ML20064G399

Forwards marked-up FSAR Pages Showing Changes Incorporated Into Amend 1 to FSAR Re Conformance w/SRP,NUREG-0800, Transmitted on 821006

ML20064G399
Person / Time
Site:	Satsop
Issue date:	01/04/1983
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0800, RTR-NUREG-800 GO3-83-08, GO3-83-8, NUDOCS 8301110470
Download: ML20064G399 (28)

Text

.

Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 Docket No. 50-508 January 4, 1983 G03-83-08 Mr. G. W. Knighton, Chief Licensing Branch #3 Division of Licensing U.S. Nuclear Regulatory Coninission Washington, D. C.

20555

~

Subject:

NUCLEAR PROJECT 3 SUPPLEMENTAL INFORMATION ON CONFORMANCE OF WNP-3 TO STANDARD REVIEW PLAN

Reference:

a)

Letter #G03-82-1015, G. D. Bouchey to 1

J. D. Kerrigan, dated October 6, 1982.

Reference a) transmitted Amendment #1 to the WNP-3 FSAR.

This amendment con-tained the initial phase of the WNP-3 review for conformance with the Stan-dard Review Plan (SRP) NUREG-0800, required by 10CFR50.34(g).

In, those cases where differences between the WNP-3 design criteria and the SRP acceptance criteria were identified in the initial Supply System review, a schedule was provided detailing when the bases would be presented for con-cluding that the WNP-3 design criteria are in compliance with the Commission Regulations.

Presented herewith is the material for which commitments were mcde for the month of December.

Included are marked up FSAR pages to show the changes which will be incorporated into a subsequent amendment.

In those cases where exception is taken to the SRP acceptance criteria a reference is provided to the FSAR section where further information is provided.

Where necessary, ad-ditional information will be added to the appropriate FSAR section as indi-cated on the marked up FSAR pages.

pe\\

8301110470 830104

{DRADOCK 05000500 PDR

O G. W. Knighton Page 2 January 4, 1983 G03-83-08 SUPPLEMENTAL INFORl1ATION ON CONFORMANCE OF WNP-3 TO STANDARD REVIEW PLAN In certain instances, following a detailed review, we have been able to con-clude based on information presented in the FSAR that the WNP-3 design crite-ria do, in fact, conform to the SRP acceptance criteria.

For these cases, with the exception of a change to the FSAR conformance review table (Table 1.8-3), no further change will be necessary.

The detailed coniparisons of the WNP-3 design with the guidance contained in Regulatory Guide 1.143 and Branch Technical Position PSB-1, which were scheduled to be submitted at this time, are not yet complete.

It has become apparent that much more effort will be required to provide an accurate re-sponse than was initially thought.

For these cases the individual FSAR pages from Table 1.8-3 have been marked up as shown with revised schedules.

If you require further information of cJarification, the Supply System point of contact for this matter is Mr. K. W. Cook, Licensing Project Manager (206/482-4428 ext. 5436).

Sincerely,

$Pm

. Bo anager uclear Saf y and Regulatory Programs AJM:ss Attachments:

cc:

D. J. Chin - Ebasco NY0 H. S. Reynolds - D&L E. F. Beckett - NPI J. A. Adams - NESCO D. Smithpeter - BPA A. A. Tuzes - CE A. Vietti - NRC Ebasco - Elma UNP-3 Files,- Richland l

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t.ci.nlee..ea me that a,e. swerms., t>. reacter, le nka tre renter line.see mas ti.e aet.o.ity to eteret.e an.ctietties lect dies eaciest.e er ree*,al of persear*B ead peeperty free the area. Ints ares ses to troverses I

by a higNay, railr++4 or -eterway, provided these are est se close to the f acil-s.p as to ta4erfere etth mersal eseratless of the f acility and greeleed appea-pelate and et f ectie a err a.gese.ts are eeM to castrel traf fic en tDe high ay, railreed, er water.ey, le esse of emergeacy, to prelett the pallt besith end safety.. Actieltles warelates to operaties of the reactae ear be pereitted la an e clesien area==Ser a:9eepelate lleltatlees, provided that me sigolficaat E4sards te tte p e lft k+alth e 4 s.lety =lli reselt.*

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Te e.et tt4 requirements of 13 US Fort 100 t** agolicaat ewst deerastrate.

petee te isseew e of a coestructlan perett er lletted wert aetheeltallea, that It has tre owtheetty wittle tse recleslee area as re<pired By Sectise 100 3(a),

es eest greestae reasseatle assw ente taat it will kare such eetherity price to e

steet of coastrwet tee Aaselste emeership of all leads withle the escluslae e ea, sect al., el. eras eis+ s. Is ceasleered to carry.Its it tte reaetred

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TABL E 1.0-3 yterc - coao sec ST M aFD efettv P'n!s CD9".T aEt SsF/a CtrTa!s3 Cs!*Tsfa Tis e ets w c3 1.

5e t eelt lastr e etettes seg. 1 - Jety 19s3 rr

,*as la additlea, the trianfel time blstery acceleregraph located to De cea-talment foundattee or to the free field should be connected to t e centrol race, se tut peaa ecceleratles level empertenced to De baseerst of De reactar costalment strictere or to the free fleid is ledicated to the coe-test roce operater. The respoese spectrw recorder fe De reacter contafe-seat fewadation er in the free fleid is alsa ceanected to the costrel room to indicate if De desty response spectra teles for discrete fregumectes

• are esco wd durist en eer*h4pate.

4.

Couper15ea of Strasured eM Predicted Sessoases le the event of an earthquake, De costrel reos operater should be famedf-3 stely lafereed throup tM event lad 1 Caters. If tM f astrweetatten shoes that the peak acceleratten er the response spectre esperienced at De foundatles of the containment butisf ag er le the free fleid exceed tM M accelerattea level er response spectra, the plant s%ould be shut doun To help predict (Ae cape-g (aef. 3) pendtag peretssten ta res ee operattens.

SIlity of pe plant for reset #g operettoas, field fespecties of safety-reisted ttees should be fuelemented eM De seesured tesponses free beta tee post-receretag and streag met *ee acceleregrepes should be coopered 7

with these ess med to p e destge.

[est eeces e et bee.,

the war.

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n er ette the a epe sar e steege sa, agges The proced res for coopertsee of measured and predicted respeeses are eccetta$le If a commitment is made to provide detaffed cooperisons, es es

,the bee e ser e t.dtes the the ver est1lmed below, between meese*ed setselc respesses of fetogery I struc*

deels eriter te re to e igeer, wt the Cagetesten*e te es and egetpoemt with calcoleted respo9ses deterstard free dynamic ree=)ttiene et he er eed by e 3,ef,

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J First, pe 11ee klstery records are digttfisd ead corrected r

eastysts.

The stee efstery for ttee sigssi vertatleas and baselles eerfatfees.

records from the telastal sensers located in LM free fleid et at the f ew datten of the comtal#eest building are used to cafcalate response The respease spectre thus a

spectra et appresetate critical dempteg es1 w s.

setelped, er t>e response spectre from the response spectre receeder, are le addittee, the Stee history ce= cared with tM destgm response spectrc.

records free De free field trf estal seaser are used as loput gesund settes for the reacter bellatag dysanic endel tactwdtng sell where esplicable.

Aspitfled response spectra are peg cafcsisted at pe locations of the atmee seasers le the reacter >=tidtag for cooperisam eM correlettee with Structural respeases e M emptf-the resperse spectre directly messered.

fled respease spettra are calcolated es tag the free field Etee history receeds =ttt the eynamic model for campselsen eith De erfgtaat deste end This campertsen peretts evaluettee of setselc effects saalysis parameters.sa structores sad eestparet and foros the bests for temodeltag, deta!1od e

emelyses, ead physical tespection.

[w um-en I service Svreettience 5

f fech of t** setselc lettruments shell be dessestrated operable by the peeformeace of the chamael cMct, cheanet calibratlee, ead cheaael femc*

tieaal test operatleas at the latervait spectfted in yeste J.F.d 4.

