: prpnR1 ffAIMrNAffr riennp

(

(Requi rod for systen or c ompo n.an t i desien.3d to i

provent or miliete the c.nnsorpenv4 n f,vk:Inar accidents) 1.

System or Componeni:

IPIS-2-ll8A Main Steamline Hioh flow Isolation Switch 2.

Date performed:10/13/71 T irm requi red for cocplot ion:

1 Hour 3.

Nature of tho !!ain h:nnnm:

Pou t i rie O r,.e,orney a n..s

.,,,4, r O corr-ciiv 4

Brief summary of wor k r.er l o r md:

Readjusted aciu.aiino rer.han i sm.

1 5.

T he ef fect, if any. on the a.

nporM inn of, h. - re,cio :_f]lL The assngiated f

s inst rument t rip loric was placed in the t rippesi condiiion while maintenance was i" P' P'*S**

(

6.

T he cause o f any ".:il f u n 4in L.*

wh; 1

,ver~t:

n i n h n.w n wa-rog o rod:

vr.

Improper factory ad.justment.

7.

The e f fects o f any < i. -- h r.a l i;, n t m r e :

Would not allow t he swi t ch to t ri p at the desi red trip set tine repeatedly.

R.

Corrective and preven'is.

cn !.A n n,<

n,J,, ; _c,,. n c, af alfundiions:

Not applicable.

N h ed.e

(

e F

89)E l % SP.PcG U.Tl) W. W.3 R!iT,fM M M 2 G MQ (Relat?ied for afstoni or coop unuts do11gned ta

- {~ 3-provent or mitigato the connnuoncos of nuclear accidents) 1 System or component: Off Gas Lbnitor # 1 & 2

- 2.

Date performed: 10/14/71 Tim required for cooplation:

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.

Nature of the thintenance: Routino C Dnorgency[j Prevantive C - Corrective @

4.

Brief ourusry of work pufor. uni Repai red error in capaci to mounting.

5.

The offect, if any, on the are op.wstion of the reactor:

tDNE, I ns t rument channel in t ri pped condi tion during maintenance.

{s 6.

The endas of any an1runction for which corre7cive maintoonnce was required:

Vender assembly error.

7.

The effects of any such m d functionst-intermittent downscale spikes.

1 t

8.

Correctivo and provsative action Lskan to pr*oalado recurcence of :nalfunctions:.

l.

Not applicable.

1 i

b V

--O s,-

~

$$$4.?b'$b.Y.EYY $$.Yb$S4 $ h Y

t (Ro pti?9d for afstaa4 or caapi nats doligned to prevent oc mitigato the conn rponcos of nunimar accidente) 1 System or Conponent:

Main Steam Line Abnitor A, C, & D 2

Date performo:1: 10/14/71 Tim require,1 f ar coa,detton:

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 3.

Nature of the lhintenance: Routino C EmorgencyLj Prev 3ntive O Corrective @

4.

Brief su:mry of vark parformoi:

Corrected error in trountinc capaci tors on ci rcui t board.

Mounting error caused poor contact to capaci tor terminals.

5.

Tiie effect, ir any, on t'w nfe opaestion of the reactoci t r i pped condi t ior, du ring Maintenance.

fD NE, Instrument channel in 6.

The ca.tae of sny mlrunctlan for which corrective mintonnnce was required:

Vendor assembly error.

7.

Tho effects of any such as1 functions:

i ntermi t tent downscale spikes.

8 Corrective an,i proveative actlan takan to peoal1<10 reaacconce of malfunctions:

Not Applicable.

(;-

9 le 1

_]

[p n i ?L OprnATgpray1 "tg ia Wrr fro g

( ;

( Re qu i r mi f o r s y>.. ! r.rA or c o gio r iv. t > d -;ic,,,pj

=g prOVeni or miiir.at, ihn un i,oryinru em,1f.on l+,ar ar.ci de ni <s )

CV 2391 B HPCI Condensate Discharge to CRW 1.

System or Component:

2.

Dato pe r fornnd: 10/20/71 7 ;,,,, r. qu i r< d f o r c,.;4 a.. i i o,,.

2 Hours.

3.

Naturo of the Ya i r i.: nan: n:

h," ' "' O o > > r' v 0 >

v-" i. v, o corrective g 4

Br ief tomar y o f w,o i p~ io,m.d:

Roplaced Solenoid Valvo S.

1he effact, if any. nn H i..

,r.

< :,. r d i n,. o: - h.

to, grg

(

6.

T he cause o f any ul:1.n.iin fnr 3h.

h

, rg.,..,,,, _

,.mp i r d-Faul ty Solenoi d Valve 7.

The e f fec ts o f any coc h mal ron-t vn;: CV 2394B rernained open during HPCI operation. This had no ef fect on HPCI operation since the redundant valvo, CV 2394A, was operating properly.

R.

Corrective and pre "r.tiv..

t u.i, tal n to p,< % b

,,,u.<>.n.e or ilfunctions-Not Appli cable.

e" w

_ _ _ ~ _.. _ _ _ _ _ _ _. _ _ _ _ _.. _ __

1 l

fun i T Wrn,V: i m krrw.T A i qqge i i mpp.

" ( Requ i red ' i o r sys !.ans or cocoon in t - J o, r n.ul a n -

q p rovent. o r. ira f ica t o. t he consanmr.pm ur reustnar.vci doni s t l.: System or Componeni:

RCIC System Steam isolation Valve 60 2076 2.

Date per fortnod:10/21/71 T iw requi red for royilotion:_

5 Hours 3.'

Naturo of the Uair. lor,anen:

Rooi i n+ 0

'<m < "-"ev 0 "* < v-ni i ve O correctivo D i 4

Br i e f sunvnar y o f wo r t nor l o r mi:

Cleaned and lubricated valve, adjusted packing arid reduced closi ne torque swi t ch set t ing.

t ope r a t i on 0 f i b., t.,u t o r - - W NE.

T ho. HPCI 5.

T he ef fect, i f any.. on the ae r

System was operable during the -time that the RCIC system was isolated.

6.

The cause o f any mal f urwi t on f o r - w h i c h < r < r m ' +

,4.- mu n hin ince wn! regdrnd:

Closing Torque setting too high.

7.

The ef fecic o f any such _ mal fundiens:

Valve would not reopen af ter having -

been closed while hot and then allowed to cool.

9 8.

Co r rect i ve and p reven t i ve a t i on taken to piteb.ds e nan e nne-o f El func t i ons:

Tests : conducted on' valvo following maintenance veri fied' proper operation.

l 1

"T-.

4

...~.a_,-.L,.

-.,L..,

,t"

..k

[001 i f 5" GPER Al I fJ: RrmH1- '?/,i Nt f NM)9 - [,r rf)R!)

- ((T.

(Requi rad ior sys tenn or eomoot.uil-dr,ignod in

~

prevent or na ligato the co w rpon<o or nu.b ar accidents)-

LOV 2071-(HPCI Test Valve) 1.

System or _ Component:

2.

Date performed: 11/2/71 - T in,, requi red for conpie t

_2 Days

_ ion:

3.

Nature of the Mainte: nance:

Rnolino I.:neu r.oney 0 r'< vent i ve O cor rec t i ve

4 Brief cuninary of wnil. per forned:

Replaced stem anti-rotation stop and cleaned _up stem threads.

c

_HPCI 5.

,T he e f fect, i f any on the are operat ion

,,f

+1v-re,,c l e. :

fDNE system remained operable during maintenance work.

6.

The cause of any mal funct ior fo r which a rtnJ

!"<- ' o i rii enar.co w r - re.p i red:

o Overtravel in the closed di rection.

I

7.. The effects o f any such mal func t ier.s:

Damage to stem and stem nut threads.

R.

Corrective and prevent ivo au. innt ; aken t o p r ul6d > r ecu r

en,> of 6al func t ions:

Reset torque swi tches and limi t, swi tches, b

..,_so-

. ~. s... _... #

= FELIMG J!%4MI.11 JEQRI 31.416%$!4Jit'44Q (Requit isd for 3/staa4 or cogi m9 s do11gned t) t f -.

prevent oc mitigato the conn quonces of nuclear accidents) 1 System or Conponent: Main Sieam Line Moni for "A"

2 Date performods 11/3/71 Timo required far coop 1.stion: 1 1/2 hours 3.

Nature of the thintennee Routino O Dnorgenay'ij Provantive O Corrective @

4.

Drief surmry of work po: for.nn 1:

Replaced capaci tors C3, C4 & C5, 5.

The effect, ir any, on th nfe op.u clon of t.he reactner f0PE, Insirumont channe1 in tripped condiiien during Mainienance.

-l 6.

The cause of any ulf' unction for which corrective minteanace van required:

Faul ty capaci tors.

7, The effects or sny such mufunctions:

Intermiitent downscale spikes.

8.

Correctivo and pcovsativo actlan takan ta prualide recarcence of malrunctions:

Not_ applicable.

4 4

}

IntisR%nMiA8m1AL8tewlOMMM f' -

(Re.lut?wl for Jystoad or coop onuts do11gned.to prevent oc mitigato the conn moncos of naclear accidents) 1.

System'or conponont:

P1' ant Protection System 2

Date performeils 11/13/71 Tima requtred for complation:

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.

Nature of the thintensnes RoutinnO anergennyQ rreventive r] corceettre m 4

4.

Drief stunty of work par foran1:

Replaced the sixteen Main Steam Line High flow I sol at ion Swi tches (0-70 PSI D.

ranCe) wi th the originally installed swi tches (0-200 PSID range).

T he dead-i band measured during a routino surveillance test was excessive, i

5.

The effect, _ if any, on the are opeation of the reantoc None, Reactor was shu tdown, f

6.

The ca2so of any rannmetton for which corrective mintenance was required:

The source of the problem was later revealed to be jewel bearing contamination.

7.

Tho effects of uny such mdfunctions:

The jewel-bearing contamination caused excessivo deadband in; the swi tch setting..

8, Corrective and provantive achian takan to prealvio recacconce of malfunctions:

Replaced the' 16 switches and_ ini tiated a program to inspect all Barton instruments used on cri tical systems.

t

- ~...,. -.,,.

i ~.

I

.t-I FOUT I NC OPf RM i ff RFPORT '!Al NTr NAffr nFm!Q

-. (-f's (Recpi rad t or. nyn ir pn or componcnt r d e n, nod in

. p revent ' o r mi i ipaln iho c.onancpe:rio:<. o f :nuc t oar acci doni s )-

1.

System or Component:

12 Diesel cenerator.

^

2.

Date perfortred:11/15/71 Tine requi red for corpin t ion:

3 Hours 3.

Nature of the f.hiniennoc,o:. Rout in" O t" roonev 0 P v int i v-B correc.t ive: O 4.

Brief summary of wnt L per for wd:

Peplaced top left air starting molor so the inservice mqtor could be disasc9mbled and inspected for2ene_ral

!;9ndi t ion.

5.

T he e f fec t, i f any, on the

,3 f - eq# r a t ion o f t he roncin,:

None, Plant was Shutdown.

6.

The cause o f any mal funciin-fn-whi ch. " re

+>s- ":n n l o e o w n,--

- re rp i r o.d:

7.

The effects of any toch mal _tbnr.t ierc:

R.'

Correc t i ve and preven t i vo r.. tion taken to ptoe hde ' + cu r ren& of "al fonelions:

E FOItil Nr oprRAT I tf: Ar(WT "A niirt'ATr pre)g ;

- f -l

-- ( Requ i red f or n yt t er:n o r omptnentr~d m on+1-t.n provent_or tai i t r.ii n. l bri coisrpenwr. is t _nofelbar accidents)-

Main steam isolation valves.

1. - Sys tem or Componeni:

-t 2.

Date performed: ll/15/71 Tine required for ce6 pin t ion:

2 days-

' corenncy

_ K n v.;o l i vo rr.orrectiv6 Q 3.

Nature of the Wiininnance:

Pnotsii" 4..

Brief summary of woi k perinenr+d:

Repaired all leaks in fSt V daspo,i piping.

- N ^

5.

The ef fect, i f any. or: ths-a'-

oper.dtr=n af ihe r e. u i n.' :

PONE, Reactor wa6.

shu t down.

(

6.

The cause o f any mal fon. i ic-for whi-h--orrn,f i.u - *asin h.ncinen w n-rerpired:

Poorly installed piping.

- -7.. T he e f f ect s o f any s uc,h mal Non. i i erd : Leakage of -dashpot fluid causing -

decrease in valve' closure time.

- 8. : Correcti ve and preven N ve -;m;i ;on Iakkn-in pree.Indi i ecur renc" o f r.a1 funct ions:

Remade all ! defective joints with teflon tape sealant.

etN 4

y---

,i4ei e

Yae+w as s+u

r T-v't w

1v'yir yy ir*

_._... ~. m

+

4 g.

b n

.Itx41i y ! c ep A1 :rn -n w c1 'i: 9 5:r 4 e: i ot.n t

( fvt ga t ri nj t a r

.,v-!<vn or. ww.ce it-f-

,:-8 preveni or.*uiif.o+

i f m on i 9 4.;n.

f I. m. l om y;e,! (1-m r. )

a 1.

