ML18026A521

Forwards Revised Response to NUREG-0737,Item II.B.3, Post- Accident Sampling Sys, Re Chemical Engineering Branch, Technology Section Questions 3,4,5 & 6.Response to Questions 1 & 2 Will Be Submitted Prior to Fuel Load

ML18026A521
Person / Time
Site:	Susquehanna
Issue date:	06/16/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 PLA-848, NUDOCS 8106180356
Download: ML18026A521 (37)

Text

-REGULA'TOR r

-INFORMATION.'O'I'STR'IBUTION.S'r TEN (R'I'DS)

SUBJECT:

For war ds r evised response to NUREG 0737'tem II.~ B,3~

"Post Accident Sampling Sys" re Chemical Enginee~ing Br anchP Technology Section Ques'tions 38485 3, 68RespoPIse

'to Questions 1

8 2 will be submitted prior to fue1

load, 1

DISTRISUTION CODE: 800IS COPIES RECEIYED:LTR J ENCL

'TI'Tl.'Es '.o.SAR/FSAR AHDTS and Re 1 a ted

'Cor respondence S IZE':

'OTES'.Send ILE 3 copf es FSAR L al 1

amends

~ 1 cy'.BWR.LRG Psi(LRRIB) 0500'0387 Send ILE '3 copies FSAR L all amends,l cy:BNR LRG Phf(LE RTB) 05000388 ACCESS'ION NBR 81061'80356 DOC ~ DATE t 8'1/06/16 NOTARIZED; NO DOCKET ¹ FACILt50 387 Susquehanna Steam Electric Station<

Unit l~ Pennsylva 0%00038 50"588 Susquehanna Steam EIectrtc Stat<car Unit 2'i Pennsyiva c0~5000'988 AUTH'AhrE AUTHOR A'FFI.LIATION 4'ORTS S g Sl.~'re>>

Pennsyl v'an<a 'Power',Liight Coi REC I,P ~.NAuE REC,'I'P'I EN T A'F'FIL'IIAT'IOhi

'SCHHENCERPA ~

L'fCensing Br'an'ch 2

REC'IP I'F'NT ID CODE/NAME ACTION:

A/0 LICEiirSNG LIC 'BR ¹2 LA

'INTERNAL: ACC ID EVAL BR26 CHEM EhrG BR 11 CORE PERF BR 10 EMERG PREP KMRG >RP LIC 36 F K 'Yr A se R E P DIV 39 HU>> FACT ENG 40 I8C SYS BR 16 L IC GUID RR 33 MATL ENG BR 17 MPA OELO POAKR SYS BR 19 QA BR 21 REA'C SYS BR 23

'SIT ANAL:BR 24 COPIES LTTR ENCL 1

0 1

0 1

1 1

1 1

1 0

3 1

1 1

1 1

1 1

1 1

1 0

1 0

1 1

1 1

-1 1

1 1

RE'C I PI'KNT ID CODE/NAME LI'C BR '¹2

'BC S'TARKPR ~

04 AUX SYS BR 27 CONT SYS BR 09 EFF TR SYS BR12 EMRG PRP DEV 35 EQUIP QUAL BP 1'3 GEOSC IENCES 28 HYD/GEO BR 30 I5E 06 LIC QUAL BR 32 HECH ZNG BR 18 NRC

'PDR 02 OP L IC BR 34 PROC/TST REV 20 R'

S 8R22 c REGAL M 01 STRD'CT,ENG BR25 COPIES LTTR ENCL 1

0 1

1 1

1 1

1 1

1 1

1 3

2 2

2 2

3 1

1 1

1 1

1 1

1 1

1 1

1 1

1

'EXTERNAL! ACRS N'SI C 41 05 16 16 1

1 LPDR 03

~g qcjg "TOTAL.NUMBER 'OF 'COPIES REQUIRED; LTTR ENCl

TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEr (215) 770 5151 HOIILtANSV. CURTIS Vice President-Engineering rL Construction-Huctear

'7'TA eeRr June 16, '1981 Mr. A. Schwencer, Chief Licensing Branch:No.

2

'Division 'of Licensing U.S Nuclear Regulatory Commission Washington, '.D.C.

20555

'Docket Nos 50-'387 388 SUS(UEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ISSUE ItT81 ER100450 F IL'E 841-2 PLA-848

Dear Mr. 'Schwencer:

This letter revises the text of PPSL's response to NUREG-0737 Item 2 I.-B.3, Post Accident Sampling Systems which was transmitted to you in PLA-798.

This response address guestions 3, 4, 5, and 6 from the Chemical Technology Section of the Chemical Engineering Branch.

Responses to guestians 1 and 2 will be prior to fuel load.

If you have any questtons, please contact us.

Very truly yours,

/r'-

~/

'N:A.. Curtis Vice President-Engineering and Construction-Nuclear cc:

R.M. Stark NRC pro/

5 i/I

Post Accident Sampling (ZI B. 3)

X 1.21 3

'Statement of Response X.1.21.3.1 Introduction

'A 'design,axd opera'tional <eview.of th~ existing.reacto'r coolan=

'an'd containment atmosphere

'sampling system was per'formed to determine i s abi..li'ty te meet %his requirement.

'The existing sampling system does not meet this requirement and there ore an addi.tional system dedicated to post-accident sampling will be installed.

This system was designed

+o satisfy all,the requirements as stated in 'NUHFG-0578 and the clarification of item ZI.B. 3.

The system vill be insta.lied and operational by fuel load.

The Post-Acciden't Sampling hays em (PAS'S) concept is based upon obtaining grab samples for remote labora'tor'y analysis, having a

minimum of operating corn pl'exities, having very little "in-1'ne" instrumentation, having modular construction or maintenance and contamination control pu=poses, and being compact in size so as-to require less shielding and to better fit into existing p'ants.

This concept results in a th ee-step sampling/analysis process.

The samples are obtained via a

Pos't Acciden..

Sample Station located adjacent to.secondary containment.

They are

+hen transported to a sample preparation a=ca which consists o::

a

-we-.

chemis rv laboratory wi.h the capability to perform the required chemical analyses as well as prepare the samples for radioisotopic analysis.

he final step involves transporting the samples to a counting area with a suf icien~ly Low background to permi+ accurate gamma-ray spectroscopic ana1ysis-X.1.21.3.2 Description of. Sampling System The underlying philosophy in the design of the sampling system is to meet the requirements of item II.B.3, to minimize exposure by minimizing the required sample sizes, to optimize the weigh of the shielded sample con.ainers in order to facilitate movement

+hrough potentially high-level radiation areas, and to provide adequate shielding at the sample station.

The system is designed to provide useful samples under all conditions, ranging from normal shutdown and po~er operation to post-accident conditions.

The PGID for the PASS is shown in rigure X-.'1.21-1.

The equipment includes isolat'ion and. control valves,,piping station, sample

station, and control panels.

X..3.-21-,3.2 1

Sample.Points a)

'Metxe11 and Drywell Atmosphe" e Provision will be made to obtain gas samples from two separate areas in both the drywell and wetwell.

The ample li.nes will tap into the containment air monitorinq -system

'('CAMS) sample.lines outsiQe

.of p.'ary containment and a'fte the second containment isolation va5.ve.

The two drywell sample taps axe on the highpoint 3ine, sampling at elevation 790'nd the midpoint line, sampling at elevation 750'.

5)

"Secondary,Con'taixment Atmosphere A sample line wi'll be insta.lied to allow sampling of the secondary containment atmosphere.

The location of this point has yet to be determined.

This sample point would be use'ful iz rletezmining.t'e post accident accessability of the

,reactor k.uilii.zg.

c)

'Reactor 'Coolant and "Suppression Pool Liquid Samples.

When the reactor is pressurized reactor.coolant samples vill

.be obtained from a,tap off the jet pump pressure instrument system.

The,sample poin't vill be on a non-calibra,ted jet pump instrument line outside of primary containment and after the excess flow check valve.

This sample point location is preferred -over the'o mal reacto" sample points an 'the reactor water clean up system inlet line and

,reci culation line since 'the reactor clean-up

.system is

-expec'+ed to zemain isolated unde" accident. conditions, and it is possible that the recirculation line containing the amp1e line may be secured.

The jet pump instru ent line has keen Qetermi~'ed: o be the optimum sample point Eo accident conditions since:

1) the pressure tap" are well protected from damage anQ debris,

2) if the recirculation pumps are secured, there is normally excel1ent circulation of the bulk of the coolant past "hese aps (natural circulation),

axd 3) he taps are 1ncated sufficiently low to permit "ampling at a reactor water level which is even be1ov the lower co"e suppor t pla-e.

A single samp1e line is also connected to both loops n the RH"-.. system.

The sample lines vill tap of the high p essurc switch instrument lines coming off the common section of the RHB system return line.

This sample point provides a

means of obtaining a reactor coolant sample when the reactor is not pressurized and a

least one of the BHR,loops is-operated in

+he "shu'tdown cooling mode.

Similarly, a suppression pool sample can be obtained from an 3HR loop lined up in the suppression pool cooling mode.

X.3.21.3-2,2 Iso1ation'alves

.and Sample Lines Containment isolation 'for %he dryvell a'nd wetwe11 gas sample lines,are:provided by the existing CARS sample 1ine isolation valves.

'The jet pgmp instrument sample line, containment isola<ion is provided:by an existing isolation valve and excess Slow check.valve upstream o', he sample tap.

All gas sample 1ines 'f am 'the,sample taps 4o awd.including %he first flow control valves are seismic category

3. except fo" the seconda"y

,containment sample line vhich has no control valve before it

-.enters the samp1e pa'nel.

The sample lines from the BHR system are seismic category 1 through both system isolation valves and a f3:ov.ms't-i=Mng orifice.

The sample line f om the jet pump

,instrument.

system is se smic category 1 to the flov control/'isolation

-val've.

All.containment.iso1ation valves upstream of the sample taps can be;overridden,f:rom the cont"ol

..=.oom A11 isolation end con+~ol valves shovn in Fig. X1.21-]

which.ave,within the Q boundary

~axe contro'11ed

.by a single

,permissive,switch in the.contxol zoom and individua11y 'con'trolled at, the sampling -control panel located adjacent to the samp1e station The solenoid isolation and control valves which are part of the

post

accident sample -system to the Q boundary vill be environmentally guali'fied-.