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se oaeit f ecert.a of we enic.t and sieetrices restement sev. 2 s

hly 1941 fr-,*di (4) The celteria of sesectica, II.1.e(7). (8). e4 (13) ead II.2.e(1) (2), ead (3), above, are applicable when tests are coaducted on the equipseat supports.

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3.

CDC 1 of Appeadle A and patograph IVII of Appeedf a 5 to 10 CfB 50 establish reestreseats for receeds coaceratag the quellfication of egulpeent. In K

I L-n_sM re ffereer esistbeseeestheWtr3destge/

s rit e and eccepto we casterte,ddeettfled e erder to satf sfy these requireeeats, complete end auditable records must be th SRF, tv bases feVcomelodiasp4 hat the 3

avallette ead paintefaed by the appIfesat for the life of the plaat, at a ceatral locatten. Their files should describe the quelf f fcatten method petsecrperteer

' eespit

/wsth the set a

res=1st Mes will provided December 2

- esed for all equfpoeat la suf fittent detall to decieret the degree of comp 11aace with the criteria of this SSP settlea. These records:should be eedated and malatataed current as equfpment fs replaced, further tested, er othemise further quellf f ed.

The equfperat quellficatten file should contale a list of all systees e

eestpoeat end the equipment support structures, as deffaed in peregraph 2 of sesectfen I.

The equipment If st steeld ideatify which egefpment is e555 s eelted ead which equipmeat is top seppiled. The equfpment quelfff-g cetten file should also faciude qualfficatten s m ry data shvets fee each

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piece of equfpment, f.e.. each mecheefcel and electrical componeat of each

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sutes, which sesamorite the component's queltf fcatten. These data sheets should f actude the followtag infermetten:

e.

Identif fratlea of egulpmeat, f actedtag veadee model sambee and locatten within each buildtag. Velves that are part of the reector coelaat presswee beuadeep should be se Identified.

b.

Physical descrfptlen, f aciudleg dimeesteas, welght and field seuntf ag coadt t t en.

Ideatificatten of whether the egetpment is pipe. fleer, we well supported.

c.

A descriptf en of the equfgeent's femctlea withf e the systee

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d.

Ideattffcattee of all destpa (functiscal) spectf fcatleas and g

esallficattaa reports. ead their locatleas. fuattloaal specifice-t k** f*' *ct b' '*1 " ***'"biS Sh*8 coa' ** th' 9***'y I

3, resttfea of Begulatory Gufde 1.148.

I Descriptfee of the regulred leads ead their f ateasttles for which e.

the equipseat sust be psaltfled.

f.

If qualf ficetten by test, ideattfication of the test methods sad proceeseos, leportant test parameters sad a semesey of the test o

reselts.

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3 If guellficetfom by aaelysf s. Ideattf fcatten of the emelysts methods ead essemptieas and cooperisees betmarea the calculated and allowette e

stresses and eeflectieas for critical elements.

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wur-3 ysAR T& ELE 1.0-3 sumsc - 0000 E STANDARD RETT 5f FLAll

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SRF/AccTP!Alect CEITTRI4 9.4.5 Eastseered Safety yesture Ventstattoa System Sev. 2 - July 1988 ACCEPTANCE CRITit!A Acceptaallity of the E$fVS design, as described in the appilcant's Safety Analysis Report (Saa), is based on specific gervrai design criteria and regu-1ste guides.

The design of safety-related portions of the f 5FV5 is acceptable if the inte-grated desf gn of the systees is in accordance with the following criteria:

1.

General Design Criterien 2. as related to the system being capable of I

withstanding the effects of earthemakes. Acceptante is based on meettag the guidance of Segulatory Guide 1.29, positten C.1 for safety-related porttens and C.2 for nonsafety-related portions.

1 2.

Ceaeral Cesign Criterlee 4, with respect to metatalning enetroveental cenettions in essential areas compatible with the design 11eiti af the essential equipoest located therein during neesel, transient, and accident c ondi t t ens.

j I su se.ork 01 (1) then are e. ehered erste-o s.4 ewee et var 3.

3.

General Design Criterlee 5, as related to shared systees and components tapertant to safety.

w General Oeste Criterten 17, as related te assuring proper funcitoning of

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the essential electric peuer system. Acceptance is based on meeting the ett a and

see, ce ce,ege gee. ggea g.

guldence of l'.se 2 under selectlen A and ites I under subsection C of th

say, been n.,

84 the Waf-3 the sectlen en 'Recommendettens" of IR2EG-CR/0660 (Bef. 9) relatig to sten e tute e in e ta=ce et the ce==s to 's the protectlen of essential electrtcal campenents free fatture due to the I

I nest ese will penjeedby o.9enn test.

ecemlettaa of dust and particulate esterials.

Ytt M, P-3 cds,)u resse/.* s.,& &

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Geners) Deste Criteries 60, as related to the systees capability to suit-5.

i, contr.i reie.se of gaseous ruso.cties of n nts to the eseirea ras.

uhuG/Ot-c4to acce.pt.nce is based on meeti, the,inac..f ee,i.tery suims 1.u.nd ft * ~44 -5 u a. as reisted to m si r, testi g. and w etenance criteria for etos-4 sphere cleang system, and neraal ventilatten eshaust system air filtration N8 r k O& CL

'm s y M[M,%

and edsorption units of Ilght wate*-cooled nuclear power plants, positten g

C.2 and Postttens C.1 and C.2, repectively.

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WW P-3 TSAR TART.E 1.8-3 WUREC - 0000 BC STANDARD RTVIIV FL All a -

ColftIANCE TE3 ND N/A RE"* "

SRF/A@f RAltc! CRITTRIA f

II.2 tie td weete,Menes e Svetees see. 2 - July Isal ACCEPTANCE CalitRfA 1158 acceptance criterte are based en me'eting the relevant requirements of the felleulng regulattens:

1.

10 CFR Part 20. I 20.106 es it relates to redleectivlty in effluents to g

unrestricted areas.

2.

10 CFR Part 50, 5 50.34a as it relates to suffletent design infersatten being g

prevfded to demonstrate that desten sbjectives fee eqvfpeent cecessary to coe"rel releases of redleactive ef fluents to the environment have been met.

3.

General Oesten Criterlen 60 as it refates to the redleactive waste manage-g sent systees belag designed to contral releases of redleective materials g

to the envireement.

4.

General Oesten Criterien 61 es it reistes to radienctive weste systems to x

be designed to assute adequate safety under nereal and postulated occident condittens.

L 3

The relevant requirements of the Ceemtssten regulations identified aLeve are set by using the regulatory posittens contained in the felle=Ing regulatory guides IIsted below.

a.

Regulatory Culde 1.110 as it relates to perforslag a cost-benefit 3 gee peserk (1)

(1) Refer to FSAR evbeecttene 11.2.3 and 11.3.3, analysts for reducing cumuistive dese to the populatten by using available technology.

b.

Regulatory Culde t.143 as It relates to the selselc dest p and quellty g

group classification of coepenects used in the liquid weste treatment systee end structures housing systems and the previstens used to control leakeges.

5 le CFR Part 50. Appendia I. Sectlens II.A and !!.0 es it relates to the

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tffer e ests tween be WWF-3 esga

,_,,p, numerical guides for dose design objectives and lletting conditlens for eri ria and seee enee er erta i fled operetten to meet the *as low as is reasonably achievable" criterten.

t e SoF.

bases er tone tog that e

-3 else teria e la e esce wt she sa

's reew toes v be pr by Dee r

2.

% 11guld reewaste treatment system should have the capability to meet the f

.etrecents specified in 10 Cf R Part 20. I 20.106 and 10 CFR Part 50, 5 50.34a.

a at General Design Crf teria 60 and 61 of Appendia A of 10 CFR Part 50 end the A

dose design objectives specified in Sectlens II. A and 11.0 of Appendia I to 10 CFR Part 50, incInding prowlstens to. treat ilquid redleective weste.