System' or Componnn t :

"D" Main Steam Safety - Relief Valve 2.

Date perforrmd: ll/16/711ico regirm; rn, cernhst9,,.:

4 Hours 3.

Natu ro o f ihe t'a ; J ener.o.:

i-; >o t i no O ' > o ' ' ~ < -< 0 v< " ' f v<- O cor r"< t iv = D 4

Dr i e f commar y n f woi 1 r.cr i ru ~<l:

Disassernbled valve, top _wo;ks and -

'i solenoid for ins 1>ection.

1 l

n-1 5.

T he e f f ec t, if any fDff,' Reactor

, or the a'

o p rM >r.-n of : h" < -

h.

was shutdown.

(

1 E

6.

T he cause o f any malionci t r.-

for whir,b n ar '=

' ii n ha.nn e w n: -casired:

r 7.

The effects of any wh mat rone t ir.n::

R.

Corrective and preventive a.t ion, lahn to pi rindo innue.rbo m nr.al formi s ons:

t

.m.,

m...

_._,...,-,.-.,-.,,......,w-

+,,,.. -,.

-.-~.e...

,. ~.. -,. - - - - - - - - - - - - +, - - - - -. - - -

FOif11 Nr oprnA1 to prP:)RT MAINTO;Affr Prf!')RD

~

(Requi red _ for _ syn tons or comormn t e J m ened in prevent or mi ticain ihn ranunqunnom o f nuclear - acci donic) 1.

System er Conponent: PS t V 2-80-A -

2.

Date perforrned:ll/16/71 Tine requ i red f,r co<:ple t ion:

2 Hours 3.

Nature of the Main t onarn c:

Poutirve O L1 eri oncy 0 " eve"t i ve 0 - corre< t ive E :

4.

Brief summar y o f woi t pe r for ned:

Replaced main operat ine_ spool valve.

r 5.

T he e f feci, if any. on the.af o opor at ion o f ths rmis. t o, :_ _ PO NE,

reactor was shutdown.

-{,

6. -- The cause of any mal funciint for which corrm i t e v a i n t er.wv o wan r erpi red:

Soool valve stiekino.

7.

The effects of any such mat ronct ione:

Slow valve clesgre.

8.

Correcti ve and prevent ivo act ico t akhn t o p recle.de r ecur < oner or mal func t i ons:

- All air = lines and ai r accumulators were blown clean.

-h 1

~

N

-[01T i Nr OPrfW ! ff, nrpor1 rui:jirWre rFrN<D

./~4

- (fWqui rnd f or sys_ ens or < erworien M _ doc i criod. ;o m-

- proven t or mi t icai<, the emusrper. cts o f nucleiar accideninP C V 2-M 1.

Sys tem or Conponent:

2.

Date perforrmd:ll/22/71 T ics' requi red f or tonplo t ion:

10 days 3,

Nature of the Maint<.nnnce:

Rou t i n+ 0 t"ortmo < O Pr 'ven t i ve - correc t i ve; @;

4 Brief r.unnary of wor t re forwd:

Disassembled-- valvo and rebuilt poppet

~

a cuide and Iapped main poppei and pi)oi ves)ve.

2 2

5.

T he e f fect, if any on the.afe operation o' iht - r o;,c t n e :

PDNE, reactor was shutdown.

6.

The cause o f any mal iuoci i t.n for wh. c h.w r nc ' <

n.o e nie nno n wa: re rpi red:

Valve body deformation and worn main poppet maide.

- 7. - The e f f eets o f any toch mal Nor.Iiend: Excesn_y_al ve - Lea.Ange.

v r1 Correctivo and pre nntive ;,.aion iaLan to pr.- Lh.IP i ncu r":n> o f cal funct ions:

^

not-appli cable.

w

_ m

.,- -,i-,.

r

..,r-

.,,,,u,.w.-wwe,,

owwE

,,~ w--rru m--

., - -. W.---.,-- E-E w- - - = -~~ ~ ----

--d-

- -e--U~~--'I'

folli t Nr OpraA71 on Rrpor<T UA1 MirNAhrF P! r()R!)

[')_

( Requ i red - fo r s ys t es o r cc.reponon i r dos i er,ed i n provent or mi t igat<i lhe cemiotpont.ns of nuclear accidento) u 1.

System or_ Component:

PS 2-3-52B ECCS Valve Opening Permissive Pressure Switch-

2. - Date performed:11/24/71 T iire requi red for cornplolion:

2 Hours =

3.

Nature of the Vaintenance:

Rnotine Erm; encv O r+ niiva 'O corrective E 4

Brief summary of work r,cr fnrmd: A seipoint lockine device was installed to keen iho t rip settinc f rom dri f tinn.

5.

T he e f feci, i f any, nn the ale operat ion of h+ i. m.c t o r : tD NE.

The i

associated loric channel was mainiained in the t ripped condi t ion while_ the _

maintenance was in orogess.

6.

The cause o f any mal fow.iios for which rorrm i tvo minionanen wn 'rerpi red:

The instrument was not originally purchased with a selpoint locking device.

I t is believed that the instrunent settino dri f ted as e result.

7.

The effects o f any wh mal Nnnt tons: The i_n,s t rument was found to trip below the desired seiiinn.

9.

Correctivo anc preventive miion faken to pe ne. hide -i +:cu r r ents o f r,al funci s ons:

A program was initiated to install setpoint locking devices on all simi1ar insiruments.

4

' j q

---.i,

-%.r,-

9

.em...v.---

--ey--

-w-h---

~w,

,---y--

<,-t-vt-w

,e r=# w-vete, ww e. e e m swm e ren-ei=9s++ws--

4.--m-.

e----

6'*%

- f(Xili Nr OPTPAll Pf; Riponf '9AI tfirNAtor PFcar,D ip (Roqui red f or c,yuons or corrononin doc trned to

~

prevent or m)iirain the corsgrponces of <suclear acciden to) _-

1.

System or 'Corponeni: All inboard and outboard AGIV.-

2.

Dato performod:11/30/71 T ine requi red for comp t nt ion:

14' days-3.

Nature of the thintenance:

Rnnt ino O trarency O_ P nvent i vrJ O corrective o 4

Brief summary of woe k perforned:

Inspected and dye penetrant checked al1 fSIV dashpoi qushion sparb.

d 5.

T he e f fec t, if any, on the. -- n '. ope r a t i r n o f 11.o r n i n

PONE, reactor was shutdown.

(~

~

6.

T he cause o f' any nol t on.d i c.:

for' whi ch v r n - i i,< n a i n ; <;na!'er w n regsired:-

'7.

The ef fects of any vbch manJnti tc rs:

t-8.

Correct rve and preven t i ve a.t[on l aknn, to prmlode mcu r nom of cal' tions:

k.

... -.... ~.

folill Nr oprRA1 t ti, nrPoPT 'M3]rMrgyrarg -

(Fequi red lor syt t'ont or 'ot @ nont'.de t mMJ in

- p roven t o r L mi t icat e 't hs' rorr;.+rponcer 6f hu.;lohr accidontsI

l. L System or Component:

No. 11 Diesel generator 2.

Date perfortred;12/7/71 7 iim rgn red - fo r ~*.no p ir. ' i nn.

6 Ilours_

3.

Nature of iho f/ainIc,nnec:

Pr,o t i n, O % '"<n v 0 t w ven'ive (Y)-correciiee O !

4.

Brief summary of wo F per fne ned: Disassembled all tubinc_ and valves -in the starting system.

Cleaned and-lubricated all cortponents. Replaced one sect i o n o f darrace. d~. tubi ng*.

4 5.

The ef feci if any. or t h*.

a 4 our i M i o n o f ; h.

r<

' t r.

fDfE reactor 3

3 l.

was shuidown,

(.

(

~

6.

T he cause o f any malium i t o for which.

i r,1( r a,vn w n: re qui rnd:

o 7..

the e f f ec ts o f any mch mal e,m i i err.:

eenupseene

~

1 1

R.'

Corrective and-prevent ;v4 a. Lion iaken-in p rIody > *icu r, once of~ wtfuret;ons:

s l

t.

t, e

Kol t Nr OpfrtAll y; prPord nAi:gpigr<-

gi-

[-'

(Roqui rnd for tyMoc.s or omoorsin M Migned in '

provent-ov' mitinat6-tha <ntu gienu? ni nn.:lonr scoi den ttd ISiV 2-868 1.

Sysiern or Cornponent:

2.

Date perfortned:12/I2/71 Tfine r.aqu red for coupl<,t ina:

4 days 3.

Naturo of ihe P!ain!.:nnnc4:

f:no t ine O r."n'"< n v O iwve n ' i w O corrective- 0 i

4 Orief somrnar y of wor L per fnt v.d:

Disassenibled valve and lapped main poppet -

and pilot valve.

4 S.

T he ef fect, i f any. o n t h<.

af operatinn of th" r,i-,d er:_JEE,.. reado r w as shutdown.

6.

T he cause o f any mal f uni.i ur f =_ r which io t"

mo i. iermv c war, co rp i.r od:

+

Scratches on pilot valve seat.

7.

The e f fects o f any toch rnal r. nr.f ions: Excessive valve:loakape.

R.

Correct i ve and proven t i vo aE4 ict, t aken to pr n -lud= ' n.:u rrenm of nal func tions:

BM Applicable.

M amw-

l r

__________________._____.____.______._...m.______

_ = _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _

..~. -~.

. ~..

.~

r R)UTI Nr oprRAll TD f!FPf)f.T YAI Tjif NAh:F f$rntM-

~

ar co mpo r.un i '- d<4 : gren! !$-

( Re cp i rod t o r F,yr, ' r:rt.t prevenl~nr mi l i c.ai e t he, c.onsorpmn..a o r nue.Inar acci dnn t n ) =

1.

System or Componeni: Main steam safety-relieLvalves A, B, C,iD 2.

Dato performed:.12/13/71T im rego rod for ennplet ion:

2 ' ciays 3.

Nature of the flainionanec: finu t i r e O oorrency 0 ".veniive E corrective l O L 4.

Brief sonnar y of woi k re ine wd: Changed out main pressure set springs and inspected valve. top works.

5.

T he e f fect, if any, on t he:.afe opera t ion of t her t w ins:

fDNE. reactor was shutdown.

6.

The cause o f any mal funoi n en for whi ch c o < t ac t i e nau r, t enarer wr re gsi red:

4

z

- 7.

The effects of any such rr.al fnnt.tions:

l

- 8.

Corrective and prevent ivo stion taken.to r,rt 1i d

9 " t odurr ens of twl funct ions:.

d

l rotnINr opinM t to BrPopi e%1:pwrc r :ctmp

( Foqu i r ed f o r. 5, y*, Sn.t

[') l ra 4.~o:2,ormni n dre,i; n.sd ' ;n -

'~

prevent or int t inati - the cow qnore > oi nocinar acci den t o ) -

1. - - Sys tem or Conponent:

Main titeam safety valves A & B-2.

Date perfortred: 12/14/71T itre ' requi red for coopinijon:

1 day 3.

Nature of the Vaininnance:

Poutine O Enar"anev -

creveniivo. O correctiv+ 8 4

Brief summary or wor k perrniwd:

Chanced ou t valves.-

t

'4

. 5.

T he ef fect, i f any, no the a f ' operal i nn n f 4 he r-;ic i n r :

ff)NE. reactor was

+

shutdown.

6.

The cause o f any mal fun..t ion fnr which m -too't"<

m r.knaner wr re gii. red: -

l t is not unusual-for very slight leakage to develop under normal-service conditions.

7.

T he e f fec t s o f any s uch tr.al i' mdi 6 rm :

Very slicht leakape was; observed duri ng vessel hydro.

8.

- Corrective and preven ti-vn n. t ion.i ak m in prc 'loJ? t ecurrence of mal func t ions:-

Not Applicable.

p.

_['-

W

-s e

w.

r--

a-T w-t--

m

er

-t

.y

,g.

w

-+91

-44yyg++>evP_-y.+-g-yg-Ww-+-yN-y 9 p g' 'TN T

'T-WYW T r yevg-&-y+'-+-^y-r

-+er-

F{Mlli Nr OprRAll to ftFr.ior,1 r. tai tai r NA T' Pfranr3 Q

(Regtu red inr sys!ons %r 4.onnor nt, do;icoed in?

_ proveni o r. mi t inale t un core,mpmnr<< ur <esci,iar veid6nic)

~

1. - Sys tem or Component:

WI V 2-800:

2.

Date perforned:12/17/71 Tim re qui red for conpint inn: 18 days s

3.-

Nature o'f the Maintonnnco:

floo t i no O tro r"<:nev 0 t' e ven t i va O co r rec t i ve 1 4.