The gas aamp1e lines are heat traced to prevent precipitation.of 'moisture and the resultant, 'loss of iodine in the sample lines.

X.1 21-3 2

Piping Station The piping station,,which is to be 'installed within the reactor building, includes sample coolers and control valves which determine the liauid sample flow path to the sample station.

The

.location for the piping station is shown in iguze X.1.21-2.

Coolinq water,:will come 'from th Beac"oz 3uilding Closed Cooling

'Ma'ter System.

X.1.21.3.2.4 Sample Station and Control Panels The location of the sample station, control panels and associated equipment is shown in Figure X.1.21-3.

The sample station consists of a wall mounted frame and enclosures.

Included within

'the sample station are equipment tray".whi"h con ain modulazized liquid and gas samplers.

'The lower liquid sample portion of the sample station is shielded with 5 inches of "lead brick, whereas

'the upper gas.sampler has 2 inches of lead shielding-he control instrumentation is installed in two control panels.

One of these panels contains the conductivity, and radiation 1evel zeadouts.

The other control panel contains the flow, pressure, and temperature indicators, and va "ious co'n""o1 valves and switches.

A graphic display directly below the main cont ol panel which shows the status of the pumps and valves at all times.

The panel alamo ind) cates the eel ati ve position of the pre sure gauges and other items of concern to the operator.

The use of this panel will impzove operato=

comprehension and assist in trouble shooting ope"ations.

The various sample lines and return lines enter the sample station enclosure (which is mounted flush against the secondary containment wall) through the back by way of a penetration in the steam tunne1 wa11.

'X.l 21 3 2 Q.a Gas Sampler The gas sample system is designed to operate at pressure ranging Xzom sub-atmospheric to the design pressu"es,of the p=imary containment one hour after a loss-of-coolant accident.

The gas samp'les,may

.be passed through a particulate filter and silver zeolite cartridge for determination of particulate activity and total iodine a'ctivity by subsequent gamma spectroscopic ana1ysis.

A radiation monitor is mounted close to the "ilter ray to

.measure the activity.buildup on the ca"t"idges.

A1"ernately, the sample flow bypasses the iodipe sampler, is chil'led to remove moisture and a 15 millilitergr ab samp1e. can be taken o=

determination of gaseous activi y and for gas composition by gas chromatography The gas is co1lected in an eva'cuated vial using hypodermic needles in a manner analogous to the normal of=-gas

~

~

.sam,p'1'es

.'-.Qh.en,purging,the drvw.ell -an"d:,we+.we'1'1 gas,samyl.e

.lines

".to;obXain ~a.,zepzeaenta'Mve,+amyl~,

'.the

.'f1ow.is;re'tu-ned 'to.the wetwell: 'however, during purging of the secondary containment line and when flushing the sample panel li:nes with air or

.nitrogen, flow is returned to secondary containment.

The sample

.sta'ti:on -:,Zex3:gn,a'11ows,for.,3.ushi;ng

.o t'e 'anti e:sample:panel

'~leone '.from %he -~Your >pose:%ion gael'ector 'value 'through""the needles

- >4Th:eat:-her.-air, ni;grogen 'x>r.the gas "to',be +ambled

'This

'capa'b'ili'ty;wi11 mix.im'ize any possib3.e;cross con'tamination 'between t he var iou s sa m pie s.

X..1-,21-3..2,4.;;b;Li,g.uid Sam pl.e r

'The liquid;:sam'pie system is.designed 'to operate at pressures from 0 to 1500 psi.

The design purge flow of 1

gpm is sufficient to uaaintain,,turbulent flow in.the sample line and serves to

.;all+via'te cross ~ox'Eaminati'on

~be~~ween samples, The;pu..ge

.flow is waturned <o;t'h.e muppress'ion -pool

'The 3xqui3;sax pliny ";system, is d'esigaed 't.o.@11'ov zeu ine demineralized

'wa 'er 'Clashing of the

.system moines from a poin't between the two,coolers in the piping ata'tion 'through

.'he.sampling -needles.

-:Using the hydro-'test

.connecti.on;.w'hich.is x>ups'ide.the;samp'le

'panel, iX is.also poss'le to backf lush all the liquid sample 'lines through the sample tap poinC..~his 'will 'a'liow.'for:clearing af p'lugged Zines.

A11

-'3..'iqux'6 'saw",pl'es 'are 'take'3.3.h"tA) Z5.'mi11"li er septu bot'ties

..mount+'d -mn;sam p'Bin'g,needles

.'Xz "che 'no,.ma'1 'lineup, the sample

flows 'through

':a conduc+i'v'4p ~cell

.{'0 1;to '.1'0'00 'micromhos j'cm and

'-throagh ~ !ball erg ve Jo

~c'.

ou+ 'to 0.10 'mil'li.1'iter 'volume.

After

Liow 4'hrough 'the.sampj.e,pane'1 i ~ta'bl" shed, the ball valve is

@o'tated

-'90'~.and,a;sy."in"e,

.connec" ed

• o a 1ine external to tne pane1., '~s ',used 4o "f1us'h

.'h'e samp1e;plus:a measureR volume o.

diluent:,{genera'lly 3.0 milli3i'=;s) 'rough

.he -valve and into sample bottle.

This provides an initial dilution of up to 100:1.

The sample bottle is contained in a shielded cask and remotely positioned on the sample needles "h ough an opening in "he bottom

,of the;sam,pie -.enclosure.

Alt:em'a tely,, the sample can he diverted

',<hroug'h a '70,:milli'liter'bomb 'o 'obtain;a,3.a',-ge;pressurized

'volume

-'gh'is '7'0,",millx1iter 'volume can be ci'rculated and

depressuri;red.3;n<o:a."gas.".sampling:chambe A 15 mil'liliter gas sampl'e.;ca'n

".then.be'obta" ned ~'h'rough z, hypodermic needle '.for gas

chroma'tour-.,aphic @nQ;.radio='so.opi'c;analyses v'f the dissolved gases

~associa'+ed

',:wi+'h.the

',70 >illiQ:.-iter "3.iquid volume.

'.Te~;millil'iter

.:al'iquots:;e'+ <<ha's degassed,3.'iqui'8

--can 't:.hen be ".taken,.for.off-site

-'gor ~on'-,,s'i te:depen'6iqg

.;on ';act'ivity 3;evi l) ~na3p'ses which 'requi*re a

ge3;atively ".large ',until'used.'sample

'This 'sample is o'btained

'xemoteQjr <<ziisig the "3.arge -vo1ume cask rand;cask =;,positioner through

--..neeM.es en %he:faun'Bezel'id'Sf '~'he ~am~le "station enclosure.

g 2,.'2l -3 ~2~'4..a ",Sa'm.pi'e ',St@<~on 'Venti'la~ion

'The,'.sa~mple."st'ation.enc'losure waled,'be vented to seconda ry

con'tainment

v~a the;maxn,steam li.ne tunnel.

,Vent'i'lation is

>motivated;;by'!diKerzz4i.'a1,"pressure.'between,t'e turbine and reactor.,huis'drags,~he

-::ven~iQatwon,ea '.e;equi'red for heat

- >';.-emcv+1',4uxing ';;op~<a'ti on'ws m'bout <<40.sc'f m.

";The -ven~la<ion duc.

,;ms:;siced.,"4;o

.Bless.,-t'han,"2'QQ

..',s'cpm

>.a'.t 2/4:;i,nch ',oowa~ er diffe ential

.;pgessuze

.. ~wh'en" %he:.en'cZ'osure ws 'ep'enei3 'for ':mai'ntenance.

'Standby saba -'.X1ew vwZ12:be ah'out '3;.saf m;.~n'0, "can ',be ',reduce'd "by 'taping all

0

~

open'ings.

A pressure gauge is aC'"ached to 'the sample;station

'enclosure to,moni'tor the pressure.differential.betveen the enclosure and the general sampling area in the turbine building This vill assure the operator that airborne activity in the sample enclosure will be svept into secondary containment.

X 1 23. 3,2.'4 d.Samp1e Station

'Sump The sample sta".t'ion is provided with a sump at the bottom of 'the sample enclosure vhich will collect any leakage within the enclosure.

This sump can be isolated and pressurized, discharging into the sample sta ion liquid return line to and

'hence into the suppression pool.

X.l.21.3.2.4.e Sample Handling Tools and Transport Containers Appropriate sample handling +.ools and C=ansporting casks are

.provided.'Gas vials are i'nstalled and removed by.use o'f a vial positioner t'hrough the front of the gas sampler.

The vial is then manually dropped into a small shielded cask directly fron the positioning tool.

This a'llows the operator to maintain a

distance of about three feet

~rom the unshielded vial.

This cask provides about l-1/8 inches of lead shielding.

A 1/8 inch diameter hole is drilled in the cask so tha

'an aliquot can be withdrawn -from the vial with

a. gas syringe without exposing the

analyst to the unshielded via1.

The particulate and iodine cartridges a

e removeR via a drawer arrangement.

The quantity of activity which is accumulated on the cartridge is con roll d by a combination of flov orificing and time control of the flow valve opening.

ln addition, the deposi*tion o" iodine is moni ored during sampling using a

radiation detector installed in the sample s ation next to the cartridge.

These samples will hence be linited to activity levels which will not require shielded sample carriers-The small volume (diluted) liauid sa pie cask is a cvl:-nder vith a lead wall thickness of about two inches.

The cask weighs approximately 65 pounds and has a handle which allows i to he carried by one person.

The 10 milliliter undi1uted sample is taken in a 7'00 pound lead shiel'ded cask which is transported and positioned by a four-vheel dolly.

.The sample is shielded.

by about 5-1/2 inches of lead.

X,.3..21.3.2.4.f Sample Station Power Supply The PA'SS isolation and.control valves, sample station.control "panels, and auxi.liary equipment are connected to an Zn'strument A"

Di.stri'bunion Panel vhich is powered

'from an 'Engineered:Safeguard System (ESS) bus.

Fglpgqng.loss of off-site pover, the HSS bus is powered from the on-site diesel generators and backed up by batteries.

The Heactor Building Closed Cooling '.Tater

System, which is needed for the sample coolers, is also poverod "rom t) e emergency diesel generators Allowing ')p~ of off-site power.