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l TABLE 1.8-3 a-NUREC - 0800 o

NRC STAlsDARD REVIEW FL Als Ct2ftIANCE RgptApg3 m an ma SsF/ACCEPTAJECE CRITTRI A 11.2 tlauld Weste Manaseunt System.

Rev. 2 - July 1981 (Cont'd) 1.

Specific criteria necessary to meet the relevant requirements of the Commission regulations are as follows:

e The calculated annual total quantity of all radioactive material g

a.

released fram esth reactor at the site to unrestricted areas will not result la an estteated annual dose er dose comettaent from 11guld effluents fo-any individual in an unrestricted area from all pathways of exposure in eacess of 3 milltrees to the total body or 10 ellitress II.L, \\. *L. n to any organ.

Inadditionto1.adove,theIIquidraesastetreatmentsystems I 8** E**'I (I)

(I) 8efer,te F5AR oubsectione 13.2.3 b.

should include all itses of reasonably demonstrated technology that g

when added to the systes sequentially and in order of dietnishing cost-tenefit return, can for a favorable cost-benefit ratio effect reductions in dose to the population reasonably espected to be within 50 attes of the reactor. Regulatory Guide 1.110 provides an accep-table method for perforetag this analysts.

The concentrations of radioactive materials in 11guld effluents g

c.

to an unrestricted area should not exceed the limits in released, art 20, 4ppendia B. Table II, Cel a n 2.

10 CTR

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2.

The 11guld ree,aste treatment systes should be designed to meet the g

anticipated processing requirements of the station. Adequate capacity 7,

should be provided to process Ilquid westes durteg pertods when major processing equipment may be down for saf atenance (single fsflures) and during periods of excessive weste generation. ET58 will accept systems that have adequate capacity to process th+ enticipated westes and that are capable of operating within the design objeC*tves durtnd normal fa meet these operetton. including anticipated operational occurrences.

prncessing demands. ET5g will consider interconnections betueen subsystees, redundest equipment, and reserve starage capacity.

XA /f a.... e jc. (Q The sefseic design of structures hotsing Ilquid raeseste systems, the g

3.

quality gro w classification of Itq61d redweste treatment equipment, and previstees to prevent and cellect 65111s free indoor and outdoor storage k.

tents should confers to the guideltres of Begulatory Guide 1.143.

ET58 will accept system designs that contain provisions to control leakage E see Re. art (2) (2 ere fier es en betwe the 3 des.

k 4.

gett ee the ece tence e teria dentet d in and factiftete operation and safatenance fa accordance with the guidelines kh

Sar, base for c metas et the

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of Segulatory Guide 1.143.

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wuP-3 F$AR TABLE t.8-3 WUREC - 0800 8

NRC STAPC AltD eFVTEV PL AN COMPLYAMCE 58P/ArctrTANCE CRITTRIA TES NO N/A RIMARES it.3 c.

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voi,i,si ACCfPT_ANCE CRITERI4'

[158 acceptance criterte are based on setting the relevant requfrements 4.

of the fellowfng regulattens:

1.

10 CfR Part 20,520.106, as it reistes to redleectivity la effluents I

to unrestricted areas.

50, 650.34a, as it relates to sufficient deste inferne-x

,10 CfR Part 2.

tlen beleg provided to demonstrate that desfgn objectives for equfpsent necessary to control releases of radfeactive efffluents to the envireteent have been set.

3.

Gener's) Design Criterten 3 as it relates to providing protection to g

t gaseous waste hamiling and treatment systees from the effects of en e

emplestve afsture of hydrogen end crygen, i

4.

General Desfgn Criterten 60 es 11 relates to the rodfonctive waste r

management systees befng designed to control releases of radfoottlee r

materia 1s to the ensfrennent.

e-U 5.

Generel Design Criterten $1 as It relates to redfeettivity centrol x

fn gescous weste man.geernt systees and eentflatten systees assectated with fuel steroge and handifeg areas.

es it x

10 Cf t Part 50 Appendla I, Sectf ens II.S.. II.C., and 11.0.Istting 6.

reintes to the pimerical gufdes far destyn objectives and I conditlens for operatten to meet the "es low as is reasonably achievable

• criterlen.

The requfreernts of the Commissten regulettens identf fled above are set by ning the regulatory peittom contained in the following regulatery suldes Segulatory Culde 1.140 as f t relates to the design testing and E

s.

maintenance of mereal ventitatfen exhaust systems at nuclea*

power plants.

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c ts.se. f. ~ g.se s

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.3 e che

{

waste tre,at, ment systee and str,uc,tures hovstng the systems and z..ser..n.6...

t,e...,,o~,

.r.

,e n.

m. e..,.

a

_ p,ev s ens ese. to c.t,e

e..g.s.

s. r.

4 A L:l k, p a, p w& u n w &p.r k q uo u

cu l

w:lik L w 3 as:d~3

,cm,p6A 5 crm,

u

o j

vuP-3

{.

TSAR TABLE 1.0-3 g rc - 0e00 peC STANDARD REVIfW FLAN ODIFLTAMCE TES 30 N/A REAPO sRP/ACCEPTAMCT CafTTIT A 31.3 caeous veste Menesement systeme Rev. 2 - July 1981 ic.sr t 's)

'""'*'*'"*"[/

"'*/'""""

The sofsaic desfon and quality s+epciassification of components s see me ort (l')

(1)~

' d88 3.

"8

'b'

used in the gaseous waste managenent sfstems and structures housing to s9F/the bee for eene tag t t the F-S these systees should confers to the gu delines of Regulatory Guide

[entsepiterie e la <=P

1. ace w h the to

,e 1.143. The design should include precautions to stop continuous

8"If 1*** wil be proved 67

• r i

• ?-

4 leakage paths, f.e., to provide l' quid seals downstream of rupture discs and to prevent permanent les6 ef the Ifquf d seats in the event j

g g gpgg g

of as explosion.

f(4Wilh Q

./ /df/5 4.

ET58 will accept sfstes designs that esitain previslens to centrol x see se.ork (t) 48-leakage and ta fac 11 tate ration and estatenance fa accordance with the guidelines of Regu atary Guide 1.143.

%g g

,g

,)M 5.

fiss v111 use the guidelines in segulate ':stde 1.140 (bef. 9) for MS the desfgn testing and saf atenance of HE A filters and charcoal MI adserbers Installed in normal ventilatten exhaust systas;.

If decontanteation factors for fodine different from those spectffed I

in segulatory Gutes 1.140 are used for desfon s, they should be supported by test data under operating er s ou ated operating

~~

conditions (temperature l. pressure, hafdtty, espected fodine concen-I.

tratlons, and flow rate The effects of eging and polsoning by af rborne contaminants should also be sgperted by test data.

6.

If the potential for an esp 1estre stature of hydrogen and esygen I see ee.ork (2)

(2) sofer to rsAR embooetten 11.3.1 fee e discwesten entsts, the gaseous weste mana at systems shoule either be designed on the aeolsa af 885* easemass weste m m t eyeree to withste N the effects of a espleston, or be provided (cies),

with dual u4s analysers with a omstic coctrel functless to preclude the formation er 9stleg of errlestre af stures.

e.

For a systes desfoned to withstand the effects of a hydrogen emplestan, the desfon pressure of the systes should be appresta mately 20 tfees the operatlng absolute presture (f actudlag the N Sfh/fM*fkll) intermedf ate stage condenser for ShR offges systems).

Small allowences should be eede to confers to standard destyi pressures for ef t-the-shelf components; f.o., if the system operating pressure is ocefnel?y 15 psfa but could approach 20 psia by desfgn, afping could be designed to 350 ps1a, since the next higher standard pressure rating Is 600 pole.

7 The process pas strees should be analyred for potentfally-emplestve ol ' ares and annunciated both locally and in the i

control rose.

r g:.