Brief.commar y of wor k per fa wd: Dissassembled valve and lapped _ main poppet ~

and oilot valve.

i 5.

The ef feci, if any. nn the a f e opo r a t i nn o f t he t n:6-M r :_ m NE, reactor was shutdown, f

6.

T he cause o f any mal funct ior for wh; r b < t-inc t u< nair,lonaner ar re gii red:

Imperfections in valvo seatinc surfaces.

. 7. ' T he e f fects o f any ru t h n,al !unc t ione :

Excess valve leakape.

R

- R.

Corrective and preventive-a.. i.. on. t aken to p r e :liIda r -cur enm o f *tal funct i o.is:

fk>t Applicable.

--e i

--J

.c....

- ~.

j ---

3 3

TotiT I Nr OPFR/0 l tI; RfMW1 '/Al NT_QA.y;r r$COR!f-

.- {}

(Borpi rnd l'or gyn lonn or e mnpo nnn t '-.d%i cond io -

preveni or milifate thn wnwtpor,. rn, o f nucinar acci donic F

-1.

Sys tem or Componen1:_ fElV 2-5 D

-4 2.

Date perfortred:. 12/27/71T ine requi red for co+rpint ion:_10 days <

3.

Nature of the Mainionance:

Rnuiino O Ernt e n"y 0 Prevc"iiv O correc'ivo 0 ;

4 Brier somr ar y of w L PF fo"" d:

Disassembled valvo and lapped main poppet and pilot valve.

- 1 S.

T he e f f ec t, if any. on ths afo ope r a : mo o f t h+

n.3c f o r :

ID NE, Reactor was shutdown.

. (J, 6.

T he cause o f' any ol fun. i i on for wh4 ch m-ro hp s a i r, '. o w ' W S requi red:

Imperfections in seatino surfaces.

7.

T he e f fect s o f any e udh rr,al Eine. l ierd :__ Execss valve leakage.

R.

. Correct i ve and p reven i i vr m. ! i nn iatan io pr.,s np

,& cur ene of Sal funct ions:

Not applicable.

'i E

-- F *

w w w M r $ww=wwe-

weer ev *ws r w esi meww me sw w+.w-m-w w em w-wW ewr e-etre +v

ww ' ww-www % grygg--w,yispyeg w,

, pp np yey a-t a-g-,w-w g v-*=*1**w

Twv e e se y ve., j 9-we* ** t'd

i i foiiT I Nr OprRAT l rn RFPOPT vat NTf NA?f:r r$cnnn c -

(Requi rod - f or syn tr nc or componnni r.~ d^m enoJ t o -

i prevent or mi t ignin ihn tonwgion</s of-ruscloar' accidentc)1

'1.

System or' Corrponent :' tEl v 2-86-D -

~

2.

Date perforned: 12/27/71Tinn requi red for conpint ion:

10 days

3. ' Nature of the Mainienance:

Rouiim 0 trarrency "r eve"i i va O corrective E 4.

Brief summary of wor k ner formd:

Disassembled valve and lapped main poppet' and pilot valve.

s.

5.

T he e f f ect, i f any, on t hs.afo operai mn.- f the r.w ine:

IO NE, Reactor was shutdown.

.(1, 6.

T he cause o f any nul fund im for wh i rl. - i o w ' s se m n ' -n m o n.v '. regn rod:

l Imperfections in sentinc surfaces.

7.

The e f fects of any d och mal fann t iem : Excess valve leakace.

R.- Corrective and pre: vent i ve viion taken to pr: ilob t & cu r enc. o f mal funct ions:

tbi anolicable.

(.

t l

I m,.....-

R

+

. a m.

4 V.

RAD 10ACTlVE. WASTE DATA A.

Liquid Waste July Aug.

Sept.

Oct.

Nov.

. Dec...

1.

Total Curies Discharged

-7.4x10-1.33x10 5.54x10-1.09x10-2.4x10 7.9x10-2.

Total Gallons Discharged 20,968 5,125 37,350 4,265 52,330 23,236:.

~

10 10 9

3.

Total Gallons Dilution 7.6x10 9.3x10 1.07x10 1.09x10 4.86x10 '

4.05x10 '

-10

-12

-10

-13

-II

-12 4.

Average uci/m).in canal 3.58x10 3.93x10

1. 37x10 2.65x10 1.3x10 5.16x10 5.

Max. Concentration

-8L

-9

-10 released ~.in 24-hrs.uci/ml 1.4x10 3.43x10 2.03x10 1.15x10 1.02x10 8.97x10

a. Time,-hrs.

1805-0004 1620-1705 2050-1017 1350-1425

!930-2300:

1600-2115-

'(duration, minutes)

( 359)

(45)

(807)

(35)

(210)

(315)

b. Date-7/20-7/21 8/12 9/1-9/2' 10/14.-

11/19 12/20 6.

Percentage of-Annual

-I

-3 i

4 2-

-3 Limit released 2.58x10 3.92x10

1. 37 x10 '

2.54x10 1.3x107 5.16x10 7.

Total Curies H Disch-1.02xid arged 9.'16x10-3 3.87x10 2.47x10 3.22x10 3.21x10

-1

-I '

u

J(

.]

y B.

Gabeous Waste -

July Aug.

Sept.

Oct.

fJov.

Dec.:

1.

Total / Curies Discharged a.-iloble. Gases Ci 1,283 16,700 21,100

.26,300 4,140 II

-3

-2

-3

-3 b.-1odine Ci 1.7x10 1.7x10 1.5x10 8.18 10 4.62x10 4,4x10

-4

c. Particulate Ci 2.3x10,4 3.63x10 5.37x10 9.72x10 3.15x10 3.32x10

2.. Percentage of Annual Limit

. a. IJoble Gases % -

' O.28 '

2.5 3.1 3.8-1.38 II

b..' I

..-Pariiculate%

0.253' 1.38 1.9 0.58 1.64 0.289 3.

Maximum'uci/sec.

.14,250 15,000

.14,250-11,500 11; released in 24"brs.-

'11,250-

a. Time.

0600-0140-0030-'

1000-0500-

1200-0600~

0140

.0030

-1000

-0500

.1200

b...Date 7/6-7/7 -

8/8-3/9 9/12-9/13-

.10/1-10/2 11/9-11/10 12/9-12/10 3

-1

~I'

.2

'4 Total Curies H

~~

8.1x10~ r Discharged 6.84x10

.li37x10 2.43x10 8.33x10~

'1.1x10 q

I

- ii s

4

N i

^

O

?

/

C.

Results of isolonic Analysis July Aug.

Sept.

Oct.

Nov.

Dec.

1.

Radioactive Liquid 7laste Isotope a.

1 31

-3

-6

-3

-6 1

Ci 7.1x10 3.09x10 4.9x10 1.34x10 2.01x10 2.23x10

-5

-6 Co Ci 1.05x10 4.2x10 2.56x10 B.74x10 3.65x10-3.10~

60

-5

-6

-5

-6 Co Ci 2.5x10 3.29x10 2.10 1.62x10 9.68x10 51 Cr Ci 1.35x10-7'.8x10 4x10 6.18x10 137 Cs Ci-1x10 2.

Gaseous Waste

a. Noble Gases l33 Xe Ci

'24 349 900 781 358 87

-Xe C i'-

106-2275 2507 2313 1124 68 Xe Ci 121 2086 1991 4333 1778 i

Xe "

Ci 93 1562 1413-1902 762 135 Xe Ci 145 3743 4570 5120.

1989 L

133 Xe Ci 4 5. -

2822:

277 2 4987-2411 9

i'

--L '

- - - - - - =...

w.

.n.---

.1I i

I1i 1jIlllJ:

ll

?

1 Q

1 1

5 d

1'111 7

0 7777-l e

c 3 6 7 3-e 0

0 0

5 2

i D

1 1

r 1 $

1 1

r 2222 3

e 1111 hS r

e tn 0

7-7-

e v

1 o

x 0

0 C

S 1

1 0

O i $ 1 rac i

c E

I 1

1 d

17-0 I-7-

7 1

77 l

t e

c 0

O 0

8 2

62 i

O 1

I 1

6 r

1 I 1 1

r 00 1

e 11 h

l S

o t

e t

7-tp i

e 0

0 0

s S

1 1

1 0

0 1 $ 5 f

fo depp 6

i 1

0 0

3 8

s h

1 7-75 g

)

1 1

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x 1

4 b.

u 5

1 5

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42-A I.

1 1 1 1

a w

68 1

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e a

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t y

0 0

h 1

l 1

1 A

7-u x

0 0

x 0

2 J

3 1

1 5

1 9

9 l

9 4

1 1 $ 1 1

l 5

9 A

7 A

)

t y

F i

i v

b i

u t

C c

i

(

A d

e e

C i

i i

i C

e e

'n p

C e

C

'C 0

i i

o p

t 4

C C

t i

1 a

l r

i i

1, 3

o u

t h

L, N 3

l 1

l 5

t V

C s

1 u

i r

s h

s s

ie c

0 k

C C

a l

s o

s r

i M

f a

s p

e i

i l

t o

s t

d r

o a

o o

a d

o r

i a

T G

D D

P C

C B.

i l

l o

B g

b c

S 1

2 3

4 D

z l

l ll1

P VI. ENVIRONMENTAL MONITORING UEma[y The Environmental Monitoring Program yielded no increaees in the levels of radiation due to plant operation during the period of June 30, 1971, through December 31, 1971.

31.E.08.Eli.C318.!2 vac continually monitored with Ociman 'or Ibndix Air Nuclear Samplero at eight locationn within a 15-mile radiuc of the plant site and at the Minnesota Department of 11ealth building in Minneapolis. /t11 air particulate samples for thic ctudy period nyeraged 0.2 pC1/m3 of Groso Beta including the l

data thken from the air sampler located on the roof of the Minnesota Health Department Building. Table,,2 nho.tc thece resulte. -

E E1E9"$1".t,a,1,Qag g,g pgg [g,J g,Q Off-site and on-site locations (Dec' Maps'

[

I and-11) during thic study period averaged 9.6 mr/h-week jeriod (See Table 7) which in similar to the data accumulated dur3ng the pre-operational period and "First Half of 1971" (Cee Table 1).

Environmental Gamma ExpostgeJi,1m ba,gec) Erposure at off-site and on-cite locations (See Maps I and II) during the study period were reported by the film badge contractor, H 3 Landauer, Jr., Cenpany as "M" for h-wpek" periods.

Thic means that lens than 10 millirema of gamma radiation van accumulated during each exposure period.

1 Prec,1,pitation or fallout was collected at the on-site nuclear air sampler-(See Map II) and at The Minnecota-Health Department Building in Minneapolis. - No' significant difference existed between the data from these two points'. (See Table' 5)

~

- ('

T

..,.y.e.

7.., 5

.,d.~m.,m-

,mv...,

,..,.-_,_y-y---

,,y.,

,'sh,'.

h,, E_.

,7,

,~,k'--,

.5,,

_,e

'yw.

Im.m.,.

w,,E E,- w... 5-wy

+,

g

_~

i i

_ (^)

Rsw Milk from four regions was sampled by NSp and an additional area by the l

Minnesota Department of Health (See Map III) within a ten mile radius of the i

plant.

The average levels of radionuelides analyzed, are similar to the pre-olerational data and the "First Half of 1971" (See Table 1)

Micciosippi, River, water campled daily and composited into weekly samples taken upstream and downctream of the plant (See Map IV) averaged 9 pC1/1 of Beta radiation for each area. This in eimilar to pre-operational and "Firot.Hsif of 1971" levels.

(See Table 1)

Mirainsippi, River,120tt_om,qt;dimgnt is compled each quarter year and analysed for radioactivity. The study periodo recultc averaged h7 ICi/gm of Croan Beta which is similar to pre-operational levele and "first Half of 1971" W

results.

(See Table 1)

(

Topsoil taken from three fields (See Map VI) growing crops (potatoes and soy-beano) and being irrigated with water taken from the Mississippi River down-stream from the plant diccharge is analysed. The resulta shev an average of h

t 56 pC1/ gram of Gross Eeta activity. This in similar to the pre-operational and "First Half of 1971" reculte, (See Table 1).

Well Water is taken from three deep wella and four shallow wella in the plant area. ThedeepandshallowwellaaveragedhpCi/ leach. This is similar to the pre-operational and "Firct Half of 1971" reaults. (See Table-1) i i

Fish taken fram the Micsissippi River at upstream and downstream-locations (See~

Map IV) averaged 7.6 and '7 3 pCi/ gram-(dried weight) of Gross Beta. Thio' data compares to fish analycco performed during _ the pre-operational and "First Half

~

-( ]

of 1971" periods (See Table 1). The fish analyses data in presented'in Table 14.

u.