Compressed air for the,air-opera+ed valves comes from co pressed air cylinders, thus eliminating any dependence on the 'plant compressed "a.ir system.

k

,ZA1 421 %3%,3

~

0

'Descr'ip't'ion "of 'Sample 2reparati.on/Chemistry and 'Nuclea "Cou n ting

=':.Paci'li'ties After Me samples are obtained from <he sample station, they will be transported to a s'ample preparation/chemistry area.

There

'.t'heyvi.l'1 '.be -:di:-3.'uted as necessary

-and,a poro'private:,a1'iquo+~

'taken

.'for.'.che'iiv+1:and '-a@.'o'otopic;,axaZyses.

-The -aiiioi'soCopic

ana~si.s."v511

.be done.an <<a:aepa a'te:country

.area

"-vhere

'";background -AM:a'ti'on can he kep't to,a '.minimum.

Tvo.di.'Herent facilities will be available to plant personnel to perform the

,above tasks.

The,primary facility,is the.existing chemistry 3.aboratorv:an'd 'counting.room <<which 'is at elevation 676'>,the ground '3.eve'1. o'f <he contro1.struct:ure.

'A backup.sample

preparation/chemistry area and counting room will he built as part of the Emergency Operations

?aci1ity (EOP) which is located

,2500;feet.south'-vest of 'the,cont=ol:structu"e.

Xn addi+ion to

these

'.ov-x3:"te'.a~6 ';near-'.si'te 'Saeilities, which

<<a:re i:n tend'ed o

kam63."e.',the";-aas.aacples

'an'd.'~'he diluted "-Iiquiii samples.,

prior zrrangenents

-will".be;ma'de =vi h an- 'independent

.off-..site,.laboratory for aaa3ysis

'o'f the undiluted '10,m'1-liquid samples.

X..'.1 21-'3..3 1 -

'Qn-Site 'Chemis'try.'Labo<<ra'tory and Coun ina Room

'he,:p1gnt

--sh~ie3:di<<ng.study,.:resu'its, presente'd in -Section 'X.'l. RO

~ 3

s'h'ow 4:"ha% ';fo3:novi;ng;-zn z'cci'd~n>>,

.>>..i:e ',chemi<<s~""y laboratory will be

'Z'one ZZ '..area

.:"(+1'Q.'0 'mR/h),.

'"Therefore.t'e -.exiztiuq 'facil.i=ies

,.vQZ 'ke ':a'ccessi'ble.zt '.least;for

',in."ermine'+ent

-use following an

'ace'iden>>.

='The mos't Cinsect 'route;betwee'n

- he sample station and

't)'ese abaci..1'itiee 'is:t'h-ough:a eas -o~ >>'he <u biwe building which

~should:be,'Zone

'X,areas

(+'.l5.m3/h.)

" o1'loving a'n 'acciBen't.

'The chemistry

'1'a'bora ory ~s oz-'vi1i',be:equ"-pped

+o provide he

'capability-'tg.h'andre t'e ga's 'samples.wed the '0,.1 nl diluted liquid samples.

The maximum activity of these samples will he 0.7 Ci and 0.3 Ci, respec ively, using one-hour decay and the f actional releases of core inventory specifiea by NUTMEG-0578 (see Sect;i;on X.-l;2i..3.5)-

'The 3:aborm'.tory w'i'll;maiwtiin a dedicated;inve'ntory o'f 'i<em's such

.as 2'ead ":-bri'cks;fo;:shie3.'ding::gas,s y.,ingesgloves, reagents for

.dna'l.y;ses, wtc, +hi.'ch;wi1'l:be nee'd,ed

.'in:case.of an accident.

The

la'borat.or@

.-"~.i11 'be.:.equi@pe'.d 'wi:th a.gas;chroma'tograph, "pH meter,

<<condncHvi'ty,zretzz

<<tux'.biBiaete'r 'and..o'ther in trumentat'ion needed Xo,perXore Che mequ'i'"ed.analyses.

'Zhi's equi'pment

however, nay

-sit

. be

- de% ca'+ ed.=exclusiv e'ly *No:post-..'a'ccid'en't;anal'ysis.:Supplied

,air,-pr-- e1'f-.con'tai'ne'd;breathing "ma'sks wi'll 'be ava9:la'ble in the

event-,.'i'.".

hj'gh a'cttviCy.'";leve1s in, !the oentila ticn supply or

- ",abaci'derita&"~pill's '<<z "",the:Za'.ho=a

.o.= y.

'~The ~>x~'sting;:coun"tieg 'Xa'ci3i.','loca'.te'd.-'ad jacent, 'to the -chemistry

'"Za'bora'.tory a*s-,we1'1 equ5:,pped "Po.ha'nile

'he,;ga'm'ma spect=a a'nalyses

,+equi'red

.for '.post.-;acct;dent;samples.

<<The, coun>> inq:room is

..eve:,pped swa'th <wo Ge -('L'i);d<<etec o=,s vi>>h -.fou.=,.inch 1ead.shie'lds

':.:<<can'n'e'cXc.'d 'Xo;-.a:coet'pu4er

'.base'd."an'al'yzer.system.

The system has autos'tie.",me ah "sea ".c'h <and.";:i'so+o pe.-i:"e'n 'i'fica tion.capa'b 'i"..ies.

"The G.:e~'(L'i):-det'e'ctor-."aud ~sh<<e'1f -'.a'see'.m<<bly

=,'i.n ".'.Ae,.lea'd s'hield,can be

-:well m*so1+'Xe3.,mn'8.'4<<he:cap'a'b'i M<y ".',to.~urge ";,the vol'ume <<with in the s'hi eM -.vi~!h-;,,corn,pre's'sed,gas.~wi'3l

'..be,'-p.".ow.."'deD

'"'Vh.is,vi11 help

0

~

prevent atmospheric noble,gas activity released during an

,accident 'from swamping the detec+o'z

'X.1.21=3. 3.2 EOP Sample Preparation/Chemistry and Counting Facilities

The sample, preparation a~8 counting;.rooms 1aca'ted in the near-s'ite

~ OF vill serve as 'backups

-to %he:-og-si' Xacil'ities.

'The EOF is '25'0'0 'fee't from the control structure and is directly accessible from the site by road.

Travel time from the sample station to the EOZ will be less than 30 minutes.

The backup

,facilities vi11 be activated whenever the.on-ite facility becomes inaccessxhle or if addi.ional lab space or counting equipment is needed to handle the increased work load in the on-site facility resulting from an accident.

The sample p."eparation/chemistry room vill be furnished with a radioiso+ope 3.aboratory

'hood, about 10 feet of labo,ratory cabinets and

.benchtop working space, a small sink draining to a emovable

carboy, and at least a 5-gallon supply of deminera'lied vater in plastic carboy mounted on the ve11 over the sink.

The hood will be equipped vith a HFPA filter uni.

Al.hough some analytical instrumentation may

.be kept in,his "oom, i is not mean to completely duplicate hat in the on-site laboratory.

However, the faci1i'ty vill be fullv equippod to handle the necessary dilutions and manipulations to prepare samples vhich come directly from the sampLe station for c amma spectroscopic analysis.

Additional instrumen ation fo" the required chemical analyses vi.ll be brough from the on-site 'labo"ato y as needed.

'Chemical

reagents, glassvare and other miscellaneous

.eguipmeni will be stocked in the facility.

A supply of lead bricks vi11 also be kep+ in this room fo'r use as te-.,porary shie1dirg..

A lea"..

brick cave for storage of samples vill also be provided.

The EOF counting room vill contain as a

minimum a high resolution gamna-ray spectrome+er system.

The system will be capable of characterizing and quan+ifying

".he gamma activi.ies of reactor coolant and containment atmosphere samples.

The intent is to make this system simila to the on-site.sy-tern.

The EOP will have its ovn diesel generator vhich will be capable of supplying the electrical pover needs for the facility during loss of off-site pover.

X,.l:21,.3-3-3 Arrangements fo" Off-Site 'Analyses A.key pa"+ of t'e

'SSES approach to post-accident sampling is the establishment of. prior arrangements with an off-site independent laboratory for confirmatory and supplemental analyses-The

capability o. the off-site laborato"v vill also

.be used

+o.mee+

the requirement fo" chloride analysis.

The eason for.using the off-site laboratory for chloride and as a backup fo'r other analyses is to prevent having to handle and analyze undiluted coolant samples vhich may have activity.levels in the curie per milliliter range.

The on-site and EOF facilities are no designed to handle sources of this magnitude.

The analyses o.

undiluted samples can be done in a safe=

manre" by laboratories vith facilities and personnel specif ically built and trained to handle high-activity sources.

The Xo13.owing is a description o

0 the,signiXican't features being eguested

.of the off-site

l-abor.a.<or y

a)

A:formal mechanism wi11 be established to allow for

.initiation of post-accident services at any time

{24

'hours/day).

4)

Rritt,en procedures wi'l1 be established.,

con rolled, and maintained for each of the analyses described in Table X.1.21-1.

The analysis procedures must be qualified for use

.at the activity levels given in <he table.

This requirement

may 'be satisfied by,referencing

%he 'appropriate literature,

'by;ca3;cu1a'tions, or by undertaking a testing program.

c)

Laboratory equipment and facilities for the required analyses

.must be available

~ and ma'tained in working order

~u'ch 'that.and]:yses may be;completed

.within 24 honrs

.o th receipt.of %he sample.

d)

Prove.sion will le made "or the practice or exercise of each

.:aspect of.the,of'f>>si e analysis work at the option of the

utility.

-e);Eauipmen+

wi11 be available for -he timely transmission and receipt of infer.:ation an6 zesu'its (telecopier an3/or telex) f)

'The la'boza<ory w'll be operational for,at least chio ide analysis

.by fuel. 1oa

X.1. 21.3. 4. 1 Sample Collection and Transport Procedures After a decision is made to obtain a sample, the designated sample station operators (2) vill.proceed to he sample station with %he necessary equipmen Since a11 the post-accident sample lines (except for the secondary containment atmosphere) tap off-lines which are isolated following a containment isolation signal.,

the sample station operator must confirm with the -cont "ol room that -he necessary isolation valves a=e open.