1 14 s ::....

p!h f,

I s

w..

-m

..,.p_._.

ab b l h! !!O 5?

Wur.1 rsAn 6

TABLE 1,4-3 UUREC - 0g00 1

f ERC STANDARD REVTEW FLAN ggMPLTAuct Str/Acc7tTANCE cRTTERTA YES up N/A REMARES 11.3 Cesecue Weste Menerement Systema Rev. 2 - July 1981 (coet'd)

~ ~

b.

For systees not designed to withstand a hydrogen emplosion.

I see senerke (1)

(2)

(1) aafer to rsAn subesetten 11.3.1 for a dieevesten dual gas analyzers (ulth dual being defined as two independent of the cum 5 deetsu bases %A ! sh m(4j*

prui* h b.

gas analyzers continuously operating and providing two inde-pendent seasurements vertfying that hydrogen and/or oxygen are (2)"where tfferences tot betw en the wur-deetan not present in potentfally-explosive concentrattens) with crit

1. and the ceptence rtterte i elfted in automatic control functions are required to preclude the fer-mation or butidup of emplosive hydrogen / so gen etutures. Gas ths say, the b es for e sud8ns t the wur-a tsn criters are to e tience wt the C solen's l

analyzers should annunciate alares both locally and in the e outettone vt i be pre toed by n, der iser

'High-high alare" gh alare" should be set approstestely II and control rose. 'Mf C

should be set at a esataan of 4E hydrogen or j

oxygen.

a K % / h44 n f ( (g Control features to reduce potential for emplosfon should be auto-x satically initiated at 'Mfgh-btgh alors" setting. The autaastic contret features should be as follows: (1) for systems designed to preclude explosions by maintaining either hydrogen er psygen below 45, the source of hydrogen or oxygen (as appropriate) should be automatically isolated free the system (valve should fall in closed if the downstream position); (2) for systees using recombiners, 5 (as appropriate).

r bydrog=* and/or osygen concentration exceeds 4 7

acceptable control features include automatically switching ta an etternate recombiner train and (3) injection of diluents to reduce concertrettens below the IIsits specified herefn.

Systems designed to operate below 45 byd' regen and below 4E osygen y

may be analyzed for either hydrogen or oxygen; systems designed to operate below 45 hydrogen only (no ogygen restrictions), should be analyzed for hydrogen; and systees designed to operate above 45 hydrogen, should be analyzed for suygen.

(

(

For BWR systems with steam dilution upstream of the recombiners.

x see samark

)

)

C'"d'*"****'"'r"'"'-

analysis for hydrogen (orygen is not an acceptable alternative) should be downstream of the recombiners and upstream of the deTay portions of the systee (analysis sestreas of the recombiners is not l

required if the systee is designed to assure the avellability of dilution steam during operatioi). For PWR systees using recombiners, g

analysis for hyd n and/or oxygen should be downstream of the g

recombiners. In ition, unless the systes design features ore-clude emplosive statures of hydrogen and oxygen upstreas of the a

recombiners, analysts for hydrogen and/or oxygen (as appropriate) d should be igstream of the recombiners as well. The puener of gas j

r 5

- ~., -

.e

.m r* n.-

r p

H #' -

j

[i l iN B:!

t.

4 WNP-3 FSAR TAat.E 1.8-3 IfUREC - 0800 o

uRC STANDARD RfvIEW FLAN CEDEFLT ANCE SRP/AccTPTANCE CRITYRf A TES no W/A W_""'

13.4 Sette h ete Menseement Systems rev. 2 - July 1981 (reer'd)

C.

General Design Criterten 60 es it relates to the redfoactive waste I

management systees being designed to control releases of rodf oactive esterials to the environment.

O Ceaeral Desten Criterlen 63 and 64 as it relates to the radioactive weste z

system being designed for monitoring radiation levels and leakage.

E.

10.CFR Part 71 as It relates to radleective materlat packaging.

3 The relevant reguf rements of the Commission regulettens identiffed above are I See Raeark (1)

(1) Where d ferences e at betwee the WWF.3 sign met by using the regulatory positions contained In Segulatory Culde 1.143 as criter end the o eptance e teria ideer led la it relates to the setselc design and quality group classification of com-this

, the be a foe to tag that WUP-3 ponents used in the gaseous weste treatment systes and structures housing the de se eritert era la e teace with Commi tom's systems and the previsions used to contrel leakages.

rfsstations % 1 be prow ed by rec er 1982 j

[ g/ /

g/pf g

Specific criterla necessary to meet the relevant reqvf rements of the Comelssion's regulations are as follows:

/

v

,dM 1.

The systes design parameters are based on radionucilde concentrations and g

[

4 M S M

volumes consistent with reacter operating emperience for sletter designs.

y k

g,h fk yff[*

g,'

g, 7.

All Ifquid wet wastes will be selfdffled in accordance with a process y

contret progree prior to shlpeent offsjte er there will be provisions te gg g g -

verify the absence of free liquid in each container and to reprocess

[

cont 4 f aers in which free 11guld is detected in accordance with Oranch J

TechnlCal Pesillon (STP) (15811-1 (Ref.1).

3.

Other wet wastes wf11 be selldified or dewatered (subject to receiving g

burial site acceptance) In accordance with a process control progree or there will be prowlsions to verify the absence of free liquid in each container and to reprocess containers in which excess water is detected, in accordance with Branch Techalcal Position (BIP) (15811-3 (Ref.1).

I 4.

Selfd waste containers, shipping tasks, and methods of packaging meet appilcable Federal regulations, e.g.,10 CFR Port 71 (Ref.1), and westes are to be shipped to a licensed buffel site in accordance with appifcable

[

Commission, Department of Transportetten, and State regulations.

I 3

g 5.

Processing equipment is stred to handle the desfon SW5 Inputs, f.e., the selld waste generation rates reviewed under ites I.1 of this SRP section.

s 6.

Onsite weste storege facilities provide sufficient storage capacity to x

allow time for short lived radionucifdes to decay prfor to shippteg in accordance with Branch Technical Position (51P) (15811-3 (Ref.1). (The

~

bases for the storege time chosen should be sfeen in the safety anq1ysis report).

a

)

S

1 C

vuP.3 r$aR Tast.E 1.0-3 ut't2C - 0800 BRC STANDARD RETTSI PLAll 1

COMPtiAIICT 4

sa?'AOCYPT*Cf CINrt! A Yt3 WD N/a REMAR8S 11.6 Sette weste Menesement Systees Pev. 2 - July.198t (Coet'd) fplng sys I see me.ork (1)

(1 were fr e e te e th.

3

..I s. y M c.omponents and o.rd..e.,te,ms, and st,ru,ctures, hoesing SW5 co,mponevits.

. er 7.

l ae es, - d,n t the pro. s ons e Re,.1.,ory ou.e 1. m

.:tt.

It..t.

1 (Ref. 2), and Branch Tecenical Position (STP) E15811-3 (Ref.1).

shte ar. t beoes e

ledtes t t war.

de yn cet rio er to e tience 8th Came stoe's I

TP Sws contains provisions to reduce leakage and factiltate pperations' I see Reserk (t) r p latt will pree by e

toer.

8.

an. malatenance in accercance with the proetstons of Regulatory oulde

- 3 1.143 (Ref. 2) and tranch Teculcal Positt,on (STP) (T5811-3 (Ref.1).

'f h gg g, f,*

g j

gf f,f Q j g) g,e,

e 9.

F.or longer teve onsite storage (several years, but significantly less

• b than the life of the plant) the storage f actitty should be sesigned to g

w. ( f Q w gg,3 5

p,'/f k

, the guideltnes of Appendia A to this 58P 5ectten (Ref. 3).

e

% p%

_7W 4491 C

I m & s-y y y u w g r.,

$n a %w.km ~ s:L sk~p w

-s.

e i

I 7.

E ili $!

r ;-

l

!?: f !!.

i

<3

'N5 f..