-x

3 i

p3 Additional parameters besides those presented above are Airborne Radiciodine (Table 4), Water taken from five lakes (See Map V) in the area (See Table 10),

blht.33!!?E.8.1$158".! (Table 11), Lake,an_d,R1,ver,Aguati,cjege,t,ation (Table 12),

j t

I,ske and River Attached Algae (Table 13), C.l.a.m.s. (Table 15), Like and River A.33"li.?..I.".8. ggt,s (Table 16), Ve,retation from ceveral fields in the doenwind area of the plant cite (Table 17), and gricult, ural, crop analyces from the river irrigated fields (Table 18). The data presented in these tables are comparable h

to pre-operational and "Tirst 11sif of 1971" recults with no significant variation.

l

-1 Conclusion Effluent releace levels were ao low that correlation between plant emissions and these environmental parameter resulta van impossible.

(

No statistically significant incresced levels of radioactivity were found for any of the psrameters studied durl.ng '.his report period.

i a

l 0

l l=

. ~.

f 1

t O

1 1

l Table #1

SUMMARY

j The values are averager or all camples of the parameter taken that period.

f

'First Half

Decond Hair l

1968 1963 1,970.

,,,or,1971

'of 1971,,,,

~~-~(f4f76375roenBeta o.o?

o.eo 0.e0 o.30 o.20 Environmental Cantta Exp~osure

~~~~~('IE5F(6f71iweeks) 98 S.O 91 95 9.6-Fallout 2

~~~~((C1/m)GrossBeta

1. S.

20,603 12,033 18,000 13,000 Milk pCi/1) Cesium 137

~ ~ ~

21 14 15 13 16 pCi 1) Iodinel31 4

4 4

3 4

(101 1) Strontium 90 12 11 9

9

-11

(.

Mitsissippi River Water

~~~" {i41/ F5F5is FJfi 11 9

9 12 9-f River Botto'n Sediment

~-~~(iff75mT5F3Ei~ Feta 30 37 50 59 47

~'psoil To

-'((ci/gm) aross Pota 26 47 54 57-

- Well Water

~~~~{idf~/1)GrossPeta 5

3.

.7 5

4.