(A telephone extension to the control room will be installed close to the sample control panels for this purpose).

The control room must also activate the "Acciden+

Sample Station Permissive Svitch>> to allov tho sample station operator control

.o'~ <he '"isolation and con+rol valves>>

vhicn are part of the post-acciden.

sampling sys+em.

After.svitching the "Baster Shuto'ff Valve. Control>> to the>>open>>

position, the operator is ready 4o opec the valve(s) cont"oiling flov from the desired source to the sample station-After opening the necessary control valve(s),

+he operator goes to the

'"sample station control panel".

This panel controls the valves w'hich -are part, o'f the piping station and those in the, sample station enclosure in the turbine building.

Po1loving a,series of presampling checks and procedures ncluding:

adieu tment, of the enclosure dampez to insure adequate

cooling, checks of demineralized wate and nitrogen supplies, flushing oi'ystem vith deminera1ized va ter, draining

+he trap and sump, etc.,

the system i.s ready for obtaining the sa..ples.

X.1.21.3.4.l.a procedure for Obtaining Gas Sample A standard 14.7 milliliter of -gas vial is placed in the gas vial positioner and inserted into the gas. port, on the fzone of the samp1e s'tation.

The desired sample location is selected by switch and. the gas is circulated until the sample lines a

e flushed out vith the gas being sampled.

The vial and a small volume uf tubing emains unflushed; howevers the vial and th s tubing volume are then evacuated.

The sample is then dravn into the vial hy pressing and holding a pusnbutton svitch.

Tf cross-con'tamiration is suspected due'o incomplete evacuation of the vial, the evacuation and fillsequence can be repeated using ai=

.oz,nitrogen flush before taking t'e final samp'le, or 'the sequence can be repeated wi h the desired sample

'gas until the operator is assured

that, he has a representative sample Following an air or nitrogen purge of the sample lines, the gas vial oosi+ioner is then removed "from the port and the vial inserted into the gas vial cask.

The length of the vial positioner allovs the operator to remain about three feet from the -vial during this opera~ion.

The cask has a 10-inch carrying handle and can be easilv car ieQ by 'one person down the stairs in the tu=-"i'ne building to "he

,chemistry 3.aboratory.

~

0

,X 3 21.3.'0 1

',b 'Procedure Zor Obtaining an Iodine.Pal:ticulate

'Sample The desired filter cartridge(s) are placed into a cartridge retainer which is placed into the gas filter drawer.

This draver m1iRes ',into an,opening in the 'front.oX the sample station enclosure

'The:appropriate critical orifice is also chosen and

.-palace'd.in 'the car ridge retainer.

'This;vill determine the flow rate through the sampler and thereby con'trolthe amount df activity deposited on the filters.

The operato then selects a sample J.ocation and flushes

+he sample line except for a short piece of t'ubixg goi.ng 'to <he sample Braver.

However,, this line can be

'flushed vith aiz or nitzogen prior to samp1ing if cross-contamination between samples is suspected.

ln addition, as part of the normal sampling procedures, this line is flushed with air zz ni4rog'en after completion of each sample sequence and should Wherefore >e 'Xr+e of contamination for 4hz follzwirg sample The operator has

%he option of.us'ing

.an au'tomatic timer to obtain

.samp1es ~ith col1ection Cim es between 0 a nd 30 second s o c o f manually 'timing the sample for longer collec ion times.

Afte" starting the sample 'collection secuence, the operator will be able 'to.Xollov activity build'up on the filtecs by observ'g the radiation level readout on the control panel from the probe inserted 'next to the caztz3.dges in the gas sample panel.

After sample collection is:completed the ca= "idges a=e evacuated using ~he vacuum from the gas pumns and. then 'flushed with ai" o=

mitroge~ 'to remove the noble gases The filter drawe" is withdrawn and the cartzi6c'e e.aine=

with fil.ers is plac=d in a plastic bag The bag as then closed, and depending on the measured dose rate., i4 is carried by hand o= attached

..o a pole and carried to the chemist'zy lahorato=y.

Ho shielding cask is p oviQei3 or these samples since it is possible to regula e the amount of activity deposited on them.

Xn addition, for ease of counting, it is desirable to keep the activity levels on theso samples low.

X-1-.23.-3 4 'l.c:Procedure for Obtainieg a 3ilu ed 'Liquid Sample

.A -15 milliliter sample bottle vith a neoprene cap is placed in

'the zma11 volume cask

.which i.s then placed into a positioner attached i,o the sample station suppo"t frame.

The sample needles

aCe 'exposed by pulling out the l~ead shielding drawer undec

+he sample station enclosure.

The cask -holding the sample bottle i

<hen svung into position unde the sample s'tation and he sample bottle raised into position so the needles penetrate the neoprene cap.

Atter ali;gni.ng <he proper "valves.,

the sample lines fron the selac~wii source r:hzoggh che piping 'station are flushed vi.h

.return Xlov to 'the,vetve11 Xf er "these lines are flushed, the bypass val've in the piping station i-closed

.aud +he sample flows Co the sample -sta+ion 4! rough the cal'bra eG

.volume sample valve

and back 'to the vetwej.l After sufficient flushing, the cali.,bzated valve is rotated 900 in"o alignment with the line to

'the sample.bottle..

-A,svringe Tilled with up -to l0 ml of

'Bemire=ali~ed va'te" j;s connecte".

on~.o a lime a+ "he f=on of the sample Station

-en'1 this -vs~'er is in jec+ed 'to wash the sample captuzeB i.n %he h811 valve in o:the sample bo.tie The syringe zs "thorn.remove4:,

H.13.ed,with air, re-a tached anR the air inj'ected to force 'out all vater.remaining in the line through the 10

~

~

-,sample needle and into the sample bott'le.

'The r'insing action of She xater followed 'by,the air purge of t'e 3.i'ne,shoal'd reduce cross-contamination between dif+erent samples.

The calibrated sample ivalve is returned to the purge position and the.

sample

lines, from the second cooler in the piping station, th ough the samp'le valve and

.back +o the suppressor

.pool:are z'i'nsed

.witr.

demineralized wate."

'The operato=

~hen

-, etu=ns to, he.sample

station, remotely lovers the samp'le bo'ttle into <he ca.sk,

-screws a top plug with carrying handle into '.he cask.

'The cask is then carried down the stairs to the chemistry laboratory.

Although one person can carry the cask, a pole with a hook in the middle

will be available

.to allow t.,wo people t,o carry the cask more easily.

X-1-21.3-4.1.d procedure for Obtaining a Large Liquid Sample (undiluted)

. and/or a Dissolved Gas Sample standard off-ga.s sample vi 1 is placed in '"he gas vial positioner and in erted into ~he,dissol.veil gas sampling port on the front of the liquid sample panel and a

1'5 millili.e" sample bottle is pl'aced in 'the large volume sample cask-The.sample cask is positioned unde" the sample e..closu=e using a fou"-

wheeled cart.

The cask is raised into position and the sample bottle raised out of the cask and on'to two needles using a remote mechanism.

'ithen

+he cask is properly posit.'ned, the operators wi11 be.shielder!

-Crom *he sample du"ing all subse"uen" operations.

After at+aining the proper valve 1ineup, the sample lines are first f lusher th "ough he p'.'ng station and then through the sample station lines including the 70 milliliterhold Up cylinde r and gas breakdown circ u la" ion loop.

After co mple+ ing the flush cycle

a. fixed volume of the pressurized liquid is isolated a nd a

measured amount of a t=acer gas is injected.

The isolated volume is then depressurized by opening a valve to previously evacuated 15 millilite gas collection chambe The operator now has the option of either collecting the dissolved gas sample in an evacuated vial o" releasing it to +he suppression pool atmosphere.

Zf a dissolved gas sample is collected, it is handled and transported in the same manner as the containment gas sample discussed previously.

The ooerator also has the option of collecting a

10 milliliter sample of the degassed liquid or allowing it to be flushed to the su'ppression pool during 'the subsequent demineralized wate flirsh cycle.

T a

large volume sample is desired., it is drawn into the evacua+ed 3.4.7 mi1li,liter sample bottle.

To minimize cross-contamination, the system can be cycled.several.

times through all the above steps before taking the final 1arge volume sample.

The dissolved

.gas and liqu3.6 sample system is then flushed with demineralized

.water to minimize radiation j.eve'lx whi.le removizg sample rom the station.

The sample bottle is then remotely lowered

'f=om the needles into the shielded sample cask which is lowered or, the ca=t and pulle~

out 'from under the sample enclosure.

A lead 'pl'ug is then

".inser.ed in the opening o

the cask and ~he cask can be easily moved to the eleva+or in the control structures using the positioning cart.

By using this eleva or no steps are

.encoun'tered when moving the cask 'om the.sample station to ground 1evel.

The,shielding s+udy results (X.'1-2Q.. 3') indicate

~

~

that this.elevatpr.should be accessible from a ra'diation level standpoint

'Xz ca'se of loss of off-site power, 'the e1evator will be out of service since no emergency power is provided.

However, the uncliluted sample is only essential for dete mining the chloride concentration which is not required until four days

,.after;sa,mpling, This,wi3.1 allow a, reasonab3.e time or the re toration:,.of o'ferrite power

'However~f a'er two.days -off-si'te power is no't resto"ed.,

a-rangements cd be made to lower the sam@le casa from the turbine opera.'ting loor to ground level through one of three open hatches.

Since the undiluted sample is to be sent to an off-site laboratory., prior arrangements will be made to:ha've a shippjxg container sent from the off-si"e laboratory o" have one =available on-site.

The current intent is to have several shipping containers built which will hold the large volume casks, thus avoiding the exposure which would result from trying to t-.ansfer the sample from the sampling cask to another container.

X-l.'2'} 3

'4: 2 Chemical/Badiochemica1 procedures X.1 21.3.4.2 1 Introduction The 'Post Accident Sample System (PASS) proviDes,a,means o f obtaining primary coolant, suppression

pool, and primary and secondary contain ent air samples for radiochemical and chemical

'anally, is ollowing a majo= reactor accident.