W P-3 FSAR TAEl.E t.8-)

Nt'tEC - c800 NRC STAMARD REVIFJ FL AN C0 WI.IAnct YES aK) N/A REMARK $

Strf ATTRAnct rFITTRIA Frocees And Ef fluent todfolagtest Mrwaltering Instraumentetton And Sempties Systems 18.5 sev. 3 - July 1981 ACCEPTANCE CR111tIA (158 acceptance criterte for the process and effluent redfelsgical monitoring lastrumentation and sempling systegs are based on meeting the relevent require-ments of the follewfag regulations:

A.

10 CTR Part 20, 520.106 as it relates to redloactivity monitoring of g

ef fluents to unrestricted areas.

General Design Criterlen 6* as it relates to tM radioactive vaste manage-g meat systees being designed to control release of radioactive materials 8.

1 to the ensf rennent.

General Design Criterte 63 and 64 as they relate to the rodfoactive vaste g

e management systees being designed to monitor radiation levels and leakage.

C.

Specific criterte necessary ta meet the relevant requirements of the Commission regulattens identiffed above are:

Prowlstens should be made for the instrumented monitoring er for the samp1tng g

and aaelyses of ou noreal and potentf al ef fluent pathways for release ofradioactive materials to the environment to meet Genera 1.

[

I See Benarke (t)

(1) reenydtoR later Cutde 1 7 e w

To meet Criterten 64, the design of systees should meet the prowlstens of ng to.ptesen 4 et et a tt. ga s.,,,,

Regulatory Culde 1.21 (Positten C and Appendf s A) (Ref. 2), Regulatory Guide 1.91 (Positten C and Tebte 1 or Table 2. as applicable) (Ref. 3),

estrpetett range are bet 4 esp

,a and gas ete nd moett to er betag and Reguistory Culde 4.15 (Positten C) (Ref. 4).

ased meet e requtr to of the e ject gulate Guide.

E The paseems aNi If geld process streams er efflueet release points should be evitated and sampled according to Tables 1 and 2-a.

I Whne Hfu u estet tue the w 3 dent For hath PWts and PWts, liquid utstes and confined volumes of geseous

• * * ** ** d " " "

• I" h.

l in ecceedene,

,t bases he g Wag t t de 3

waste should be lhepIFd L3tC M 1? FfffT 19 re ease, Continuous gaseous effluent monitors d tan eri ele are i e teace a tb the is on's

=tth Regulatory Guide 1.21.

are not required for open structures, such as PWR turbine buildings reswiad e allt b+

ovided by peember

1. 2 T

i er atmospheric vents for ifquid waste tanks containing treated or

&seef 6d YIs kie kh[

For Ifquid g ~3 processed liquid waste and located outside of butidings.

aad gaseous ef fluents that tennot be practicably monttered er sampled

[regh(g, l

=[ q %

g ge y

• g batchwise, one of the fellowing methods of representative sampilng N S Ma hMj..Ql.l T

l 2

should be provided:

A continuous proportioning sempffng systes with at least tuo gg,,,,,,,g#

{jSri

.f u m d and,e..e.e efri

.e.li.,

di.i....

net.rio,.nd e,

g (1) rhe syst,e shouid be designed to,r.-

se ee courtf.n tanis.

re-ided h.trh.

.e.

eide a n.ed or -asured no ratio.f the sa.ee conected to the sempied stre - discharge..r. aiternett.eiy 2e x s.,,e.e,e F A periodic automatic greb s==pliag systed utth at least tuo (2)

~

s pie conection te.*s.

The systes should be dessipied to 9

d 0

e

i WW3 D

rsAa TABLF l.0-1 MUREC - e40n i

NRC STANDARD REv!?v Flap e

COMPLTANCE SRPIACCIFTANCE CRITTRIA yts _po g/g gyygpgg II.s Frncess And Ef fluent Radiological Monitoring lastrumentatten And Sampling Systees (coat'd)

Rev. 3 - July 1981 collect a flued volume of sample at s'ra'te proportional to the seasured flow in the sampled streas discharge.

end g.%. teet monitoring end,* ipitas of Steste (3) Radioactive materials other than noble gases in gaseous effluents.

g g semark (1)

(1)

Redtof

.. ggg,,nto to provided beechetee.

A continuous sampling system with replaceable panticulate filter and radiolodine adsorber. The system should be designed to automat-teolly take samples at a fined or measured flow ratio of the spie throughput to the sampled stream discharge flow.

For f ateroittently operating effluent release points, the systre should I

g be designed to automatically take samples whenever there fs flow in the effluent stream.

For all of the above samples, a perfodic analysis frequency for the.

g collected samples should be specified to the technical specifications.

e t f

tot betwe the wpr.

7.

Prowlslons should be made for the instrumented monitoring of, or the I See Bemerts (t) and (2)

(3)

,re 4

,,t,,n,se

,,,orences

,,,,,,,i,

(,

periodic or continuous saapiln0 and analysis of. radleactive weste

,,,, 3 To meet Criteria 60 and 63. as they relate to radio-i

,gg,

,g, process systees.

I

,H uttu are la e lleen wt the t u lee, s active waste systees and detectfon of excessive radiation levels and Initiation of appropriate safety actions, the design of systees shoulg

" vlattooept be er d,4 6,see e tes J

seet the guidelices of Appendia 11.5-A (this 5ar section), Regulatory Guide 1.21 (Position C. as appilcable), Begulatory Guide 1.9F (Post-d g p. } Q.lf ( m /

@K b O

tien C and Table 1 or Table 2, as appilcable), and Regulatory Guide I

4.15 (Position C).

fe-Lawwam h

• m S 5

Prowlsions should be made to assure representative saepilng' from (yg/k f, $ "/ g,'g g f.

,3 x

a.

radioactive process streams and tank contents. Recirculation J

pumps for.18 quid waste tanks (collection or saeple test tents)

Qf g.

gg, should be capable of rectremiating at a rate of not less than J

twotankvolumesineighthours. For gaseous liquid process

%g{ f 2, g,g, 3, g, g stress samples, provisions should be made for purging sasple linesandforreducingplattoutinsamplelines. Provisions for caseous samplina rros ducts and stacks should be in agreement g

with ANSI N13.1. (Ref. 5) 3 Where practicable, provisions should be made to collect samples 2

b.

free process wasta streams at central sample stations to reduce in accordance wit $ and radiation exposures to operating personnel leakage, spillage SAP Section S.3.2.

Prowlstens should be made to purge and drafn sample streams back a

c.

to the systee of origin or to an appropriate waste treatment

..[

systee.

Prowlslons should be made for administrative and procedural control for necessary avulliary or ancillary equipment, and for special fealares 3.

t n

,:$IjE.

5 fii !!! 's 3

i!E !. "

e3 l:!:

'ie

'=

s u

x s

,M-f h 55$

!D

%?

' k

}I-

{$i i!!

1 O o

WF3 FsAR TAX E

1. s-3 arrt:. cyc sFO ** A. Me*t 87T!ral Pt ME E

crw81Y AKI se e

,ts e si > n str/acec7' art ittre!a II.s erece.e ama effiveet Beate1=etrol Dirtff9tIhg I$eTF e ettell9S ama 555$111g $y9ceSe ee,, 3 - J.1y 15a1 ster,eIe.een vue-yIseta=

fr %e*a) for the lastrumegted resfologtcal mattering sampli aM enalysis K

(1) nere ne ef process ami effleest streams. "fs meet Cr{terfoe 61,and Criterios ers(e ese saa ucegn6 ace crunte sprif tea a

c9 sar, be ee s a com tee et,s the opt-3 54, as t.6*y relate te rad.isactive maste process systees aN efflueet d elsa c sette a se

.tance g(th the test

's discharge paths, tM cesfy ef systees eV the leplementatlee of adefef 5*

1. ressigen. wat p e.e&ec by D( % r trative aM procesaral controls sheeld meet tw g(uidellmes of AppeedizFesitfee C) e M 3egule-e.