Fish-

~~~ (pCi/gm) Cross Beta 6.5 12.1 75 Flesh.

35 11 7 Skeleton 4.0 25.o-11 7 24.1

'16.2

Data collected during 1968,1969 and 1970 are considered pre-operational: and the '

data under Columns "First Half or_1971 and Second Hair or 1971" is operational.

O

. _ _ -.. y._ _ _ _ _ _ _. _. - _ _ _ _. -. _ _ _ _ _ _.. _ _ _ _. - -.. _ _ _ _.. _. _

.1 t,

~h I

V I

o Table 2 l

I All! PAJCICUIATE

-1971 l

bcriou I

of No. et poi Grnnn !%ta/ meter hmpling locat$ cm CM k c'iN

_ TV Mrc 1

GE:. tm

~ Onsis

- rn e e

~

Station #1 Clear lake July 4

.72 44

.60 1

Substation Aucunt 5

45 17

.27 September 4

.24 08

.12 October 4

.03 06

.03-llovember 5

.03 04

.05 Decceter 4

.09 07

.OS l

Station #2 Becker July 4

.78 43

. 58_

Substation Aucunt 5

43 17

.27

-l September 4

.20

.05

-.12 October 4

. 23

.06_

.12 November 5

.06

.04

.05 December 3

.07

.07-

.07-Station #3 Hacty Ju)y 4

.72'

.52

.60 Aucant 5

44

.16

.29 Septenber 4

.23

.06

.12 I

October 4

.11

. 06 -

.03 l'ovc nbe r 5

.06

.03

.04 December 4

. 03

.07

.03 Station #4 Plant Site July 4

59 36.

.49 Auguct 5

34

.16

.21 September 4

.20

.06

.12 October 4

.06

.03

.04' Novembei 5-

. 06 -

-.01

.03 D0 comber 4

.02

.01

.02:.;

Station #5 Otcego July 4

.64

..42

.51-

+

Auguct 5

45

.16

.27 September 3

.15

.03

.11 October 3

.08

.08=

.03 November 5

.07

.03

.05 December 4

.09

. 07-

.08~

Station #6 St. !!ichael'

. July 4

. 84__

.29 59 Au; pot 5

43'

.18

.29

-September' 4

.21'

.07t

.12 October 4

.10-

~. 07

.03)

November 5

.07

.03

.05 December 4

.03

.07

.03.

[

--s=,- = +.,yrwn.,-,-%vy.,--e...---

we.v--,%-e.

y

.5,--v, ww-v,e.

r e im.,

.,-w.,,..-

,-%.-en.~,.

-rw--*=-rwr-"-*<we

-4

-'--w.*--

-er**-e-+*

we

-<=--*-~Y

hble 2 Alli PAllTICU11.73 1971

Eh*b 11 0. of rC3 Crorn Petn/neter5 Sannlina leention Collection

!>.nvl o r,

h:a num

&.tnun livr.rce e Station #7 Orrock July 4

.61

.47

.58 August 5

39

.18

.26 September 4

.22

.05-

.11 -.

October 4

.09

.07

-.0S ' :

14ovember 5

.09

-.03

.05 December 4

.09

.07

.03 Station #8 thple lake July 4

.69 51

. 60 -

t Augunt 5

41

.18 --

.20 i

September 4

.24

.03

.14 i

October 4

.09

.07

' 03 flovember "5

.03

. 0.'s

.05'

- Decenber 4

.13

.06

.09 Department of Health July 5

.56-

.25 46

)

Building Aucunt 4

.30

.38

.24 Se);to.mber 5

.17

.07

.21 i

(

October 4

.09

-.05

.07 flovember 4

.03

. 0'4

.05 J December 4

.09

.07

.03

{

i 1

i f

O

.n...

c..,n....

,,., +.,, - ~

Im Table 3 AIR l ARTICU! ATE-MCfGULY CCHKEITES 1971 pC1/m3 Period Of N*

I 141 144 1 34 137 131 9'5.

103 106 65 95 Collection T.n mpl e n Cc Ce C r, Cn I

!iti IN ihi Zn Z r_

Jun 40

.09

(.0040

.067

.053 Jul 3P

.17 0.co ?6

.051

.030 Aug 40

.11

(. CXXis

.020

.C09 0ep 31

.04

'.0005

.016

.006 Oct 3?

.0?

i.0004

.016

.002 Nov 30

(.0008

.cl 0.0001L 0. GOB 0.010.C030 ( 0004

(.0:02.002 Dec 31 0.0006

.01

(.000? 0.Of>33 (.007.0DO9 0.000b 0.0007 (.001 i

y 4,.

,c.

Tabic 4 AIR 30:CC I'ADIOIODIiG 1971 Teriott 131 M

/

of

!!o. of n01 1 Samnline Ie>e ufen Co? h: ti e, T-,1

...f o rw.,

Station #1 Cicar Inke July 4

(.02 Substation Aucunt 5

(.01 September 4

(.01 October 4

(.01 flove-ber 5

(.02 December 4

(.01 Station #2 Becker July 4

(.02 Substation Aucunt 5

(.01 Septonber 4

(.01 October 4

(.01 lloven.her 5

(.02 December 3

(.01 Station #3 I!acty July 4

(.02 Auguct 5

(.01 f

September 4

(.01 October 4

(.01

!!over;bu r 5

(.02 December 4

(.01 Station #4 Plant Site July 4

(.02 Au mst 5

(.01 o

Septecher 4

(.01 October 4

(.01 November 5

(.01 Do ceir.ber 4

(.01 Station #5 Otsego July 4

(.02 August 5

(.01 September 3

(.01 October 3

(.02 November 5

(.01 D3cember 4

(.01 Station #6 St. Michael July 4

(.02.

August 5

(.01 Septenber 4

(.01 October 4

(.01 November 5

(.02-December 4

(.01 C.

~

P2ble 4 AIP.30G' W.DIOIOD]!M 1971 1eriod of

!!o. of r>C i iyyy/n)

--.13 e inn t 3r n v r rv' C-S w aine inrit4n -

=--

Station it? Orrock July 4

( 02 Au mis t 5

(.01 September 4

(.01 Cetober 6

(.01 f,'ovembe r 5

(.02 Decenber 4

(.01 Station #M lhple lake July 4

(.02 Au!*u r t

.r,

(,o1 September 4

(.01 October 4

(.01 llovember 5

(.01 December 4

(.01 Composite of all Stationc July 32

(.002 Auf ur;t 40

(.001

(

September 31

(.001 Oc t obe r 31

(.001 flovember 40

(.003 December 31

(.001

{s.

T, 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 c0

?'i 2 6 8 6 4 0 3 2 0 1

1 1

0 0 0 0 0 0 0 0 0 0 6

Z 0 7 9 0 1 4 0 6 4 0 3

5-0 6 3 6 1 0 7 8 2 0'

3 2

r S

9 1 2 5 0 5 7 2 9 1 5 5 E 3 1 1

3 1 1 1 1

0 0 0 0 0 AO O

0 0

2h 0 0 0 0 0 0

2 U

l';

6 C

7 6 3

9 1

3 5 1 1 2

3 1

1 sE T

0 0

0 0'

1 0

6 1

(

3 2

2 dN 0

o 7

0 ts h1 i

b 0

0 O

5 t

0' i

a l

0 0

o 2

2 h

(

1 3

I 1

5 5 0

3 1 1 3

1 1 2

1

(

2 n

O 0 0 O 5 0 4 0 0 0 0 7 6 P

7 5 E 6 5 2 0 2 6 8 3 2 1

(

2 1

(

5 T

1 U

e O 1

+,

l L 7 b

L 9

/

s a

A 1 i

C T

F 4'

51 1

e 0 0 O 0 0 0 0 0 0 0 0 0 C

0 0 O 0 0 6 0 0 0 0 2 6 4

0 8 k 6 9 4 0 7 5 7 78 4

6 3 2 6 2 6 3 5 2 1

1 1

e C

5 0

1 1

4 4

(

1 1

a 0 0 0 0 0 0 0 0 0 0 0 5 t

0 0 0 5 5 3 0 0 0 2 3 0

Be 0 7 0 2 7 7 0 0 0 5 0 8 3 9 1 7 6 1 1 2 6 5 3 2

2 3 1 1 a

B 0

0 0

5 1

4

(

2 1

l'!W n

d.

o i

o t

i f c

]

g p t v e l g p t v c roe u u e c o e u u e c o e e

l I

A S O n D J A S O N D t

i l

o C

s i

o 6n l

l hio o

l p

e 1t a

c Pa e

i cc n

t o

n n

I i

o M

M t

._.m

--__.___.__._m_.

.____..____._.-m..

I\\

Table 6 H112 P i/ liter O

Dra te of 137 131 90

&amplint Location Cellection Cn 1

Sr Region #1 - North of Plant Site Dwinger 7 2?-71 31 (4

21 9-22-71 14 (4

16 10-20-71 15 (4

21 11-17-71 11 (3

24 12-16-71 10 (4

16 L

Kirchenbauer 7-20-71 3E (3

25 B-1P,-71 6

.(4 6

9-22-71 23 (3 +

36 10-?O-71 16-(5

-22 12-16-71 13 (5

15.

Kiffecyer 11-17-71 13 (4

14 4

Goener

' 10-71 16 (4

33

_( -

Region #2 - Southeact of Flant Site Dalman

' 1"-71

?9 (6

9 Hartzler 7-?F.-71 19 (3

13 9-??-71 7

(3 10 10-PO-71 10

(?

3 1P-16-71 16 3

9_

Schremer 11-17-71 12 (3

3 Subra 3-10-71 1?

(?

5 Vandercon 7-2E-71 17 (2

-7 9-??-71 B

(2-4 10-ro-71 lo

_(4 3_

11-17-71 11 (5

6 1 71 2.T (5

~6 Region #3 - Vest of fir 4nt Site Holland

.7-2'-71 13

_(h '

6 t-1f:-71 16 (T

6 9-??-71 1?

(h 7

10-TO-71 19 (5-g 11-17-71 9

(4

[$

12-16-71 14 (4

6 I

l

i-

'I5bic 6

!!I1X pCi/ liter

}

Co5e 137 131 9b on 00 1

Sr Tamplinc locntion Ecgion #3 - cont.

Ilophins 7-28-71 10 (4

5 9-22-71 13 (3

6 10-20-71 24 (4

6 11-17-71 14 (5

3 12-16-71.

13 (3

7 Urich 8-18-71 17 (4

10-Region #4 - South of Pinnt 'lto L. Becker 7-2 -M 23 (5-8 8 '1 17 (3

10 9-22-71 12 (3

5 10-20-71 8

(4 6

11-17-71 14 (4-9 12-16-71 7

(3 5

(

Vetsch 6-18-71 21 (9-9 9-22-71 9

(2 7

10-20-71 9

(3 7

11-17-71 15 (4

8 12-16-71 16 (2

9 Zachenn 7-2E-71 15 _

-(3-8 Elk River - Fast of Plant Site Ihrthel f-24-71 17 (4

6 11-23-71 16 (4

12 (3..

16 Inkoduk G-24-71 11 1 13 (3

18 lie 11 son 0-24-71 21 (4

.11 11-10-71' 19 (3

18 11emeth E-24 22 (2-14 11-10-71 32 (4

21-

. b.-

i

y TAB 12 7 GAMMA DT. AGE mr/4 weeks

~

htte of Collection

~~

4

.s a

e 1

2 A

1 4

a e-i i

iccation

(, a'.,,

,, f, _

J

_ Lg

!1_

ij -

M Utstion B1 11.0

'). 4 10 5 99 99 10.0 9.4 10.0 station J2 10.1 B.5 9.8 95 9.6 95 Station O 9.2 S.3 99 9.4

9. _4 9 2 --

9.4 9 3-Station f4 10.1 91 9.6 10.2 92 10 3 91 97 Station v5 10.1 91 97 9.6-93 9.6-91-95_

10.4

- 10. 4 -

Station #6 10 9 96 10.6 10.4 10.4 92 96 95 Station #7 92 10.0 Station #8 10 5 95 10.4 10.2 10.2 10 3 98 10.1'-

95 93 92 93 9.1 9 3--

(.

Station #13-station #14 0.6 S.4 10 3 97, 10 3 9.8 10.2 9.8 Station #15 8.7 8.4 93 94 9.4 96 9.o' 91 Station #16 95 83 9.5 9.4 91 91 8.8 -

91 station #17 10.7 8.9 10.4 99 10.0 96 92

_98 Station #18 95 90 92 9.8 97 9A b

]

s

r. :

Table 8 -

PCSSISSIPPI RI'IER WATER Upstream of Plant Downstream of Plant St. Paul

dater Intake 7 i Fa'A/1 rCi Cs-1 9/1 eCi Bata/1 pCi Cs-137/1' 7"i Be'A/1 p"iOs-17/1 0

'L.

12

-(2 15 (2

i 13 (4

1

- 12

.(2 11 (2

i lh

!2 i

' 71 -

10 (5 '

9 (2

19 (3

71 8

(2 9

(2

[

6 (4

.1

-17 (2

9 (2-13-

{3 10 (2

9 (3

11 (2

\\ 71 '

7 (2

7 3

i 9

(4 I

' 71 5

(3 8

(2.

10 (2

[

i i 71. -- (2 9

2 11 (3

1 12 (2

8 (2

k 10 (2

1 2

(

l 1.

7 (2

~9 10

-(5 p7r

-S

- (2_

7; (2

[ -

O

.}

^

Table 8 HISSISSIFFI RIVER WA~ER Upstream of Plant Downstrear of Plant St. Faul Lt **r Intake Date of.

Colleetion DCi Beta /1 pCi Cs-137/1 nCi. e9 /1 ~

UCi09-1311 ~

rCi Bgtef1

,Ci_Cs-137/1 9-21-71 7

(2 9-21-71 to 9-27-71 6

(2 5

(2 9-28 11 (2

9-28-71 to 10 4-71 6

3 7

(2 10-5-71 8

(4

--10-5-71 to 10-11-71 7

(2 5

h.

10-12-71 S

(2 10-12-71 to 10-18-71 8

(2 8

'S 10-19-71 9

(2 10-19-71 to 10-25-71 10 (5'

9 U*

10-26-71:

9

-(2-10-26-71 to 11-1 -10 (2

11 4

. n-2-71 12 (2

n-2-71 to 13-B-71 9

(6 9

7 n-9-71 9

-(6

~ 10.

(3 10 (2

11-9-71 to n-15-71 11-16-71 8

(2 ln-16-71 to n-22-71 8

(2 10 (2

..11-23-71 9

(3 n-23-71 to 11-29-71 8

(5 10 (2

11-30-71

.13

'5 i

n-30-71 to 12-6-71 11 3-7 (4

4 Table 8 MISSISSIPPI E1ER WAM Ihte of.

Upstream of Plant Downstream of Flant St. Isul Water Intake Collection

' Mi Beta /1 pCi Cs-137/1 rCi 3-ta/1 pCi Cs-17/1

Ci_ Peta.'1 eCi Cs-1p/1 j,

11 0

12-7-71

.12-7-71 to 12-13-71 7

(3 6

(2 9

-12-14-71 9

4 12-14-71-to 12-20-71 11 2

10 6

E $12-21-71 10

- (2

.12-21-71 to 12-27-71 12 (2

11 (2

5 (3 23-71 i

s

.,,...,.,,.....-n-e

- ~. -,, -

.m.,

w a-

O Table 9 MISSISSIFFI 111VJli WATCR MO!G 1,Y Cu 113 ITIS 1971 leriod Urnt re,n of i hnt vowristrean of 11nnt St. Inul Intnke OI 2

00 3

90 2

00 Collection pCi 11 / 1 pCi Sr/1 pCi 1!/1 pCi ' Sr/1 pCi 11/1 pCi < St July 700 1.7 700 1."

300 1.9 August 900 1.7 200 15 300 1.6 September 900 1.4 1000

1. ';

700 1.4 October 1000 1.7 900 1.2 600 1,5 November 700 1.2 500 1.0 700 0.S Neember 700

?.1 500 19 800 1,1

(

i l

k..

Tatble 10 q

IAKF., WATER :

p0ifliter Dra te of

'Irosa

_ q)S r g)7 Sarnpline loca t ion Colleetion 14e ta Ca kl Bass lake 64'1 14 (2

1000 2.0 i-30 "1 11-(5 900 0.6 10 n 1J

<P 900 29 10,' # "1 l '.

s4 Um 31 11-11-71 10 (5

900 3,o 1J-J'g-71 12 (4

1300 5.9 Bi6 Iake 7-10-71 X'

(2 1200 4.6 s-4 "1 1h (3

1100 52 c.- e- - 1 10

( P.

1100 51 10-o '1 M

(2 1700 50 11-1 M 1 19 (5

1400-5.')

1:-22-71 16 4

1100 4.2 Clitty inke 7-19-71 3fs (2

1200 2.2 n-4-71 12 (5

1100 25 9-3-71 13 (5

500 25

{

10-6-71 35

($

1100 43 11-10-71 11

,2 400 17 1?-22-71 13-(3

?OO-4.2 Ida lake 19-71 21 (2

2"00 4.4

'. 4-71

?O (1

1 -00 3.o Bertram Inke 9-ft-71 10 (2

?OO

1. 6 --

10-6-71 14 3

'f00 1.1-11-10-71 12-(S

'1100-13 12-22-71 1?

(2 900 1.2 lockt lake 7-19-71 17

,J-200 19 E-4-71 14 (4

1100 25 9-3-71 9

(5 900' 25-10-6 '/1 1?

-(2-1300 2.1 11-10-71 t-(5 500 1.8 12-22-71 13-G i00 0.8 llud lake 7-19-71 4f2 -

(2 600 2.0.

6-4 42 (2

700-P.5 9-6-71 23

( 3--

1200

.2.1-10-6-71 25 (3

-.1200

< 2. 0.

11-10-71

_ 1 ".

(2 400

- 17.

12-PP-71 19 (2

600 1.7 b

'!hble 11 1 AKL f, 31V7.R BirPUti S?.DIENTl1 un, r m

...hte of

,, ono ar rril ctitm Nta Oc y,,)C.

10/> Tea %r 9r-734 S

'Zr Feepline Inc9 tion f

~.

Tunr Inke

'0-71 42 0 0" O.02 Partrar Inke 10-1-71 40 0.

O.'

O..

O. ;'O O.04 Big laFe l' -l'-71 4 :'

l.10 0.06 Clitty Inke i t -i'- 71

0 1.1 C

.)

00) 0.44 0 05 locke Inke 13-1-71 47 0

0 07 Mud Inke 19-1-71 76

0. 'l 0.03 Mircirnippi River-t,pu re am 10 ^-71 40 0.Cr-(.01 Miccir.ri ppi I4ive r-1** r.s t rea m l'V -71 h7

(.a

(.01

/

(

i

- _. =

i

,i

'Ihble 12 1A}3: & HIVD AC.*ATIC VE'lETATICH i

pCijnrnm II 106 M

95 ppi,i_n,g loca ti on C 1 e 1or Oc

' 02 I

7g Sr Zr Minnisnippi River-Upetream of Flant 7-5 71 110 (01 0.48 4-l')-71 92 11 (O.C (O.?

9 0 55 13 19-2-71 76 3

(0.6 (0.1 4

0 35 1.0 Hisnisnippi R3ver-Dc,unstc;. n of Plant 7-3-71

'.00 (0.S 1.10 E-19-71

??

7 n;

(0.1 4

0.72 1.4 1D-2-71 67 9

1.0 (0.2 4

0 55 19 Baoslake(C,4*<I) b-31-71 f> i 5