Because o" the ektwemely hig'r. radioactivity levels associated with extensive

'"fuel damage, the PASS and its auxilia"v su~po=t was developed with the phi1oso'phv of 'prove"..ing the capab'ity of ob.aining the

.necessary samples and of pe= arming on, a t mely basis those

analyses, as regui-ed, for immediate plant needs, or as defined by '.regula, orv zeeui=enon;,s.

P=ocedu-es an".. arrangements w'l be established

".or shipping samples o facili".ies having the experience and eauipment appropria.e "o performing detailed and accurate chemical analyses on multi-Curie level samples.

The analy'tical procedures chosen will satisfy the philosophy of performing only those analyses as re<quired fo" opera+ional

'support, o+ ninimizi'ng 'pe sonnel.

expo u"e and contamination

.hazards,,

and of depending upon outside analysis for xtensive analysis an>3 3.ong-range operationa'eeds.

Tests we"e pe" formed

by General Zlectric to assess the e fec s of high fission product levels on che.suggested ana1y~ical me ho" s.

The tyne of fuel

.damage.associated with the release of megacurie auan'tities of iodine and other.activities, also has the po.en'tial fo releasing ki'logram,guanti ties ~f stab1e or vary lang lived fission qxoduets.

'I< is conceivable that he primary coolant mightctxntain

,3.:0-20

.'ppm

=.cf iodide and.bromide..

Also., the =elease ef a major Xractaor. "o'he coze inventory of cosim

.and rubidium may sligh 1y raise the primary.coo1an+

pH.

Such releases will also

cause an inc-ease in +he coolan conductivi y.while radiolysis of the water will probably contribute o the formation of low levels of hydrogen peroxide.

Depending upon +h concent"ations,

+hese

,axe a11 possible analytical interfarences

'<<ith the reguired aral~sis.

0" ~here,, 'e 'odiie/hro-~>e in.e

.e=ence with +ho

.chlori.d~ wroceduze is probably he most severe However, since t,'he requirement for ch'loride analysis ~ill be satisfied by

.sampling

'+he samples to an off-vite 'jabora erv, the chloride 12

~

~

procedure, being.proposed for the on-si+e laboratory is on'ly to

.obtaiz a rough.'upper 1imit. The eftect of radiation 'inter'fe}ence have been-generally evaluated and are summarized in Appendix A.

X.l 21-.3.4 2

2 Sample Preparation

'All,:sample bottles, iodine cartridges, etc,. vill.be 'numbered or

oth'er;vise identi'fied 'prior 'Xa saxplin'g..'Lis ~vj:ll eliminate unnecessaTy:exposure as

.a resul of handling.hijh '3.evel +ample..s for the.purpose of attaching labels

'A central.'i.zed logging system vill be developed to keep track of sample aliquot identification, dilution factors, sample Disposi ion, etc.

'I.iquid samples vill be taken at the sample station in septum

+ype bottles

.and transported to the analysis facility in lead containers.

Sample aliauots are then taken from the septum bottles for.analysis or further dil'ution.

Aliguotina and

<rans er vil3. be performed using shielded containers, o" behind

=

lead brick pile.

Calibrated hypodermic syringes vill be used foz aliguoting 'e higher activity samples.

Tongs o-oth..

holding/clamping devices vill be available for holding the sample bottle du=ing the trans'fer and dilu:ions to reduce hand and body exposure.

Unless prohi'bited by ~he intende~d analysis, di'tions vill be done using very Dilu+e (about 0.01M) nitric acid as the diluent to minimize sample plate-out problems.

Peact or coollan activity lev e1s on 'the

'or":e r o'f I to 3 Cu ies per gram vous eauire a dilution factor of lx10,,or larger, o"

gamma ray spectroscopy samples.

As an example,

a. typical series of dilution'igh-t 'be 0.1 ml (100 lambda) addeV. to 10.0 ml at the sample station, folloved hy further d'lut'ng of 0.1 ml to 100 ml in the laboratory.

An aliquot of 0.1 ml vould then be

+aken from the second dilution for counting puzposes.

Gas samples are taken at the sample station in the same 14.7 ml septum bot le used in the normal offgas sampler.

A 'ead car ier is furnished vith a small hole at the septum end so tha a gas sample can be vithdravn from +he carrier.us'ng a hypodermic syringe vithout having to handle the bottle.

Samples taken from the gas sample bottle vil either he injected into a gas ch omatograph for analysis or used to dilute the gaseous ac'tivi,.y for gamma spec.voscopy purposes.

The dilutions vill. be performed in a manner analoguous to the liquid samples.

Fractional millilitersamples can be transferred to nev 14.7 ml gas bottles vithout concern for sample leakage due to pressurization For lazger volume aliquots a

gas sy"inge hill be use'd to drav,a partial vacuum in the bottle prior.to sample trans er.

Since there is no initial dilution of the gaseous activity at, the sample station, extensive dilution may be requi ed in the laboratory.

X.1-21-3 4

2 3 'Chemical Analysis a

Introduction 13

~

~

'The chosen procedures are not;necessarily the most sensitive nor

-<'he:most accurate.

They -vere chosen prime ily cn the basis of simplicity, stability and.availability o~ reagents, minimum radiation exposure, and least likely'o cause majo contamination problems.

They have been tested for radiation sensitivity and

.are suitable S.or use at the MSS design 'basis source term of 2 Ci/gm,.and -v'here '.app1icable, vi+h 'the'esign ba:sis 0 1 ml

%o 10 m1 di3;ution at 'the samp1e.station.

Other methods may be equally, or even better suited.

At lover activity levels it may be preferable to use the normal laboratory procedures

.and equipment b.

Boron Analysis Carminic Acid Method The,chosen EACH method closely folive the A ST~~ D3082-74,

".Ma>dard Test Method.f'r Boron in Fa e, Method A - Carminic Acid "Colo imet ie Ilethod '"

The RACE procedure is.suggested because t>e reagents a'md stan'dards are available in small.

quantities, are conveniently

packaged, and can be quickly prepa"eQ It is estimated tha.

+he complete analysis, including

.reagent preparation,,can be performed in 40 minutes.

This method

-~as tested to be satisfacto=y fo" use at the maximum expec ed activit'evels.

The analysis is designed fo= bo"on

.concentrations iz t'e ange

'o..

0 1 to 10 ppm of boron.

+his

@ansi~i'vi+y is.pa'rticulazly suited 'to the sample s.ation's 0.1 to 10..0

-ml.dilutions.since t'his cor"esponds to a "ange of 100 to 1000:pm in the undi1uted coolan-.

'Chloride Analysis Tu=bidime='ric

~".ethod (see also he discussionon conductivity)

The chosen method

@as developed by the General Blectric Reactor Chemistry Training group.

The procedure is very similar to a

HACH Chemical Co.

procedure, "Turbidimetric Determination of Tra'ce.Chloride n Wate"".

The minimum quantity o'f measurable chloride by this procedure is 0,.5 ug

'Xf 5;ml:of the 0.1 o 10 ml primary coolant dilution is

used X'm analgsi's.,

the minimum measurable concent ation would be

.10 ppm

'Using the 10:ml;direc't prima y coo1ant sample greatly increases "t'e sensi'<iv).'ty "fez =-measuring,ch3.oride.

A one ml of aliquot of

'this sample moue

.be anal'yoked at the 0 5 to 1 O,ppm 1evel.

Tests o+

.he Ta'di~tuon.sensi'ti'vity

.of the me<bod shoved that

-activity 3.eyels conpara'bl~ to the PASS design basis

-source terms resulted in:the equivalent of 1.3 ppm Cl-in +he 'primary coolan.

for the

0. 1 to 10 ml dilu.ion,.

This was deemed

-to be insignificant, as it is belov the sensitivity limit, and nore i!nportantly interference from '+he la=ge amount of stable fission

,y-od'uct Xa'1Ãe

~o.;entia13>.associa ted,with 'the source terms vill far out-:shadow the zambia, ion e'ffect i self.

14

~

~

'Tests were also performed on the addition of 500 ug of boron added to '0 5 to 20 ug,of.chloride.:Ho interference was observed wit'h the turbidimetric procedure.

d Measurement of pH p'H in:di;cator paper, will.be used Car activity.1evels 'below 10%

o the design basis source 'terms The irradiation tests indicated that at 10% of the design basis source

terms, the color stability was adequate given only a drop of solution and less than a 5-minute exposure.

Using 'this method, pH measurements can be taken at the small volume sampler by placing a piece of "he paper into the sample bottle and.using an air ",illed syringe to.blow several approx'i.ma ely 0.1 ml aliquots f"om the sample

.valve into the bot41e tomoisten the paper.

This type of sampling approach can also be used to obtain a small sample.for possible electrochemical pH mea'surement.:Laza=

Research

Labs, Tnc.

manufactures

.a micro-pH electrode which functions on microliter samples.

This elec "ode or similar micr% probe is currently being evalua" ed for use 'at source

'term greater than 10% of design basis.

pH indicator paper can cover the range fTom pH 1-11 and distinguish differe'nces of 0.25 pH units.

At very 1ow conductivities, conductivi y itself may be +he best indicator of the pH.

Fo'r instance, at 0.2 micrcmho/cn, the pH is bounded by 5. 3 to 7. 6, which is well wi-hin the tech'nical specifications for normal operaton.

Thus,

+he conductivity sho'uld serve as an adequate indicator of pH as long as conductivity is sufficiently low that i. is impossible to be outside the technical specifications limit.

e.

Conductivity 'Measurements The.Pos+

Accident, Sample Station is equipped with a 0.1 cm-

~

conductivity cell.

The conductivity meter has a linear scale with.a six position.range, selector switch to give conductivity ranges of 0-3, 0-10, 0-30, 0-100, 0-300, a'nd

'O-l.000 micromho/cm

.when using the

.0...1 cm-~ cell This conductivity measuremen

.sy>tern will be used to determine the primary coolant o" suppression pool conduc+ivity.

During normal.operation the,BMR technical specif'cations require main,.aining +he primary coolant below:.Qn'e micromho/cm, and conductivity measurements are the primary method of coolent chemical control Conductivitv measurements are, of course, non-specific, but they

.serve the important function of indicating changes in chemical concentrations and condi tions.

Perhaps even-more important, in the case of the

'Bi<R primary coolant, the conduc ivi !

measurements can establish uppe" limi s of possible.chemical

concentrations and can eliminate the need for addi. ional analyses.