A tery G. de 4.15 (Pesitfea C) gulatery Gaide 1.21 II.5-A this 58F secties), fe Instuneetation, sanctlag, e"id somitselng previsfoes skuld confors to t%e following ogJ Sascity fret;encies, required swirses, festrument alarm' trio K

n-g 1

a.

setseinss, calfaration ami seasitteltf es aM previsises for preparing coupesite samples fer low-level a.alyses 5 Meld be la coefe save with tegolatory Guides 1.21 amt 4.15. Sagtfag fregaeacies aw! required acalyses sheeld be cf ree Is tM plant tectwitcal specificatfees; tMse previslens alli be reviewed at r

tM CL stage.

O b.

Frevisions skuld be eeje fet tM mecessa. Instraentation and g

o facillties to perfors gesss bete gamma g-ess alpha measurements, ise It aq1yses, aM stMr reattee avlyses la confersence with egulatory Geise 1.21.

Provisions sheeld be made to perfo+e roottne festrumeat calibee-

)(

1 e-2 c.

tien, mainteme, e"id lespections le confermerce with guidelines of tegulatery Guide 4.15. The fregaentles of sath actices skold te clees la LM plaat teckical specificetfees. The provistoes elli be reviewed at tM CL stage. Provistoes shes1d aise be se* to replace er decontaminate scelters withest opening tM pescess systes er lesig t*e capability to tselate tM ef flueet strees.

es, or diverslaa valves with aminaatic

[

d.

Isolation valres, Setpelats fer acteatles of astematic centrol features {tf a.

coetrol features 5 d fall le the closed er safe pes i Hilating 1

acteation of isolatloa valves, dancers, er diversion valves shesid t

non-EST 2

be estellsMd in the plaat tecluitcal specificatfees.

1*strimentation peevislees fer automatic tereinatlee er diversloe of releases sheeld confsrs to tM desip guidante contaired is

~

apeemffs 11.5-4 (this Sa7 section). EST testrumeetatfea peevistees fee

^

aetreatic teestmattom ee diversten of releases are reviewed f a 58P Sectfee 7.6 by IC58.

a.

Fre isieas sheefd be mede fee tM iestrerated somIteripg ee same11as e M emetysis of tdrettfled geseous efflaret paths le tM e, vet of posteisted occidmet releeses. To meet Critertem 64, es it relates s

.: T-I' -

'illE iji4:

-m IM P-3 TSAR Tastt 1.8-1 E q. 0900 grec $Talca3*) pfvffW F' Als Croft 1 ANCE -

t!PAJF3 775 iso s/a StP/accrptocg catTTt! A 12.1 - 12.4 9ealettee Preteettae Destaa Feeter**

Wev. 2 - Jety 103!

fraas'ai Ceaeral Cestga Criterfee 61 - feel Storage ead Mead 11 g end Sadie-y ectGTtTGatrol as it reTates to occieatieaal radiation protettien b.

aspects of feel steroge. kaadilag. todf eactive waste, ead other systees destgaed to assure aseteste safety durlag nereal and peste-

/

lated accident coadttlees, with switatie stifeldf ag sad ergrepelate 145 W g

coatef ament and filterf ag systees.

g"*'.****P** M'esseeces for t

s I

S+e temerk (I) 833 10 Cf t Port 70. Sectf ea 70.2a. *Crf ttcality Accideat tpf reseets* es It iiTetes ta prece4eres sad criterra for.saiterias TJ eriticality ecetdeats

-'~;n""

8.

levotolag specfal nuclear materfal.

A b

NI 4

The following eegulatory guides. Is)*fCs eM fndustry staaderds proeide taferse-tica. recewasatfoas and guiseace ead to general describe a basis ecceetable to tM staf f for fuglementtag the requirements of the regulattees 13=Mified

~

-I

[

above:

SeguisteLeter 1.1.

• Assumytf oas Lised fee fealeattaa the Peteatial fesiele'g~ ice Tease i See feest. (2)

(2) Not applicable to else.

C EsteYeeectors.quences ef a less-of-Cooleat Accideat fee Belltages T relates to asstattiens used in evaluatlag gaseems 1.

ceneatretleas of rodf oauclides le coateinment end pleat systees, felle= tag a less-of-coolaat eccide,t fee BWs.

the Peteatfal 8

Regulatory Calde 1.4. *Assu yttoas Used for Evaluatf TEET t er Pressurized 2.

IodioTogical Cease 3ueMes of a less-of-Coolea

@eWeeifeIs."es If relates to assumptfeas used la evalsettag gaseousconceatratleas of eedleauc11 des to containneat sad plant tag, less-of-coole t occident for Pws.

e.gvietery cetd, IJ. -centrei of cadustible ces teaceatestles la Costelement followly UWeTTeeleaI 12cTA

• is TI'FeTaTes LeIT6E Tif7eter raeag gase s coacAIrelleas.I radiemecisors in con-3.

l e

stelement fellenlag an occideat.

g 3

?

1

?*

f

4 's g *.

' u f.

E

, i M!M 6r! J F$As TAM E 1.8 3 NtstG - Ce00 NBC STANDAPD Rfvitu PLap CfsWLIA S R M ARKS 775 NO N/A St,Pfy [Fr_ TAN [E_cJ3 TF9t A 12.3 - 12.4 eedtattaa Proteetten Deelse Features Bew. 2 - July 1991 fra.e'd) h$

to aTyste. erceptib1$Te ITiitaf f for sei1TiiFIEitsiiTis. ten's requir e (t) seees ta, -we te e de +. red for sasr-3 segulatog Guide s.17 *Crtticality Accleeat Alare 5vstees

• as it relates n

s : - rt (t) to.

u.._::c :..: -...

$q, g'g gopgf,/f24 eents for e criticality ercldent ala o systee.

Regulatory Guide 8.19 'Occ tional Dese Assessmeat in tight-Water-11.

teaciaF rower Finafi'jiiT ~ iage En-fie Tstimiles." as it riTaferte a seGod accipli517s thi~

f rer p7. Te7 Tag is aisesseeat of collective g

occupational rediation e.se as part of the opgeing desten reefew process se that such espesures artil be ALADA.

(2)see aEI ae.ht, s. wwr.3 d,,t se which hee a I see seeerk (2) t NURIG-0101 *5tandard Techalcal specifications for Babcock and W11ces 12.

cz ns Frei'sTfiiiTsveieFrentisWas It relates te radTaUen protection con-ITderatioki IE~iEr siiti1(Tietitty, format, and taple entatten of the Sabenc6 and trtices Techalcal Specification package.

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13. M*fG-0123. "Standerd Technical Spectffcations for General Electfrc I see Fe.ork (2)

Set tf ag' water peecteesF~il.' ai TE riTiIes to rediatten protectlen c aiideralieTiln Si applicaEllity forest end Isylementatten of the General Electric Technical Specificatten pectage.

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• $tandard Techn cel Spectf tcetleas_for Casemstfen Engineerf as y see ee rg (3}

(3) y,,6,gc.i

,,,,ggg,,,,,,,,,gg 3,,,,,,,,,,,,,,,

MJefG-0717 j

14.

Pressurhe_IUaterReaHers, as Tt reTiteRe redTilfen protic1 Ten con-go,,,,,.. e, a, sidirations in tWarplicantitty, format, and toplementattee of the Centwstten fagtneering Techatcel specification package.

I 8" '*"*rk (2)

15. m*fG-0452. ' Standard Techntcal specificettens for Westinghouse

'.es.- cTied waterseacters.' as it FiTiles to radiatiin protectlen con-sidefillins TE tG-cilliantitty, foreet, and laplementetten of the a

Westlaghouse Techatcal Specificatten pectoge.

[

is. uvefG-071s sad mJefG-0737 es they reiste to taplementing task Action plaa x see se rt (4)

(s) II.r.1 witt be.ee prior to f=is pa-cr crerarten Ite.s IF.5:2 siI'TI.ETU) for coastruetten perett end operating Itcense e.d t o

, or n. re.,ec eive s,

,j app 11catleas.