l0. '4 (0.1 3

1 10 2.B Bertmm Iake 10-1-71 54 (5

(0.2 (0.2 7

-0.17 0.7 11-11-71 59

/0.5 (0.6 2.10 Big lake E-24-71 SO 10 (1.0 (0.2 5

4.20 2.0 10-2-71 110 (2

0. 2 (0.2 (1

5 30 (0.4 11-11-71 117 O2

.1 40.00-C11 tty Iake B-24-71 42 6

(1.o (0.1 3

2.20_ (1.0' 10-2-71 97 17' 1.3

-(0.1 5

5.60 2.5 11-11-71 44 (0.2 (0.2 2.00 locke lake 8-24-71 42 8

(0 5 (0.1 4

0.72 15 10-1-71 46 (3

(0.3 (0.1 (2

0 30 0.2 11-11-71 69 (0 3 C.4 1.40 Mud lake 3-24-71 29 9

(0.6 (0.2 4

0 58

(.4 - > 1-71 51 (3

(0 3 (0.1 4

0 50 0.8 11-11-71 24 (0.1 (0.1 0 99 i

x,

,...... +,

, ~,. ~.-

,,.n,

--r nw,, n,,

._. _ _ _ _ _. -,._-. _ _ _ _.~. _.

~ _ _ _ _

l t

t i

O W, hie 13 i

MISSIS 311TI.'3 /G A?'.'iCi! O AJ:U.

~

_ni;i /r r:4m D3Le of Cror '1 Snenlint-loca tion Collectfor Bo '.,

g,,Co

" Cn h

T.r Zr g-

,g Stntion #1-1400' Above Intake

'~-9-71 20')

7,';' */1 1.'0 c.5-71 r0 3-19-71 u-? '/1 l i' '

o 16 '/1

' 's 9-l0-71 4

10-14-71 6

10-i?f-71

??

Station #2 - 700' Above Intake 7-9-71 110 7-22-71 100 8 'i-71 7r l

-19-71 70 s

l

(.

9-2-71 110 c.-16-71 Mo 9-30-71 9i 10-1L-71 62 30-23-71 72 i

l Station #'4A - Acrona From Dischargo Canal 7-19 150 7-22-71 b6 I

6-19-71 70 9-2-71 130 9-30-71 59 10-14-71 76 10-T,B-71 '

EO Upstream Componite-Station #'s

. l0.5 0.8 1, 2 and 4A 7-9-71 l

1, 2 and 4A 7-E-71 5

(1.0 14

~ 1.4 10~

1 and 2 2-5-71 24

- {0 7 -

14 1.4

_5 1,-2 and 4A C-19-71.

29 (1.0 9

P.4 4

1, 2 and 4A 9-2-71.

20 (0.6 8

1.7.

3 :-

1 and 2 9-16-71 105

@.0 43 2 3-22 1, 2 -and 4A 9-30-71=

0.4 1.4 1, 2 and 4A-10-14-71 0.2-

0. 9.

1, 2 and 4A 10-23 0.8 1.4

-- (.

L p

y. -. -,,.... -

r--

-'es---

--+-*ur'=*--

?'e r e 'tev e--

w w r e ~ ~ v-w 4

-*++e.---w-v m--vvv-**-'+--w-rw-*'eew+-*v-+'e='w

- - ' - ~ = -

p Table 1!

11SSISSIPI'I HIVZR AT'3AC19:1) AfDn vuijrinn

~

~~

kite of Grona IN 1

N 95 pyglint-location Col lec tio;;

Betri Cn cc

ta Sr 3r-Station #9 - Oxbow 9-9-71 79 (P.0

(.6 7-??-71 130 43 C.o 26 1.0 17 6-D-71 120 110 (6.0 60' 1.6 13

'-19-71 P

60 00 50 l0.7 1s 9-2-71 IN 19

( 3. ')

21 1.6 4

9-16-71 03 (20 (J.0 23 1.6 4

9-30-71 91 r

10-14-71 71 (0.4 15 Station #3 - At I>ischarge Transect West Ibnk 7-9-71 130 7-?

'l 9%

8- - i 92 J-19 'l 42 9-2-71 71 9-16-71 87 i

9-30-71 7!,

10-14-71 80 10-26-71 71 Station #3A - At Discharge 7-9-71 160 7-22-71 160-B-5 95 8-19-71 85 0-2-71 B5-9-16-71 65 9-30-71 77 10-14-71 96 10-26-71 93 Statien #4 - At Discharge Transect.

Hidstream 22-71 210 2-5-71 110-3-19. -33 9-2-71 51 9-16-71 69 9-30-71 53.

10-14 65 10-23-71 64

(-_-

l l

(3 Table 13

!!ISSISSIPPI UIVER ATTACHED AIDA7, p01/<Inm E

Nte of Grs.ca 144 1?

106 40 95 S,3 p In m' i on Colleetiot.

E-ta Ce Co N

' Sr Zr 1

Station #5 - At Dircharge Trancoc*

East Ihnk 7-l l'-71 l'0 0-$-71 no L-19-71 "5

9 '-71 110 9-16-71 106 9-30-71

!6 10-14-71 (i

10-2D-71

';7 Station #6 - 1500' Below Diccharge West Ibnk 7 -)-71 150 7-2?-71 120

!>r-71 70 b-19-71 45 9-2-71 110

(

9-16-71 71 9-3CL71 59 10-14-71 74 10-2b-71 60 Station #7 - 1500' Below Diacharce Midstream 8-5-71 120 E-19-71 4 ?>

9-2-71 E6 9-16-71 67 9-30-71 54 10-14-71

'4 10-?3-71 53 Station #8 - 1500' Below Diccharge Eact Ihnk 7-9-71 140 7-22-71 120 0-5-71 99 2-19-71 62 9-2-71 A

9-16-71 b

9-30-71 10-14-71

'/7 10-N'-71 70 i

e

fi Table 13 MISSIS $1PPI RWZR ATTACHED AlDit:l p.h /rram lhte of Gross ll* 4 W

106 90 95 g pling Ioention Oc 21e nti_o_r Poin Ce Co Ru Sr Zr

=

Station #10 - 3100' Below Dircharce

'/-9-71 130 7-??-71 110

,-5 71 71

-19 '11 o p-71 C;

c.-1(,-71 lo:"

M O-71

!A i

)(w14-71 7

10-?3-71 S/,

Sta tion #11 - 5300' Below Dischart;n

-.0-71 I ?'

- r-71 99 6 91 12n

. -l' -71 7t'.

t

{

9-:-71 99 9-16-71 7

q-30 91 c f.

10-16-73 e

Station #12 - 7600' 9-70-71

.N Below Discharge 10-14-71 LO 10 70-91 va Station #13 - 12000' 9-?O-71 H

Below Discharge 10-16-71 20 10-06-71 7

Composite of Trancect and Downstream Station d's 3,36,6,8,10 E,11 7-9-71 so.

0.7 3,3A,4,5,6,$,101117-P2-71

's 0 s.

. 11 1.1 13 3,3A,4,5,6,7,E,10011 L-5-71 11 (0.,

33 1.~

6 3,3A,4,5,6,7,6,&11 3-M-71 16 D.?

9 1.6 4-r-?-71 10

1. 7 -

-5 3,3A,4,5,6,7,f,1041 c

-3,3A,4,5,6,7,E,10 M 7-10-91 L:

1:

17 1.4

- S.

3,3A,4,5,6,7,8,10,11,1N U 9 'n-71 V+

0.f 1.2 2

3,3A,4,5,6,7,e,10,11,1c^13-10- 3-71 o.U 1.0 3,3A,4,5,6,7,8,10,12,61, 10 S.-71 (0.1 1.6 1

s.

L.-..

Table l'.

IAKC AllD C(A.T0317M l'ISSIS3111I !!1h;;' A?!A'E:D' AIDA'.'

b riod hCi[Irram I

0"'""

1h's 137 106 90 95 Sampling loention.

Collectfor Nta Ce On iha Sr Zr

- - - - - - -. -. =..

Upntream of Phnt

-?h-71 6's N

.7.0 17 1.7 3

' 9-N-71 6-O.

p,o Downntrents of l'hnt 0-?h-71 5e 3

l7,3 r,

1,5 4

'-:. - 71 6~

-1.0 23

/.0 4.1

' % -71 9'

Bertram 1che 1

10-?6 '/1 J0.~

-2.5

'0

4.0 (IT Di,r, !nho

. A 'M.

7f l

4 16' O0, 10.,'(,,

'3 f. ",

e,o Cittty lake

-;n-71 110 00 sk.o (14 73 4

10-:t6-71 6r

?.

6.14 loci:.' lake

-?!.-71 51 17 sG.9 (I

O.8 3

to-P6-71

,4

( 0. '$

1,3 2

!!ud Inke i-24-?1 5'

O 0.9 O.3 (1

A-Table 14 FISH SAeleton flesh Date-g g

137 to

' 27

-90 Sampling.

of location Type Collection Gross Bata Cs

' Sr

~iross Beta

-" Cs Sr Upstream

'Redhorce, Cucker, 6-23-71 91

.05

.017 20.0

.03

.26 and Carp

.07

.015 16.0

(.02 2.4 '

carp 9-29-71 7.5 1 30 Redhorso

'12-2-71 5.3

.12

.073 26.0 0.02

.06 1 90 Walleye and Bass 9-10-71 E9

. 10

, cot, g,g

(.C?

7,00 Black Crappie 10 0-71 6.9

.C'4

, cot 19,o 4.02 2.00 Downstream Redhorse 9 C-71 E.4

.03

.017 16.0 Carp c-29-71 7.1

.C4

.017 16.0

(.02 2.60 Ecdhorse 2-T 41

.32

.07E 29 0

(.01 0 38 36 07 1-50 h'alleye and Bass 19-9-71 7.4

.03

.002

^

6.7

.06 1.20 9-29-71 5.3

.02

.g4

~

b.

_~..

i 0

1hble 15 p

CIAMS (Flech) pCi/ cram lhte of 137 Sampli_ng location Collection Ornns Beta Cs Upstream of Plant August 9 throuch 4.'

(.02 23, 1971 Downstream of Plant August 6 tnrourh 4. '-

.02 9,

4 72 h ble 16 1AYI L HIVE:. AQUATIC lilSECTS PU)( ~T'*

lote of G < oc>a f

C:>ter.linc Lnention C:113c+ ion

!; f u g.,C n 33.,I 99Sr iL. ;.f r.sirp.4 I:iver -

B-24-71 4

t.

(;

(.9 (0.4 Ups tre:r.

10-9-71 C.?

M (12 0

'(1.0 Hississippi River -

8-04-71 4.-

3 (1 5 0.8 Downstream 10-9 (9 6

(3.0 0.8

. Bertram lake 10-1-71 li:

(:

(.h 0.8 Clitty lake 8-19-71 10' 2

.(.9 32.0 10-2-71' (6

4 (1.%

19 0 Hud lake 8-19-71 1ho (1

(3.0 16.0 10-1-71 70 (6

0.0 11.0 10-26-71 99 2-25 0 I

-y

..a, g-4~v w

,,-,r,

,y-,-r r

.v v

,,,,.,. - - - +,..,

Ihble 15 CIAMS (Flesh) pCi/ cram D:xte of 137 Sampling focation Collection Gross Beta Cs Upstream of Plant August 9 hrourh 4.?

(.02 23, 1071 Downstream of Plant Au;ust 6 tnrouch 4.6

(.02 9, i 71 h ble 16 1ATS & RIVE. AOUA7IC 1tJS1' CTS

~_

in te of G i ucos e.

~w AN 131 90

{

E mr.lin,c, Loen ti on C911 action 1-tu Cn I

Sr

!!i::sicsipp5 I;iver -

3-24-71 4.t

(;

(.9 (o.4 Ups t rew.".

1C-9-71

(.7 s6 (12.c (1,o Mississippi Piver -

8-24-71

t.. -

3 (1 5 o,8 Downstream 10-9-71

(.9 (4

(3.0 0.8 Bertram lake 10-1-71 la

(!

(. ?i

.O.8 Clitty lake 8-19-71 109 2

(.9 32.0 10-2-71 66 4

-(1.5 19.o-Mud Iake 8-19-71 1ho (1

(3.0 16.0 10-1-71 70 (6

0.0 11.o 10-26-71 99 2

25 0 (L i

.m

/'...

"'ablo 17 FISID VSGTATIC

~

vC1/crnm Ibte of a ror.c

,g 137 Swnlin,c loca tion Co11cetion Bata Ce Cn 9

Zr u

Vogototion Field #1 E-3-71 75

<8 s'. 3 3,7 Vor,etation Field //2

.-3-71 41

?

s.J 25 Vegetation Field #3 8-3-71 64 1 'i

4. 3 19 Table 1E f

A0RICUI.TURAL C!! CPS pC i/crae Type Ihte of Groon Sample Sampling location -

Collection Deta 1" Cn-131 90 I

Sr Potatoes Dechene Potato Co.

B-3-71 0.9

(.005

(.004-

.005 Ewing Potato Co.

8-I-71 L.0

.011-t(.005-

.004 Peterson Potato Co.

8-3-71 9.2

.046

'. 006

.006 Soybeans Dechene Potato Co.

9-14-71 05

.030

(.020

.cr/5 4 4

n,

-n

--r-~-v w

0,

fm Table 19 TOTGOIL PCi/.~ ran

0""

lh4 137 106 90 95 STmpline location Collection _

Be ta Ce Cs Ru Sr Zr Vegetation Field r/1 3-3-71 60

.17

.16 Vegetation Field 772 8-3-71 C2

.33

.16 Vegetation Field #3 8-3-71 52

.26

.22 Dechene Potsto Co.

B-3-71 fl

.25

(.01 40

.19 (Potato Field) 9-14-71 c'

Dechene Potato Co.

3-3-71 10 17 4

.04

.24 (Soybean Field)

Ewing Potato Co.

8-3-71 57

.22

.11 (Potato Field)

Peterson Potato Co.

3-3-71 52 1.1 33 3

.16

.12

{

(Potato Ficid)

I, g

y

Table 20 WELL WATER pCi/ liter Date of Gross Gross

_ Sampling location Collection Alphn Beta Cs b

90 57 Sr Gauthier 7 27-71 (3

3 (3

1000

(.10 10-6-71 (4

4 (2

1300

.23 Schultz 7-27-71 (3

3 (4

700

(.10 10-6-71 (S

5 (5

1000

.28 Swanson 7-27-71 (3

3

(?

1400

(.10 10-6-71 (4

2 (2

1800

(.14 Trunnel 7-27-71 (4

(2 (4

400

(.10 10-6-71 (L

4 (5

1100

.it Monticello Supply 7-17-71 (4

7 (2

(200

(.10 B-l'-71 (4

4 (2

(200

(.10 9-o-71 (4

(3 (3

300

(.15 10-t,-71 (5

4 (2

200

(.14 11-17-71 (3

3 (2

(200

(.10

(

12-25-71 3

3 3

(200

(.10 Plant Supply #1 7-20-71 6

8 (2

200

(.10 3-17-71 (4

4 (2

400

(.12-9-8-71 (4

6 (2

300

(.13 10-6-71 (5

9 (2

700

(.12 11-17-71 (L

4 (2

600

(.10 Flant Supply #2 7-20-71 (4

S (5

(200

(.10 S-17-71 (5

6 (5

200

(.11 9-2-71 (4

7 (2

600

(.12 10-6-71 (5

6

/5 700

(.13 11-17-71 (3

h (5

300

(.10 12-23-71 (3

3 (2

400

(.10

(

..x.

4..

e 0

t3

..I s

D M

d

.'.1 93)

(n sq

.t L

EL g M A

W G d

cl

- a 9

b th 5

l

~

t.,t a

a~

.. a.a t, s

~

!1 t

}

l

.O c

A a

. c. -

,(f'tpffe,;. %

i a

e v

l LJ

\\/

gr U

s ;.,

.8 :

j Q.)

t>

em

-o.

w.

p.?

,0 y

&~

(,.

tj ez p;

,; f.

s t

ly d 41 es c3 %

u,','%g-

'f 1

WG A C) g c

C gj

[

L 'y d 1

m g***"*

% by % bh:

. ud,?

' /'

y l1 w.J d

., /, n;.

g c -- ps -

~

v m

4

~

p [fl9

@q u$N s e,y

\\h(/

(31 pi A

_e

,w q. 9)

.,), p# ' -

C sc

_ (-

. _ f f-L/d Oh F

g.

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- @), -

'QaNDj 4) ew<

c.

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f Vll.: CHAtBES, TESTS and DPERIMCNIS i.
q:
This section describes plant modi fications and-special tests performed during the past year. However, several major' items (such as the--removal-of torus _ baffles, extension of relief valve discharge lines,_ main steam flow restrictor modifications, and testing of_ the flow restrictors at greater than rated flow) which have been previously covered in separate reports to the AEC, are not included.
Installation of Banana Ploes and Peceptacles for the Steam leak Detection jiystem Temoemture Switchen n_ssocinied wi th the HPCI Svntom (16 swi tches).
f CIC System (16 swi tches) and t he Mai n S team t i no ( 16 swi t ches).
The 48 steam leak detection temperaturt swi tches were originally connected to local wiring by neans of twist-on wire nuts.
Each tino the switches were removed for calibration, a por t ion of the connect ing wi res was removed.
To make the swi tches nore easily removable the wi re nu t connectors. have been replaced wi th in line banana plugs and recept actes.
Af ter the plugn and receptacles were ins talled 'the proper reactor protection response to a hi h tenperature was veri f ied for all temperature swi tches.
C Installation of Vacunn Broaker nn t he l ow Presnure Side of the Reactor Vessel Ven t 1 i ne t o Cl or.ed Radw as t e f
A vacuum breaker was installed between the reach" vessel vent valve (XDV-3) and the drywall equipmnt drain sump to prevent 4rmation of a water seal in the drain line which would result in a vacuum i n.the vessel when the-vessel is cooled below 212 F.
(See Figure 1) The vacuum breaker is located af ter the two isolation valves on the vessel vent line.
Bomun1HPCI Svntem 1.nvel Swiichen 23 91 A and 23 91B The level switches which transfer the HPCI system suction to the torus on high torus water level were relocated from the torus to the adjacent concrete wall to prevent spurrious trips caused by torus vibration. An ori fice was also installed in the lower sensing line to damp out vibration induced waves in-the torus.
(See Figure 2)