'For example, i the conductivity i" measured Co

.be 5

0 15

~

~

micro'mhoyc.m, the -upper limit on "the.ch'lori'de concentration is 1.4

-ppm-The conductivity measurement can also be useR to hound the possible range of PH values.

This relationship is shown in Pj.g,ure X.l 21-4.

-,'A't a 'speci'Hc conductance oX l.'.0 miczomho/cm 'the

~PH must be be'tween 5.6 and 8:7. ".Zurthermore, a

PH of 5 and

a. specific conductance of 1.0 is an impossible situation since the conductivity is not large enough to support a hydrogen ion concentration of 3.0-5H,.

Pigu"e g 1 21-4 can, therefore, be used Co great advs'tage in c'hecking on agreement

.between PH and

.conductivity measurements and possibly eliminating the need for p'H measurement if the conductivity is very low.

In general, accurate pH measurements are difficul" to make in very low conductivi'ty 'wa'ter as the impedance of the solution may be wigan'"ica~at:compared to 'the impedance of the measuring

device,

.am'd corductivitp ncasuxements are usual1'y considered a he+ter indicator of the maximum H+ or OH-concentration.

X 3..21,.3 4 2.4 Radiochemica1 Ana3.yogis->>Gamma Hay 'Spectroscopy After the samples have been brought 4o the chemistry laboratory and appropria<el~ diluted., they can

'be ca ried wi~hou shielding to %he:counting roo

',wh'ch is adjacent

+o the chemistry laboratory.

'~ he aopropriate dilution factors will be somewhat dependent

.upon 'the detector and shelf arrangements available.

prior determination of the maximum desirable dose rates for the va ious shel'f configuration will be made to minimize this problem he presen h'gh resolu ion, high efficiency Ge (Li) detec ors, coupled with the multichannel analyzers, and computer data reduction in the on-site coun ing

=oom w'l easily handle the a n'a lysis of these samples.

The.gas samples will he counted in the standard off-gas sample vials and the.1iguid samples will be counted. in the standard

,sample -bottles used during normal operation since calibration

.curves for these geomet "ies vill.be available and regularly

.upda'ted.

ICalibra ion curves will also he available for the pa"ticu1a-"e fi1'ter azd.iodine.cartridge geometries.

In general, the countixg of tl:.e pos+-.accident samples will 'fo11ow the normal counting

=oom.procedu es A special post-accident library will have to,.'be develope'd,'r use by 'the computer peak search and i'dentifi.ca:tion routine Co,supplement the normal isotope library.

'.The post-:accident;peahen search;and i.zlentifica ion library wi11

concave:a Me; pxincipa'1 gamma nays:of 'the:f o'llowing isotopes in ad%."ta~n 0:o ~he 's'Candid ac i~a<ed.corrosion producis:

No'hie gases=

Kx-85, Kr-85m, Kr 87, Kr-88, Xe-131m, Xe-133, Xe-13 3m, Xe-135 2-l31:,,I-l32, "I-133, 2-135 Cs 1 34, Cs 1 37 Ba/J.a-'1 40, Ce-141, Ce-144, Ru-106,

'Te-129,

'Te-3.2'9m,,

Te-3.31, Te-131m, Hp-239

~

~

Zf the levels of 'nob'le,gases in the ambient atmosphere

.surrounding the de&actor is high enough 'to 'casse significant inter erence or overload the detector, a compressed air or nitrogen purge of the detector shield volume vill be maintained.

.X 1 21..3 4

2 5 'Gas 'Analysis-Gas Chromatography A.gas ch:ramatog.raph v3.l"1 b.e wsed

'to measure hydrogen.,

nitrogen and oxygen concentrations in containment atmosphere

.and dissolved gas samples.

The gas chromatograph vill be located in the chemistry laborato=y and vented to a laboratory hood Samples for ga's analysis will be used undiluted from the sample vials,and injected into the gas chromatog"aph Since the sample sizes needed for the. analysis will.ange from 0.1 to 1 mild;i1iter, it may be necessary to place a temporary lead shieM a ound the instrument The ana3.ysi of he dr'yvell, we tvell, and secondary containment samples wil3. he done using standard p ocedures.

Cali.'bration curves fo the instrument will,be prepared and periodically updated.

"Xn the mix ture o

hydrogen, oxygen, nitrogen, and possibly Krypton,

-the analysis sensitivity should be sufficient to detect any

~f these constituents at the 0.17 by volume level, or love",

providing the Kr:4 ratio in.his mixture does not vary 'by more than a factor of 10 in either di"ection.

At the 0-5~ level.the analysis should be accu=ate to within 20.

of +h~ measured concentration.

At concen rations above 1~~,

he ana'1ysis should be accu-ate to within 5.". o'f the measured concentration.

The dissolved gas sample vill contain krypton or other tracer in addition to oxygen, nitrogen, and possibly hydrogen.

Al;-"hough the analysis of the dissolved gas sample for h'yd ogen 'should be

reliable, the analysis for oxygen and nitrogen ores nts several difficulties.

The ma jor problem is due to +he incomplete evacuation of the sample vial whicn initially contains air.

A partial vacuum (4-5 psia) is dravn on the vial before the sample is taken, however, this leaves a significant amount of air in the vial.

Tkis may not be a significant problem if the amount of dissolved oxygen or nitrogen stripped from +he coolant is large compared to that 1eft in the evacuated vial, since a correc ion can be made based on the pressure measurements taken before and after aking the sample.

Hoveve,,

dissolved oxygen

.and nitrogen is not,required by HUHEG-0737, vhich states that d'etermination of dissolved hydrogen gas in the coolant is adequate..

Xn case the need should arise, a pzoceduze,vil1 be established to tap off the sample line in the sample station and run this to an in-line oxygen monitor,.

The flow would then return to the,liq,uid zetuzn Bine to the wetwell.

X.3. 21.3.4 3

Storage and Disposal of Sample Short term sample storage areas vill be provided in the chemistry

.laboratory and counting rooms in both the on-site and EOF faci1ities.

An,area fo long tnrm storage of the 'samples vill -be designated at a later date.

Lov level.vastes genera+e'd by the chemis'try procedures <<ill be flushed to radvaste in the on-site chemistry laboratory and collected in removable carboys in the EOp.

The carboys vill then

..be taken to an on-site location for 17

~

~

disposal to t'e radwaste system Ultimate procedures for disposal of the samples -vill be determined la'ter; however, after a sufficien ly long decay period, the activity levels vill be significantly reduced.

This vill ease exposure problems during disposal X.1~21 3.4 %

'System 'Testing and Operator Training To ensure the long-term operability of the.

PASS, it vill be tested semiannually.

Samples vill be "aken from all gas sample

pmnts-,however.-,

th'e:number and type of liguid amples <akin vill be;based an the opera ing status of the reactor a

the time.

he

.semiannual.functional testing

.vi11 also serve to maintair.

operator pro'ficiency.

Zn addition to the scheduled

tests, the system.will be used for operator training on an as-needed basis.

To -ensure an adequate pool ef qualified PA'SS operators, a formal training program vi11 be established.

This orogram will be part of <he chemistry technician auali. ica ion program.

All plant chemist;,"y technicians and chemis =y management oezsonnel vill be

-zeguired +o;show competence

.n the opera.ion of the sample station and the chemical,ana1ysis p ocedures.

X..1-23.>>3.5 Nose Rate Analysis

.Radioaj- ""vity source te-ms ware calculated or use ir. des'gn o

the Pos Accident Scamp]$ >g Sy<Z<m (PASS) shielding.

These sou"ce terms are for a Loss of Coolant Accident (LOCA) assuming a fuel release of ission product ac. ivity as def'ned by hUR"=G 0578.

Source terms vere calcu1ated fo" a three year reactor operation at 3293

.".2 Poz the pu poses of soeci ying shielding design source

terms, a decay.,pe"iod of one hou" ha=

been assumed Letveen reactor

'sh utdovn and initial -am pling Although the e is no decay

-pezic'd specified, in

>DU'?ZG 0578 he source terms calculated for PALS still result in a conservative design-The PASS is designed

-'to 3.imit operator whole body exposure to 100 mRem as a

zesu34

.of 'ta'king.and,analyzing the sample

'VUREG 0737, on the other hand,limits the.operators exposure to less than 5

Rem vhole cbody exposure foz,.the entire operation.

Using a Pne 'hour decay and the fractional red.eases of core i.@century mpecifi~d 'by 'VU'F'EQ 0578., the primary coolant

-and primary containment atmosphere fission produc+ concentrations are "ca1cu1ated Co

.be '2..6 Ci/gm and 0,.046 Ci/cc, -"espectively.

Using these fission ozoduct concentrations, gamma adiation

..ource terms were determined in erms of;I+V/sec fo" to.n gamma energy groups These radiation source terms vere used foz shielding 3esign 'and sample -dose, rate calculations.

Assuming point

sources

'the -calculated

.lose "a:.es pe" init volume of coolan" ard

'eonCaimment,a<>ospheze are,125 3/h/gm and 1.9 'R/h/cc at 4 inches, w.espect ivy.ly.

18

~

~

,Thus, the

'.0 1 *mi'1'li'li.ter reactor sample, would have a

maximum exposure xate of about 12 'R/h,a<

'4 inches and 14.'7 milliliter vial. of containment atmosphere at STP would have an exposure rate of 25'/h at 4 inches.

Using the calculated source te ms, dose

.rate estimates resulting from activity in the sample station and sample

.casks were calculated for various distances.

The results a'e givon ix Ta'ble X.1.21-2

=hese apse *rates ~ill be used i", a time-.motionstudy to estima e the total integra.

ed dose expected during sa~pling and analysis after the sample station is opera tiona l.

19

Chemical and Badiochem'ical Analytical Capabi1'ities Required of Off-Site Laboratory Xi:quid.'Samp1es The,3.aborato'ry

.must be capable oX hand3.ing up <o "10 nl of undiluted reactor coolant/suppression pool wa ter with activity levels up to 3.0 curies per ml.

The labo"atory

-.vill be.required to perform,the following analy~es within

'the.r'ange and accu'racy indicated.