I 17.

Aar51/Am5-Hp55C-6. s.1-1981 *tecetten sad Desten Criteria for Area mediatten see a*.ork (5)

(5) where es tference. +=s et between the unP-3 dest aa f

,.s for ITht beliTEcTiaTieseterj.* es it relates to erteeria e.d the ecce,.

,,criterne ad,eitried se RJ4TIiii 5

t T

iiiiiiiilar istiETTiGiitiTliciTTen. faFfined continuous area es==a this ser, the beoe. for e ci.atas thee the wur-3 deog e ertterte ore is ee.pliance with the ccom.testan's radiatlan sentters, and for design features and ranges of seasurement.

g regulatione util be provided by June 1991 5

18. A451 W131 1969 ' Guide to Sangling_Airtierne podteactive Itaterf als y

in Eiclear f acllTIIes.* ai Ti relates to the prisiipTes which appiy in J

WtiTnla 7gilGTamples of airborne redioactive materf als, out acceptable sethads sad eaterfels for ces sad particle sampling.

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W P-3 r$AR Tant r 1.0-1 winc - oong NRC STANriAFP RFVir JUAN M_1M SS P/ =* cF'Tuert CRITERI A TTS_le) n/A PFMA,er$

12.3 - 17.4 Bedtatten Preteetten Deelga Featuree. Rev. 2 - July 1981 craae*4)

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[of y

s,, y, rt fi) ggy g,,,gre,,,,,,,g.,

,,,,,,,4 g, mr. 9, 19 AN51 M16.7-1%9. "Celticality Accident Alare Systees,' as it relates to gu.ons e for the preventsen eTcriticeTity acct 3enis in the handling.

storiaa, processing, and transporting of fissionable materials.

Sea. m.,4 6o3-82-1324

10. ANSI miol.6-1977 ' Concrete Radiatten Shields.* as it relates to require-x medif a53 reiiss,aded practices for construclien of concrete radiatten e

shleiding structures.

• Deactor %leiding fee Nuclear f agineers3 88. Schaeffer, Editori r

71 Nbilih 3 bv WIc4TG1971,Gs if rilatn 13~IWiMeio desiping 1

Freiisi TscEars pTyiics, radiation transport, s>leiding calcuietlens.

speclet problems, and eaterials.

mor ana ischsr riar Nefert "N T IP 4.* n ft) wh,,,,,,,,,,,,,,,,,,,,,,,,,,eh,vor.3 4,,,i,.

reach for Llant tieter see e rm fr>

77.

sediatten Shieldicg ' Design sad Anaiysis

,,,,,,..eh,.,,,,,,,,,,,,,,,,,in,,,,,,,s.

seictor P G Fpia.is, lt viliiss tithi'ai, ruck ana 45Tectives a WshleYoesign aa3 th*

thee ser, ch.e th, uwe.1 4,.gg.,,,ch.

6..e.

rar conet.at.,,,g,.,,g.,, pitear, with the cat.elaa'e j

eethods of analysis employed in deteretning specific shleiding r **pa t re=*at s.

reewlettnae will be preytded by Juae le41, 1.

f4CIIIIY Of51Ds if4Ttef5 Acceptablilty of the f acility design features will be based er. evidence that the arolicaat has fulfilled the dose lletting requirements of 10 Cf R Part 20.101,

?S in), aad 24 Int, as well as the radiatten protection aspects of General Destyi Cr6teria 19 and $1, and 10 CFB 50 34.

This includes evidence that eajar esposere acrwulettag functions (eafntenance, refueling, radf aective eaterial headilag, processlag. etc.. In-servire laspection. calibretfen, decommisstening, sad recovery free occidents) have been considered in plant desloa sed that potentist redletten esposure from these activitfes will the tert AA Ata le accordance with 10 CFB Part 20.1(c) and Segulatory Guides 2.8 3

Such enes A Ift Dy restletion protectlen features incorporated in the design.

features say inclarte (1) ease of eccessibility to work and laspectlen and 1

semptf ag areas, (2) the ability to reduce source latensity, (1) design measures 3~

to redwe the preesctlen, distribution, and retention of activated corrosion pres >stts, f a) the ability to redure time required in radiet ten fleids, and (5) f Access centrol paaviola,eer pertable shleidtag sad reeste head 11ag tools.

well be pdged for ecceptability in accordance with the requirements of 10 CFR 70.70.1 or acr*** con. trol elteenatlees in Staaderd Technical Specifications f

- sioi, m. m. end Desn.

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Design *eatures to reduce maintenance, equipment downtime, leakage, or otherwise improve ALARA operation are addressed in Section 12.1.

De design activity inventories for shielding of GWMS components and the bases for' the l

l values are provided in Section 12.2.

Marther exposure reduction features are

. p::::p addressed in Section 12.3.

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l None of the GwMs components are designed to withstand a nydrogen explosion.

drogen and oxygen concentrations in the gas decay tanks, nitrogen recycle

)

i tank and gas surge tank are periodically monitored by the gas analyzer during periods when they are in use.

He gas analyzer also is connected to the spent i

i resin tank, CVCS holdup tanks, nitrogen recycle header, nitrogen recycle tank, 7

volume control tank and the gas s tripper to allow determination of hydrogen 3

I and oxygen concentration of gases entering GWMS components. He analyzer will j

i alarm on high oxygen in nitrogen or hydrogen cover gas tanks,4and on high l

hydrogen in aerated cover gas tanks. h e analyzer indicates when and where i

mixtures are approximately 50 percent of explosive mixtures to allow time to j

i take corrective, action. his action would consist of terminating the flow of i

improperly mixed gas and initiating flow of nitrogen cover gas to the affected f

j n components where appropriate. Se gas recombiner can also be used to remove

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any hydrogen or oxygen accumulation from the nitrogen recycle tank.

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he gas analyzer package is provided to monitor hydrogen and oxygen j

concentrations in various plant components where potentially explosiv.i i

mixtures could develop. He gas analyzer operates continuously by monitoring i

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through a programmed sequence of sample sources. Se gas analyzer is also l

capable of monitoring a single source for as long as desired by manually overriding the sequence selector.

Each sample source is purged, analyzed and l

l, re cord ed.

Continuous recording of sample concentrations allows for the detection and observation of trends which may be developing. Wh en th e analysis indicates that the hydrogen or oxygen concentration of a sample exceeds a pre-determined set point an alarm is annunciated.

. -r s,

11.3-2

WNP-3 1632W-5 pggg This monitor is located on the 362.5 f t.

eval of the Reactor Auxildary ~

~

Building.

It takes a sampic of the water discharged from the gas stripper and returns it to the same line. Physically it is a fluid stream monitor as described in Subsection 11.5.2.3.2, and it requires a sample pump. In this case the microprocessor has been removed f rom the skid and placed on a nearby wall to protect it from possibly high radiation fields present near tne skid.

The measured activity levels are automatically transmitted to the system computer where they are recorued and avaf iable for display through the system CRTs.

If the activity exceeds pre estaFI;,1,:?

setpoints an annunciation is made through the system CRTs and event typer. The receipt of these alarms will ' alert the operator so that additional radiation surveys, sampling and analysis can be ef fected in order to determine the cause of the problem. The ala rm setpoint s are to be set between the measured activity levels of the degasified reactor coolant and the maximum level of contamination pe'rmissible in this system. The setpoints may be adjusted continuously over the entire range of the monitor. The range of the monitor is from 10-'

t o 10 pC1/cc which is the practical range of interest f or normal power operation using a simple single detector radiation monitor.

e)

CVCS Letdown Radiation Monitor The CVCS letdown radiation monitor will alert operations personnel to an increase in the radioactive co. tamination of reactor coolant as an M

quickly as possible. 4 This monitor is located on the 373.5 f t. level of the Reactor huxiliary Building.