Core So av -System I njection Valves - 450 osi I nledack The control logic for the Core Spray System injection valves ( AD 1751 and A01753-in "A" loop and AO 1752 and AD 1754 in'B" loop) was modi fied to permi t single valve operability tests wi th reactor pressure below 450 poi. The original-valvo control circuit would open both valves -when the inboard isolation valve q
control switch was operated wi;th reactor pressuro below 450 psi.
T he cont roli circuit change consisted of removing wires from the ' inboard isolation: valves control switches (40-1751 and LO-1752)' contacts 2 and 2T which energized the?
i Valve Opon Permissive relay (14A-K13A) when reactor pressure was greater than
]
450 psi. This opened both the inboard and outboard isolation valves for the
{-, >
affected Core Spray Svstem ( See figure 3). -With the~above change _ completed, j
the valvos can be opened, one at a timo, through the 1 and IT contacts of'.
~~l a~~
_._ _ -_-~ _.
~
thei r :. ont rol respect i; ve _swi tches.. The operation-of the valve cont rol=
bg ci rcui ts-during automatic' core spray ini tiation is unaf fected.
):
RCIC System Exhaust Pioine Vacuum Breaker installation
. A solenoid operated vacuum breaker was installed on the exhaust piping ofI the.
RCIC turbine to prevent a steaVwater hanrnor in the steam exhaust piping af ter sys tem shutdown. The steadwater hammer was caused by condensing -the-residual steam in the exhaust line af ter the turbine shutdown, and thereby draa mp torus water into-the evacuated exhaus t line.
When the system isL shut- --
down and steam supply valve W 2078 is-closed, the vacuum breaker opens for three minutes to break vacuum in - the steam exhaust piping (See Figure 4).
T he vacuum breaker solenoid valvo is de operated from the 125 V:DC _ battery-supply system. This permi to valve operation during loss of off site power and is consistent with-the RCIC electrical design philosophy.
Upon loss t
of power or solenoid failure (open ci rcui t) tho valve fails closed.
I f the vacuum breaker solenoid valves should fail open during RCIC operation,-
a small amount o f exhaus t steam, at 8 psig, could be discharged to the RCIC room atmosphere. Pri mry containment integri ty would s till-be satis fied as -
there are two check valves on the RCIC turbine exhaust line before i=t enters k
the torus.
T he escaping steam would be moni tored-by the reactor building exhaust plenum radiatton monitors.
The steam leak detection alarm and isolation temperature switches, located approximately eight feet above the -
vacuum breaker 1-ine would alarm at 175 f and shut the RCIC steam supply-
{
valves at 200 LF.
l Moisture Seonrator Cent rol System Modi fi rat ion 1
The moisture separator level control system was modi fied to automatically open the moisture separator drain tank dump valves to prevent brbine trip; and subsequent reactor scram caused by high moisture separator water level.-
t-The changes lis ted below were made to all: four moisture separator level control systems (See Figures 5a and Sb).
1.
An instrumentation standpipe was ins talled to cover the range of the moisture separator drain tank high water level alarm and the mositure separator high water level turbine lockout relay trip.
s-2.
A ten second delay was added to the moisture separator -high water s=
level trip.
3.
The second set of contacts for the moisture separator-high water level I'
switch was. connected to open the moisture separator: drain tank-dump s valve.
4.
The moisture separator drain tank high water level alarm swiich was connected to open the moisture separator' drain tank dump. valve.
5.
A di fferential pressure swi tch was installed between t'he top of the
~
moisture separator and the -top of the moisture separator drain _' tank.
(
The switch trips the noisture separator drain tank dump valve when high pressure in the drain tank causes water to backup into the m
v
,r.w
_.v..,
w the moisture separator. -
The effect-of thesh-changes lwas to makeithe-moisture separator level control-system more respon'sive to sudden plant -power level'. transients.
Pressure Wave Sensorc' on Ma'in Steam li ne.
Six pressure sensors were temporarily added to the main stsam lines between the M31V's and the turbine control valves.tof measure pressure' variations during plant transients.
Pressure sensors were added as shown in Figure 6.
T he instrumentation was removed at the conpletion of-the startup test -
p rog ram.
Modi fi cat ion of the Reactor Reci rculat ion Pures Seal Svsiem -
The reactor recirculation pump seal systemc were modi fied to prevent thermal shocking the seals. following punp t rips wi th = the reactor at rated temperature. Two modi fi cations were made:-
1) An air operated shutof f valve was installed in the recirculation pump controlled seal leakof f line. The valve will automatica1ly close on pump trip and thus prevent not reactor water from being forced through the seals.
~~2) A continuous seal injection system _ was installed-to.prov'ide. a cooling~~
(
water supply to the lower seal cavity. 'The injection system;is supplied from the Control Rod. Drive Hydraulic' System (See Figure 7).
i The air operated shutoff valve was designed to fail open on loss of air pressure and loss of electrical power, thereby assuring continued seal cooling-and lubrication.
With a recire punp isolated, the seal injection system could pressurize the.
pump -casing and:the piping between the isolation valves.: Relief valves ha've-therefore been provided-in each seal -injection line.
Connections are provided for leak rate? testing the check = valves _on either side of primary ~ containment.
Pressure' Module Connections to Reactor Pressure Ins t rumentat ion -
A temporary pressure. module was tapped into eighFexisting reactor 1instru-mentation 11i nes. The. purpose of the module, consisting of two pressure --
dif ferential transmi tters and associated valving, was. to measure pressure :
drops in the recirculation system not measured wi th existing plant-.instru-i s
mentation. The -following -' inst rument lines were tapped:
I ns t rument - li ne '-
Pressure DPT 2-111B (low)
Reci re Pump Suction
(
WPT 2-IllB=(high)
Reci rc-Pump Discharge-
~
DPIS 2-129 A (low)
Jet Pump End Riser?
DPT 2-3-65 (low))
Downconer w
. g>
n I nstrument li ne Pressure DPT 2-3-62 ( hich)
Below Core Plate DPT 2-3-62 (low)
Above Core Plant DPIS 14-43 A Core Spray Sparger DPIS 2-129 C (low)
Jot Punp Middle Riser The pressure module connections were recoved af ter the completion of the startup test prog ram.
RClC and HPCI Sysiems Coni rol Ci rcu ii "odi fi cat i on The RCIC and HPCI systens cont rol ci rcui ts were modi fied to automatically perform the followi ne whenever the respective steam admission velves are opened (See figure B):
1)
Close the steamline drain valves, CV 2046 A and B for the HPCI system and CV 2082 A and B for the RCIC system.
2) T rans fer the condensate pump discharge from closed radwaste to the respective RCIC or HPCI punp suct ion by closing CV 2394 A and B for the HPCI system and CV 2898 and CV 2899 for the RCIC system.
Prior to this change the above operations were performed automatically only when the systems were automati cally ini t i ated.
Du r i ng the manual mode o f I
operation of the sys tems, the operations had to be performed manually.
' The changes do not af fect the automatic operat ion of the HPCI and PCIC systems.
Reactor Relief Valves Modi ficat ions The reactor relief valves (4 valves) were modi fied to decrease the closing time of the valvo and to reduce the pressure reset band. T he change involved increasing the size of the ori fices in the second stage and main pistons.
The work was performed under the direction of a Manufacturers representative.
The change does not alter the relief setpoint.
Modi fi cat ion of the Haci rculat ion Svsten of ihe Reactor feedwater Pomos The reactor feedwater pumps recirculation system was modi fied to provide greater reci rculation flow and better control.
The recirculation lines were increased from 6" to 8" to provide a higher minimum flow. The size of the holes in the recirculation spargers in the condenser were increased from 3/8" to 1/2" to accommodate the higher flow rate.
New flow control valves and ' associated cont rols were installed i n the recirculation lines to replace the on-off type originally supplied. The controllers in the recirculation line now have proportional band and reset and are set to control total flow through each pump at a minimum of 3000 ppm.
The new reci rculation control valves are of the " drag" type and take the full pressure drop. The restriction
(
ori fices provided wi th the original system were removed.
A start permissive interlock was added which requires that the recirculation valve be open before the associated feedwater pump can be started.
I l
l
..- ~ - - - -
t
-5.
q a
Modi fication of the Reactor Reei rculation System Valves Closinn Control Circul t-The closing ci rcui t for= reactor reci rculation" system valves (pump' suction;:
- discharge, discharge bypass and loop - cross i10) was modi fied to prevent-over-torquing the valves into the seat (which can later resuli;in' failure of-the valvos _ to open). _ The contact in parallel wi th the torque switch was -
changed from a contact which is closed for 5% of 'the closinc stroke to a contact which is closed for 95% of the closing stroke (See Figure 9).
T he '
contact opens at 95% of the closing stroke -allowing the ~ valve to' torque into the seat.
Removal of the torque swi tch from the closing circuit du ri ng 95% o f '
travel allows the torque switch setting to he maintained at a low value, just sufficient for proper-valve seating.
Previously, -'i t ' was. nocessary to set the for que swiiches high enough for the normal fluctuation in torque that ~
occurs during the valve stroke. Upon receipt of an LPCI initiation; the reci rc system valves must close to properly colect the injection. loop.
The modi fication to the valves provides greater reliability. The valve
~
motor overload contacts are the only contacts which can interrupt the closing signal.
Modi fication of ihe Scram Discharre Voluno
'i The scram discharge volumo was increased to provide 3.34 gallons of free volume available per drive (405 gal) during a reactor scram. This modi fi-
~
cation was made to provide addi tional margin to accommodate the normal c
over-piston water during:a scram plus stop-piston seal ~ leakace.
As'the CRD mechanism stop piston seals wear with drive use, the leaNage of reactor water across these seals durina a scram increases. The increased scram discharge volume will accomod5te the normal scram water from a -CRD plus the.
maximum stop piston coal leakage wi th which a drive would still be operational.
Addi tion of Pulsation Snubbers to the Sensinn Line of the Main Steamline Hich Flow Inolation Switches The-sensing lines of the sixteen main steamline high-flow.swi tches (DPiS
- 116 A thru D, 2-117 A thru 'D, _2-118 A thru.- D, and 2-119 A thru D) were fitted wi th self cleaning, pin-type, pressure snubbers to_ reduce the di fferential pressure fluctuations observed during power operation.
The snubbers are ' located -
between the di fferential pressure switch.and the associated instrument-valve mani fold such that the snubbers are included each time pressure is applied to the instrument ' for test.and/or calibration. ~ Following snubber installation, all. of the instrument sensing-lines we_re tested by~ applying pressure di rectly to the lines;while veri fying movement of the instruttent pointer' to insure that
~
the snubbers did;not~ block the sensin2 lines.
~~Deletion of SBGT Heater SCR Cont rol Ci rcui t ry _~~
. To provide more reliable operation of SBGTS air heaters E-34A-1 and E-34B-l',
L the heater SCR control ci rcui t ry was' replaced' wi th' contactors which one~rgi ze the electric' heaters when the proper minimum flow has been detected by the