1-Radioisotopic Analysis

.a

',Gamma-,Bay,S pectro scopy Xdentify and. quantify wi h accuracy

.o'f +

20% all iso opes which have gamma-ray peaks in the spectrum from 50 'to 5000:keV with a ne+

peak area of greater than 5f of the total spectrum counts within a

+

5 times full width at half maximum (P'RHWi) 'ba'nd a bo ut t'e,centroid oZ

+ h e peak.

Th e

-spec'trome't'er system mu b'e capable of analyzing

samp1e's with.total concentration,cf gamma-ray emitCing i.,sotopes as low as 0..01 microcuries per ml.

Beta

'Activit v Gross >e+a an8 quantitat ve determination

o. Sr-89 Sr-90 (up to 10 days permitted for completion of this analysis).

c.

Alpha Ac ivity Gross alpha 'count and relative alpha ac+iv ties by al,pha spectroscopy.

'Uranium,and 'p1utonium

-Zden'ti'fy zxd,perform semiquan'titative analyses for these elements.

2 Conductivity

'.Ran,g,e:

'0 3. '4'o 1',0,"OQO;mi:crom.hos pe:r cm.

Accuracy=

+

20%

3.

pH Ra'ng,e 1.ta 13

.':Ace%racy=

+

0.. 3 aH univs

'.'Ch3.'or i.de

".Range=

gre:a'ter Ch'n '50 ppb 20

5-

~

~

Accuracy;.

+ 10% if greater

't,han '5'00 ppb

'+ 50;ppb i.'f 1ess Xhax '500;ppb Boron

'Range.

0-'l to 1'.0,000 ppm Accuracy=

+ '59%. i less tham 1

ppn

-'+ 207. if greater than 1

ppm and less than 100 ppm

+

5 g if greater than 100 ppm

.B.

Gas Samples Gas samples vill be obtained from the folloving sources:

dryvell, vetvell, secondary containment, and dissolved gases from J.iguid samples.

The laboratory mus't be able to handle 15 ml gas

.samples vith.activity levels up to 0.06 -curies pe" ml The laboratory, will be reguired to perform.the +o11oving analyses within the

=ange and accu"acy indicated:

'Radioisotopic analysis by gamma-ray spectroscopy.

See Section A.l. a for reguirements.

2 0 Lleme ntal Analysis

'Identify and auantify by volume

~ 'the following:

Hvd ogen,

oxygen, nitrogen anQ Kr (spike added to di.ssolved gas samples)

The analysis sensitivity should be su= icient, to detect any of these cons it'uents at the 0.17.

by volume level At the O,.li; level the analysis should be accurate

<o

+ 20...

A concentrations above 0.5'F. the analysis should be accurate,to within

+

5%.

Particulate and Iodine Car"ridge Samples The laboratory must be able to handle and perform gamma-rap spectroscopic analysis on particulate, silver zeolite, and charcoal filter cartridges.

The maximum activity anticipated for any of these cartridges is 0.1 curies.

The ana1ysis should be able to identify and auantify vith an accuracy of

+ 50~ all isotopes which have gamma-+ay peaks in the spectrum from 100 to 4000 keV ~ith a net peak area of greater than 5% of the total spectrum counts vithi.n a +

5 times PVHM band about the centroid of the peak.

21

~

~

.Ta'>le

.X 3. 2!l-"2 'Dose:Rat'es

.'from PASS,an'8 'Transport Casks<>>

",Source

'Thickness of Z.ead Shi;e'1ding in Xn'ches 8 ft

'.3 ~t

'Dose Mate in mR~h Liquid 'Sampler'<>>

'Gas

.Sa mple,r< z )

'Smal.'1 Vo1-ume Ca.sk (0.'1 ml sample)

,2 5300 8800

'1600 310 220 55 110

.Large

-:Vo'1ume.Cask

'(3.0 '.aQ >am.pie) 5 1y2

.'260

='Gas Cask (14 7 c c sample) 2 '3./8

'5500 5'0 c ".z3

Based, on source tern 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fol3eving shutdown

,Dose *+ates from %he sample panels vi11 be present fo" on3.v a Xev minutes v'bile %he sample is florin~~.

.22

'I'RRAD'IATION:.EFFECT ON ANAL'YTIC'AL PROCEDURE'S Test Performance

.Conductivity.and pH:

H. L. Kenitzer

.Chlor'ide and Boron C. R.:Judd

INTRODUCTION

'Some scoping,tests were performed 'to study the effect of '-high fi'ssion product levels on the proposed analytical procedures.

The core inventory of individual nuclide beta energies in terms of MeV/second/Mwt after one hour decay was

'taken 'from the same CINDER run as used to,calculate the PASS act'ivi'ty source terms.

The NUREG-0578 release fractions were used to determine the fraction of the core inventory dissolved in the primary coolant.

The "all other" ca'tegory was ignored as =at a là release;fracti.on

'the dose.contri,bution from these nuclides is negligible compared to the.50>> halogen and 100K noble gas releases.

The results are shown in Table 1.

For the sake of simplicity, it was assumed that the gamma energy deposition in the sample was negligible compared to the beta energy deposition.

It was also assumed that 1005 of the beta energy was absorbed in the -sample.

The net resul,t, 1.92xl.06 Rads/hr, is conservative as the gamma energy absorption

'for sma'll samples would be much l.ess than the beta, energy escapi,ng the solution.

Dose rates approaching 2xl0~ R/h are available in the VNC Co-60 irradiation fadlity. At.93 ergs/g/R/h, this corresponds to 1.8x106 Rads/hr, and approx-imates the calculated maximum energy deposition possible for the reactor coolant.

Tests were run to determine the effects of radiation on the con-ductivity, pH, chloride, and boron analytical procedures.

The true energy deposition within 'the irradiated sample holders was determined 'by Fricke dos-imetry using the sample holders as dosimeters.

Except for conductivity and pH measurements, the dose rates were considerably larger than would be en-countered with the PASS source terms.

These higher dose rates were used

,to achieve,a better measurement

.o'f the radiation effect, and it was then assumed that this effect would 'be linear with.dose rate.

It is hoped to verify,this assumption in later studies.

-Al-

TABLE 1-CALCULATION 'OF COOLANT 'BETA DOSE RAD/HR AT 1

HR DECAY I-l'31

'I-132 I-1'33 I-134 I>>l35

,Br.-'83

Br-84

.Xe-'133 Xe-135 Xe-'138 Kr-85 Kr-85 Kr-88 Kr-.87 1

S'M Y/ (a)

'per MMt Eat

,'One Hour 1.78E14 7..26E14 8.1'5El 4 1.06E15 6.67E14

2.

04El 3 7 72E13 2.'06E14 1.16E14 5.85E13 2.55E12 4.95E13 1..33E14 3.71E14 2

Col.l*F( )

8 MeV/s per

'MMt, T=

1 hr

.Released 8.88E13 3.63E14 4.08E14 5.30E14 3.33E14 1.02E13 3.86E13

.2.06E14 1.16E14 5.85E13 2.55E12 4.95E13 1.33E14 3.71E14 2.71E15 3

Col.2*M( )

.Coolant 6.28E4 2.57E5 2.89E5 3.75E5 2.36E5 7.22E3 2.73E4 1.46E5 8.18E4

-4.14E4 1.80E3 3.50E4 9.40E4

.2.6366 1.92E6 f

(a')

FromCINDER run 8/18/80.,

BENUMB 2100T,.Core Inventory

,3:yr burn

,'(8)

'F = l.Q for noble gases and '0.5 for halogens

-I -) ~,

'..'3293 MMt 3600 s/h*1.6E-6 er MeY 7 07710-10

, 2.,68EB 9

• 100 erg/g/Rad

'CONDUCTIVITY A 0.1 cm Balsbaugh conductivity cell and stainless steel holder was irrad-iated at various positions in the 4;-in. dia.

Co-60 irradiation tube.

The flow.path from -this conductivi,ty 'cell was connected to a 0.1

.cm Beckman con-duct'ivity ce11 downstream of the cell under irradiation.

Both static and flowing irradiation tests were performed.

The flow tests were performed at

.ca.

125 '.cc/min.with a

.3 to 4 min Slow,delay between the '.Balsbaugh

.and Beckman

.cells,.

The '.Beckman,cell-, therefore, served to determine -if there.were any relatively long lived radiation products remaining ~n solution.

An 'in-',line thermometer was mounted in the 'flow system, downstream.of the ',Beckman cell.

- A3-

"CONDUCTIVITY'GF PURE,MATER A:Gelman Mater-'I purification unit was installed in the conductivity cell flow loop.

The output conductivity of the water from the purification unit was 0.055,uS/cm,

.as indicated by the purification units built in the con-ductivity,meter.

The water flow was from the purification unit through the two conductivity cells under study and back to the reservoir of the puri-f'isa'tion,unit.

The.output of'he conductivity meter associated with the iv'radiated ce1]

was j:ontiiiuous'ly'recorded.

The highest radiation field in the W in. irradiation tube, as measured

.by a Victoreen R'Meter, was 7.4x10s

.R/h.

'The actual cell energy absorbtion rate at this position was determined

,by removing the, conductivity element

.and using the cell holder as a Fricke dosimeter container.

The result, 9.Sxl0s Rads/hr was also used to convert the,R/h measurements at the other elevations to Rads/hr by assuming a con-

.stant ratio'etween

'the field intensity an'd the energy absorbtion.

(This

'is not strictly true as the photon energy distribution varies with the elevation

.in the irradi,ation facility.

Consequently, the fraction of the photons pene-

'trating the stain1ess

--steel cell ho1der will vary slightly.}

The'results of these experiments are suomarized in Table 2.

There was apparently some pickup of impurities from the flow loop materials as 0.10 uS/cm was the lowe'st loop *conductivi,ty observed.

The.0.06 vS/cm at the output of the puri'fication.unit was confirmed by connecting one of the flow cells imoed-iate1y at the output.

3n the, case i'".the flowing measurements,'here was a steady increase in conductivity 'from '0 'll.to.0.,65,AS/cm as the irradiation intensity increased from 1.'3x1.0" fo $.';6x10

',Ra'dsj'hr.

'The.conductive species

.which,were formed

'@em a'elatively stable ss there was "l'i'ttle di fference between the conductivity ms measured at, the.'ivxadi'ated:cel1 and 'the downstream cel1.