- existing flow switch (See Figure _10).
Previous experience had shown that (i
the heater SCR control circuii was not needed since full power to the heaters
. is requi red to maintain adequate heating of the incoming gas.
g WwY w-y
-r
I
' 1 fy
~~
Modi fications of the Off-Gas l oco Seal and Loco Seal' isolation Valve CV-1534 Cont rol Ci rcui t A-level switch was added to the of f-gas loop seal to closeithe _ loop _ seall isolation valve (CV-1534) on loss of the water seal.
Also a:manualEswiich was added to allow Ihe conirol room operator. to manually close the loop ', _
seal isolation ~ valve.
(See figuros 11 and 12). The.addi tion of the -level:
switch and the manual control switch does not-affect the operation of the <
isolation logic from the Off-Gas radiation monitors.
If CV 1534 fails in the closed position, water will collect slowlycin the of f-gas line,1civing the operator ample timo to take corrective action.
l.f the lovel-switch fails to trip on low level in the loop seal,. CV 1534-can still be closed using ihe handswitch.
Ai r E iector Steam Pressure Control Valves Interlock wi th Air Fjector Suction i soLglion Swiich HS-10M An interlock was provided on control room swi tch HS 1084 ( Air Ejector Suction isolation) which pariially closes the ai r ejector steam. supply valves (PCV-1242 :
and PCV-12431 when ihe swiich is in the CLOSED position (See figure 13).
This i nterlock was added to provide a means for preventing a sudden air ejector :
flow surge when the ma'n steam lines are repressurized following an isolation.
Provention of air ejector flow surges insures' that the water loop seal _ on--
the o f f-gas discharge line is maintai'ned. - Wi th the ai r ejector steam supply i
valves partially closed, the surge in ai r-ejector steam flow which occurs
(
i f the main steamlinec are rapidly repressurized is not great:enough to_ cause loss of the loop seal.
Installat ion of a Swi tch to Bypass the " FUN Unde" -I nterlock on the Primarv i
Containment Purge and Vent Valves A key locked switch was installed to bypass the "RJN Mode" : interlock.on the primary containcent purge and vent valves,_ A0 2377, AO 2378,; A0_ 2381, A0-2393 and A0.2386.. These valves are normally interlocked ~ with~ the nude ' switch such that they cannot be~ opened when' the reactor ?is 'in the FUN ModeJSee:
Figure 14). Opening of these valves is necessary foriinertingTor do-inerting.
l
~
The bypass will be used only when inerting or de-inerting ihe primary.
containment.
I t in no' way affects a group _2 isolation signal to the purge and vent valves.
Modi ficat ion o f the Renetor Reci rculat ion Svs tem Cross-Tie Valves-P.0-65A and B Openine Circuit The " seal-in" contacts were removed from the: opening circui_is o f the 7 reactor s
reci rculation sys tem crosst i.e valves LD-65A and AD-658. This allows - thei operator to open the valves 'in small incronents and thereby prevent. sudden flow i ncreases.
4 The LPCI System interlocks to the. cross-tie valves are not affected _by ithis-
^
mo di fi ca t ion.
e y
+
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e-n,
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3 LL t.a Addition of Test Jacks to Plant Instrurrents Test jacks were added to plant instrumentation associate'd with the reactor
+
protection system and emergency core cooling system to~ facilitate testing-and calibration.
The test jacks are wired-in parallel wi_th switch contacts:
and are mounted on local junction boxes to provide access during testing, All of the test jacks are capped when not in use and are identi fied wi th permanently mounted taas inscribed with the associated instrument' and switch =
numbe rs.
Test jacks were provided for the instruments listed in Table 1.
Addi t ional Peactor level instrucentation Addi4ional temporary reactor level ins t rumontation was added _ to existing plant instrumentation to allow testing of a prototype water level trans-mitter. The prototype level transmit ter was installed in parallel with Feedwater Cont rol System level iransmiiter 6-52B.
A di f ferential. pressure transmi tter was installed in parallel wi th level i ns t rumen t LITS 2-3-598 to moni tor - the Yarway level column di f feren tial, The output of the two addi tional level instrunents is sent to a high speed six channel recorder (See Figures 15 and 16).
The instruments will be removed at the conclusion of the test.
the A r E iocior Suct ion Valves isolation.
Addi tion of a Seal-in Ci rcui t for i
(,
Control Circuit,5
~
A seal-in ci rcui t was added to the ai r ejector suction valves isolation con t rol ci rcui t.
The modi fication included the addi tion of.a GE HFA relay at control room panel C-07, and the addt tion of a reset pushbutton on the bench board of C-07 (See figure 17).
The operator must' now manually reset the isolation after the initiating signals are cleared.
An annunciator (7813) is used to alarm the seal-in condi tion. - T he addi tional components are highly reliable and are the same type as those used in the reactor protection system.
Reactor Buildinn Vent Fan Indication Additional indicating lights for reactor building vent f ans were provided on t he-control room and local panels. The original design did not provide indication for vent fans' that _ were tripped by local magnetic contactors.
Red indicating lighb were added for the following uni ts:
V-AC-10A V-AC-108 V-AH-4A-V-AH-4B
~V-EF-24 V-EF-28 V-EF-10 Core - Flow Dist ribution Measuremonis Following fuel loading and prior to installation of the vessel head, _ the j(_
flow distribution through selected fuel assemblies was measured. - The flow test was con 8ucted at atmospheric pressure and ambient temperature.
Individual
~
fuel bundle flow at the _exi t of the selected fuel bundles located symmetrically in the inner zone of the core was measured with a specially fabricated flow-
m.-
r-k-
t t=
-- 8.
s
~~[y.~~
l treasuring device.
^
Flow distributions for -three core flow rates with symmetric operation of -
- the rocirculation pumps were determined.
A completo.doscript ion of-.the test and test results is' given in General Electric Licensing Topical-Report ti tled." Core flow Distribution in a Modern. Boiling Water Reactor 'as measured-in Monticello (NEDD-10299) "
6 A
f f
s a
4 4
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s v-F e
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a i krm
-w
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- -i= - -r
? --- +
-wn
-, e.
i:-
.,p
'l I,
from Reactor k
Vessel Vent 4
i Change Vacuan B, uker f
XDV-2 XDV-3
(~.
Ch a
t k
A h A VN v%
CV 2371
- CV 2372
'l To Drywell.
- n Equipment Drain Sump i
Installation of Vacuun Breaker on the Low Pressure Side ~ of the Reactor Vessel Vent Figure 1
.k-
I.Q t
Concrete Wall-
/
/
x x
Bracing
/
/
(S)23-91A (S)23-91B { 'g}S (L)23-91 A (S) 23-9 LB s
(
MM MM r /
t i
1/8" Orifice
/
[3gvised Installat ion Original' Installation b
Remount of HPCl Systan Level Switches Fi ure 2 C
]
g;
.t Contacts close when any one of three feeder breakers to Core Spray Ptep Motor bus i s closed.
a
(
21
-.T Core Spray Inboard Injection 14A-K4A 14A-K3A
?
Valve Cont rol Swaich Contact s-
' ' ~
- - 14 A-51 A Contacts closed closed when switch is closed.-
2 av 1 le$1 Core Spray Punp Rmoved Motor bus.
o 14 A-K 10 A Contacts clocec on Core Spray Autamatic Initiation
(
Contacis close when reactor pressure _.450 psi.
14A-K9A 14A-K98_ _
e 14A-K13A Core Spray injection Valves b Open Relay (opens inboard and ouiboard injection valves).
g Core Spray injection Valven - 450 psi Interlock Figure 3 b
,4 i
u

' l,
+
8 r
r l
PS17-3"ED Supply Steam DG i-LO 2078
[
h -)
l l
I, for!
s 1
3 min, afterlPipinE J.
~l LO 2078 i s
[
RCIC Pump l Change) closed.
Drive Turbine L0 r
~
1" Vacuum c--
Breaker Steam Solenoid Exhaust Valve to Torim R4 V "HE e
(
PS13-72B Vacum Breaker Connection BB-F1-2
-I F -9 l Contacts Close When TDPU relay Contacts _._
I
[ ""* ' E 2 * *
~~cl s whet-125 VDC MO 2079 i t~~
~~/- 130 sec. TD close~~
~~closed, before drop out.~~
TDPU Vacuum breaker BB-F8-2 riel y valve s 1 n id l F-10l flectrical Charmes i
RCIC Eystem Exhaust Piping Vacuurn Breaker i
Figure 4
)
~
4 h
t Moisturo Separator
~ ~ " ~ "
High Level
,286/T Moisture Separator O - >e Trip of Turbine Lockout Relmy Moisture Separatori Drain Tank High U
,
~~r l~~
(~
Level Alarm T
g a-j' T
Dump. Valve
?
Controller Control Valve i
T Controller i
f T
J LM _
s Dump Valve.
(to condenser)
_ Control Valve-(to HIP heater).
. g x
/
a" MOISTURE SEPARATOR CONTROL SYSTEM (Original) r Figure Sa.
!!oisturo Separator' - Moisture Separator Drain Tank i* Difforontial Pressure cwiich.- Opens dung-valve -on High Differential preccure.
r-----------------------1 b.
l I
l l
Moisture l
Separator p
Moisture Sep l
High Level g-
' 286/T switch opens I
dump valve g
and trips Tur bi ne l
Lockout Rela
-l.
i L
(10 cec.
"6 I
time delay I-I on turbine l
I trip) l l
Moisture Sep.
l Drain Tank
+
High Level l
L 5
Switch Alarms l
I n '. SI
l l
[
l and opens Dump}-";
~~Par at o-j' i~~
va i v m, l
l Drain Dun >p Valve Solenoid de-l hnk g-Controller energizes to M
l Contrel i
I tr i p d<no r- -
l Valve H
i valve 6,I"^"[F '
~tE l
Controll er l
I T
r___I l.
I I
l l-x
~
C l
Dump Valve l
l (to' condenser)-
1 I
L _ _ _ _ _ _.
_________________J s
Control Valve (to HIP heater) l ><1
/
i' MOISTURE SEPARATOR-CONTROL S'iSTE'A (.todi fied)
Figure 5b i
2...
i 18" Main Stennline D 18" Main Sinamline C 18" Main Steamline B 1R" Main Stennline ri To PT 1176
)
/
Temporary l
Prensure l
Sensorn
-O Pn 2-134 D
_(-'
To PT 5300 X
C O
O LIemPorary OOOO Tur bi ne Pressure O
X sien seesere.-
V"lV""
PT 1209 o
O O _O: 0 3 ursine
. Temporary Control
-Pressure-i_
- Valvoa Sensors i
j' '
~~TE;/PORARY PRESSURE SENSORS.~~
a-l Figure 6 l_
o 4.-
f awt
l O
from Control Rod Drive Pump X
X To Recire Pump #11 flow Peducer flow O Indicatoi Q ' Relief g Valve Ox Pressure 7
Indicator i
i
-(':I, ORW M
I,
~
Containment
?, _
Penetration To Recire Punp.
~~12 Lower Seal Reactor Recirculation Punp Seal inject ion System Figure 7 i~~
t
. i.
.t-a 3.
Closes on Closen or hich Primary Low Reactor 2 "'
Contairnent prec= ore Water Level _
s.
23A-K23
_ S cal I r.
23A-K2 23A-K; a
23A-521 neset Relay Energizes to Close
( 23A-K23 CV 2046A d B and CV-2394A & Bi Original Control Circuit
(,
O LS-2
'S 2036 Contacic close when Steam Z
Adrnission Valve is fully open.
23A-K7
% Relay Ererrizes to Close CV 2016A 5 B and CV 2394A & B e
f"odified Control Circuit HPCI Systen Control Circuit Changen (Identical changes were made in ECIC Control Circuit)
I t
Figure
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4 It f,
i t
G t
Contaci originally used was closed for the first 5% valve travel Torque
./
Changed to Contact which is closed for ihe firat 95% valve iravel Switch e
o i
For Valve Logic details see Elem. Dia. 730E166, Sh. 6
~
m c
h Closirre Coil
-- 0. L.
&K i
l~
I l
l Modifications to Reactor Recirculation f,ystem i
l-Valves LO-53A & B, 43A d B, 54A -6 B and 65A & B i
Figure 9
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L
i I.
t i.
i l
ni 1
4'O V, : phate i
4 6
SCf!
s I
Start Relay Contacic
?O KW t
Closr:s when flow it.
Heater er,tabl i ched and imp.
WWA is below lbO'f I
Differ-1}
i c:ntial T unp.
~ Controll-T j
U To lo Cornnon Grovnd Orininal /\\ir H<airt i'1;R Cent r ol C i r c u i t i
0 0 V, 3 phate r
To Ground
'q
_i p
.3
-)
$ Contactor
.. F)
. R.
oil
+ To Common 20 KW Stari Relay Contacic 6i l
ll f odifiei_ Air Httater SCR Control Circuit l
L.,
f icur e 10 r un
I s
7 (o3 r,". [ ti To Stack Djp+
t ca CV 1534 D17 - 1 1 /2" - 110 t
i r>c i
t 1
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l 12 5" l
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/ / / ///////
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j Off-Gac Loop Seal Level Switch
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Text

SUMMARY

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