In fact, when the flew was 'stopped and the conductivity of the irradiated cell was allowed

.to some;to equilibrium, the cell could be removed from,the radiation field

and the. Conductive would remain constant,

=at least

=up to several hours, the longest

'TABL'E 2 CONDUCTIVITY OF PURE WATER UNDER IRRADIATION

No B.radiation 1.3xl04Rad/hr 6.6x104Rad/hr 1.3xlOsRad/hr 2.6xlOsRad/hr

-6.6xlOsRad/hr 9.8xlOsRad/hr Fl ow

'No 'Flow Flow No Flow

'Flew No Flow Fl ow No Flow Fl ow No Flow Flow No Flow Fl ow No Flow Temp.

"oF

63. 5 65.'0 65.5

'65.8 66.0 64.5 65.5

'IRRAO'IATEO CELL (0.'1 cm Balsbaugh) pS/cm 0.10 0..14

'0,-11 1.4 0.13 2.2 0.18 2.2 0.'31 2.1 0.65 1,.8 to 1.4*

0.657**

UNIRRADIATED CELL (0.1

'cm 'Beckman)

.uS/cm 0.11 0.11 0..12 0.14 0.20 0.37 0.64 0.66 Still dropping slowly after 5 min

'~*

Very steady value

-A5-

ried:,observed.

'The ','flow 'was secured, at.each irra'diation 'intensity and

'the conductivity was monitored until a steady-state condition was attained.

From the data in Table 2 it would appear that a maximum conductivity is attained

'-aX about,.2.2.iS/cm,.and that the conductivity diminishes with increasing ra'diation intensity.

The steady-.state difference in cell be-havior at 6..6x10 and 9.8x10 Rads/hr is unexplained.

J4 is suspected 4h'at the;.conductivity is Cue to the formation'of hydrogen peroxide, 'but,this 'has not been confirmed.

It is.obvious that there will be some'radiation effect.on the conductivity at very high fission, product con-centrations.

This does not appear too serious,

however, as 2.2 uS/cm corre-

.sponds

-to,a,NaC1 concentration of 1.0 -ppm.

The concentration.of stable Sission products,;parti.cearly I-'l27 and I-129,:associated with 'the high

.Curie concentrations will,at the same time result in.considerably higher conductivieies.

1 CONDUCTIVITY OF 10 m,CHLORIDE Cl SOLUTION Irradiation tests were performed to determine the radiation effect on the conductivity of a dilute NaC1 solution. It was anticipated that if the pure water conductivity increases under irradiation were due to the formation of Hz0>, this might be suppressed by the presence of the 'Cl ions.

In this experiment the.NaCl solution was pumped from a reserviur.through the two conductivity cells and.back to the reservior.

A.comen conductivi'ty '.bridge was used to alternately.determine the conductance

.of each cell, and thereby eliminate any bias between different bridges.

The testing was done -at the highest available irradiation level, 9.8xlO Rads/hr.

The solution temp-

erature, as indicated by a flow thermometer downstream of the unirradiated

.ce11, ranged from 59.'5 Co,60,.2'F..

Several,alternate

.conductivity readings were taken on each cell approximately five minutes.after each, change in condition, and when the ce'll conductances had reached a steady va1.ue.

'The average result for each condition is given in Table 3.

The difference betweer.

the cell readings for any given set of conditions is attributed to errors in the stated cell constants.

The conductivity of the flowing stream increased by approximately 0.6 uS/cm for both cells before and after irradiation, which may be the result of the generation of some long lived species.

This possibly is supported by the Beckman cell, which although located outside

%he radiation field, showed a 0.6 >S/cm increase in conductivity during irradiation.

The puzzling observation was the large drop in conductivity of the,static solution during irradiation.

This should be investigated further.

-A7-

',TABLE '3

";CONDUCTIYITY-lOF;-:10:ppm!Cl

.'50L'UTION;NaC1

-:.Flow

'-,No Jara'dpi'thun

'No.Fl ow i

'.Flow

'Flow 9.:Bx10sRads/hr, No:Fl.ow iFlow "No'3v,radi:ati.on lNo!Flow Unlrradiated:Cell (0.1,cm:Beckman) s'cm 27.:7

'27.7

'-,27.4

'27. 9

.:28. 0

, 48;0 28."0

.28.1 Kri.adiated Cell

'0.:1

-cm Balsbaugh) 5'/cm

.32.1

.32.0 32.7 33.6 25.1 34.0 33.4 32.2

"-2'AS-

yH Solutions of pH 3.8 and 10.0 were made up using HCl and NaOH, respectively.

Lo-Ion pH test paper was placed in aliquots of these solutions and the R

solution was inserted into the 9.8xl0s Rads/hr position (as determined by Fricke dosimeter).

A 10.0 minute exposure for a total dose of 1.6xl0s Rads completely destroyed

.the color in the acid sol.ution and reduced the color intensity of the, basic 'solution to a,pale green.

This test was then repeated using a l..'0 min exposure at the same intensity level 'for an exposure

.of,1.6xl0" Rads.

This exposure shifted both solutions about 1/2,pH unit to the more acid.side.

The results would not necessarily indicate, that pH in-dicator paper cannot be used at the highest dose rates, but more importantly, that 'the paper cannot be imnersed in a relatively targe vo'l,ume of sol.ution.

If,.the paper, were merely 'moistened

',by a drop or so of solution, most of the beta particles would escape the paper with little energy deposi tion and the paper would not be surrounded by a highly radioactive solution with the re-sultant beta field end water excitation:products.

This subject is still under consideration.

At source terms on the order of 105 or less of the maximum*, the irradiation effect, for even an immersed strip, would be tolerable at exposures less than 5 min, as it would result in less than an 0.5 pH unit shift.

~The originally calculated source term was 1.9xl06Rads/hr.

Thirty-five percent of 'this source intensity, however,.is.due to noble gases which would escape solution in the sampling process.

A 10X source.term for pH

measurement would then be approximately 1.2xlO Rads/hr and a 5-min

~exposure would correspond to a lxlO" Rad energy absorption, which is approximately the exposure causing a 0..5 pH shift.

-A9-

"-,Some;;measurements

.were al.so made"to:"determine '.the 'e'ffect;.o'f "irradiation on pH electrodes.

Long 'leads are needed on the pH electrodes in order to reach

',in.the Co-,60 irradiation facility, and.these, electrodes were not available.

'Me intend to,'order,',some-:new:electrodes;and'will.continue

.'this:study.

In the

'meant'ime,.we.have irradiated

.a glass membrane pH.electrode 'to 1,.6xl0s Rads at a.9.85xl0 Rad/hr intensity,and found it still,fcnctions following irradiation.

TURB?DINETRIC CHL'ORIDE PROCEDURE Using the maximum source term of 2xl06 Rads/hr, ml diluted primary coolant sample, would have an internal beta exposure of 2xl04 Rad/hr,.

The turbidimetric method.calls for a total "volume of.25 ml.

'Therefore,,

even if'he.entire 10 ml of diluted sample were used, the dose rate of the final analysis solution would be less than Sxl03 Rad/hr.

Test solutions containing 0, 1., 5, and 20 v/gmof.chloride in 25 ml were.processed through %he chlorMe.test 'methods in

.pairs.

.During the 'l5-min turbidi'ty-'formation pe'riod, one.sample 'of each set was irradiated at.an absorbed dose rate of 4.4x10 Rad/hr as determined

.by

.Fricke dosimetry.

The maximum observed raidiation.effect.was a difference of about 10 turbidity units between the irradiated and unirradiated 1

pgm Cl

,soluti.ons.

This difference is equival.ent to about 10.p/gm.of chloride in the '25 ml of solution '.being, processed.

Assumi'ng this increase in turbidity is proportional to the dose;

'the maximum,effect would,be (10 pgm).(8xl0 /

4.4xl0

) =,0.18 ugm.

.If only O.l ml o'f reactor water were used for the original sample, th'is would be equivalent to '1,.8,ppm,.of Cl in the primary coolant.

This error is probably insi gnificant as the interference from all the. stable iodi ne associated with the high radiation intensity is likely to be far larger.

'The test data also indicated -that as little,as 5 ugm of.Cf in the 25 ml.of test solution inhibits the formation of the radiation-induced turbidity. It is suspected that the increased turbidity is due to the precipitation of silver peroxide and;the 5,pgm Cl inhibited,the formation af hydrogen peroxide.

In;any event, it was concluded that the test method is:useful Vor highly radioactive solutions above the

.10 ppm level, -or for 'less radioactive sol.utions,above the 1

ppm level.

For low,activi'ty samples whi.ch do not need to be 'diluted and where at least a

1 ml of sample is avail'able, the method is useful above the 100 ppb level.

'.CARMINIC 'A'CJD:BORON 'ANALYS'IS

'Using the maximum 'source term af '2xl06 Rad/hr, an 0.1 ml:to 10 ml diluted ori-mary coolant;sample;would have 5n internal beta exposure of ca. 2x104 Rad/hr.

'The ',colorime'tric.method.ca11s 'for,a "total volume:o'f 25 ml.

Therefore, even 1f the ent'ire 1'0 ml.o'f di].uted solution were.used, 'the dose rate of the final analysis solution would be less than 8xl0s Rad/hr.

Test solutions

conta'ining '0 'and;20

-:,ugm -o',boron"were processed through the boron test

'methods

".i:n 'pain's...'Ouring %he.-40-:min color.devel.opment phase,,one sample

.of each, pair,was irradiated,at:an absorbed, gama-radiati'on dose level o

4."4xl0s:Rad/hr as 'determined by Fricke 'dosimetry.

The maximum irradiation effect observed was a difference of 0.854 absorbance units between the i:rradi,ated:and unirradiated blank solutions.

This difference is equivalent

-to debout,'27 ygm

.'o'f ':boron in 25 ml of solution;being precessed.

Assuming thi.s difference -in,absorbance is proportional to the dose, 'the 'maximum effect would be (2/pgm)(8x10 /4.4xl0

)

'0.49,ggm.

If only 0.1 ml of reactor water were used:for ",the..original.'sample., this is.equivalent to a 5 ppm error in the

.primary coola'nt,analysis.

'This error is totally neglibible in terms of the levels of boron required for reactor shutdown.

- 'A12-