It receives a continuous sample of the CVCS letdown, in p,.rallel with the boronometer and is upstream of the purification filter. System process travel time delays the sample for approximately 2

two minutes delay to allow activation products with short half-liveg, particularly N-16 to decay.

Physically, it is a fluid st eam monitor as described in Subsection 11.5.2.3.2, which does not require a sample pump.

In addition, two modifications have been made, first the -

microprocessor has been removed from the skid and placed on a nearby wall to protect it from possibly high radiation fields present near the skid, and second a removable attenuator has been provided which may be manually placed between the sample volume and the detector.

The measured activity levels are automatically transmitted to the system computer where they are recorded and available f or display through the system CRTs.

If the activity exceeds pre established setpoints, an annunciation is made through the system CRTs and event typer. The receipt of these alarus will alert the operator so that additional radiation surveys, sampling, and analysis can be perf ormed l2 in order,to detemine whether the increase of contamination is due to damage to the f uel cladding or due to some other cause such as a crud burst or iodine spiking. The level of the setpoints will have to be adjusted periodically during operation to allow f or the gradual buildup of contamination in the reactor coolant. The cetpoints n.ny be adjusted continuously over the ent ire range of the monitor.

The range of t is

'e en - - -

Insert 1:

This monitor will be used in lieu of the liigh Range Circulating Primary Cool-ant Monitor required by Regulatory Guide 1.97 Rev. 2 for the detection of-fuel cladding failure.. Regulatory Guide _l.9/. recommends that Category I re-dundant detection systems be installed to measure this parameter. The recom-mended range is from 1/2 the Technical Specification limit up to 100 times the Technical Specificcion limit in Rads per hour. There is no instrument available to -accomplish thi2, additionally instrumentation in this range would be saturated by N16 Thus its capability would be unavailable until after shutdown.

0 9

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,1647W-6 ggp_3 FSAR There are f our of these monitors. The sample points f or two of them are jpeak located on the 362.5 f t.

level of the Reactor Auxiliary Building. One of Erm these samples air being exhausted f rom the north side and the other samples air being exhausted f rom the south side of the 335 f t.

le vel. The other two sample points are located on the 390 f t. level of the Reactor Auxiliary Building.

One of these samples air being exhausted f rom the north side and the other f rom the south side of the 335 f t. and 362.5 f t.

le vel s. The air samples are withdrawn f rom the exhaust ducts through a multipoint isokinetic sampling nozzle array (per ANSI 13.1) f rom a point downstream of the confluence of the ducts carrying exhaust air f rom the area being monitored.

In each case the sample is routed to a skid mounted radiation monitor that is located within a f ew f eet of the sample point. The sample pump is mounted on the monitor skid.

Physically this monitor is a two stage airborne monitor as described in Subsection 11.5.2.3.3.2 which uses a mosdng particulate filter.

The measured activity levels f or both the particulate and gas channels are automatically transmitted to the system computer where they are recorded and a seilable f or display through the system's CRTs as described in Subsection 11.5.2.

If the activity exceeds pre established setpoints an annunciation is made through the system's CRTs and event logger.

The receipt of these alarms will alert-the operator to the. presence of an unusual level of airborne radioactivity coming f rom a paricular area so that additional surveys, sampling and equipment isolation can be ef f ected in order to locate and control the source of the contamination. The setpoints mhy be adjusted over the entire range of the monitor. Additional inf ormation about N k'I l this monitor may be found in Table 12.3.4-2.

Immy (mm=r.

12.3.4.2.3.1.2 Control Room Air Intake Radiation Monitor

'~

The Control Room air intake radiation monitors provide plant operations

ersonnel with measurements and records of the radioactive contamination of air entering the Contrul Room ventilation system.

If the measured contamination exceeds pre-established limits these monitors produce a signal to automatically isolate the Control Room air intake and thereby protect the habitability of the Control Room.

These monitors. are located in both the Control Room air intake plenums which 1

are on the 442 f t.

level of the Reactor Auxiliary Building.

Ref er to Figure

12. 3-Sa. There areta total of f our monitors, two in each of the two plenums.

7 The' detector assembly f or each monitor is mounted f rom the plenum ceiling and observes air downstream of the tornado missile protection but upstream of the intakes isolation valves louvers. This location permits the continued observation of the contamination of the outside air af ter the intake has been iso;2ted.

l Each Control Room air intake radiation monitor is similar to a ref ueling pool l

area radiation monitor (Subsection 11.5.2.4.11) except for its detector i

I assembly and some changes in its microprocessors sof tware.

A schematic diagram of one of these monitors is shown on Figure 12.3-32.

These monitors are seismically qualified, Cimss IE and powered in pairs f rom the A or B saf ety busses using the same bus as their respective air intake.

12.3-32_

s

Insert 2 These monitors, which can detect airborne radioactive material leaking from containment will be used in lieu of the intermediate range Area Radiation Monitors recommended by Regulatory Guide 1.97 Rev. 2 for detection cf a Con-tainment Breach in areas with penetrations and hatched (Type C variable). An increase in radiation levels in these areas would be due primarily to stream-ing through the penetration or direct shine from the containment caused by elevated exposure rates inside containment. Any additional increase due to airborne radioactivity leaking from the containment would not be discrimin-ated by the area radiation monitors sugg'ested by Regulatory Guide 1.97 Rev. 2 from streaming or direct shine.

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1219W-7 WNp-3 F5AR n.

fji5i SIS recirculation sump to the suction of the engineered saf ety f eature pumps.

NEE!F The stainless steel pipes are welded to the carbon steel pipes at the SIS recirculation sump so that water cannot enter the annulus formed by the concentric pipes.

Outside the containment the stainless steel pipes cre seated to the guard pipes by means of a stainless steel bellews. The bellows seal allows for anticipated diff ernntial movement due to thermal or seismic forces.

The SIS recirculation sump isolation val ses, Tag Nos. 2CS-B00lSA and 2CS-8002SB, used in the recirculation lines are of the Butterfly type.

To ensure containment integrity in the event of stem leakage the valses are provided with two f ull set. of packing separated by a lantern ring sad a leakoff connection.

Each set of packing is capable of withstanding the system design conditions without visible leakage. The leakoff piping is 3/4 inch schedule 40S.

Isola tion val ves, Tag Nos. 2CS VS330SA 'and 2CS VS331SB a re provided in the leakof f lines.

A temperature element is provided in the leakof f line which wil1 provide an alarm in the Control Room if there is stem l ea ka ge.

The leakof f piping up to t.he leakof f isolation valves including the 1

associated instrumentation is designed in accordance with ASME Section III, Code Class 2 requirements. The leakof f isola tion valves a re normally open.

When stem leakage occurs through the first set of packing the temperature rise in the leakof f line will actisate an alarm in the Control Room to alert the g

ope ra to r.

Administrative procedures will require the operator to isolate the leakage by closing the leakof f isolation valves., Extension stems are provided$eth I

in the isolation walves to permit remote manual operation f rom a shielded area

.,7,,,,

f or protection of operating personnel.

Isolation of the leakof f valve and the 6;;;;-

second set of packing in the main vnive will help maintain the containment SUsl:T integrity with no leakage of sump water in the Reactor Auxiliary Building.

The containment sump isolation valves are conservatively designed to prevent any steam packing assembly blowof f ef f ects due to excessive pressures. The wilves are designed in accordance with class 150 pressure temperature rating requirements. The system design pressure is.50 psig. To ensure packing integrity the compression of the permanent packing will be checked every refueling cycle.

The primary source of post accident debris tlmt could be generated inside the containment and which could potentially clog the SIS sump screens, would be the disintegration of thermal insulation that is provided for equipment and piping. No other type of debris is expected to clog the screens or prevent in any way thu flow of water. The WNP-3/5 design utilizes two typeu of fasulation inside the containment. All piping and equipment that are part of the Henctor Coolant Pressure Boundary, including the secondary side of the steam generators, use metallic reflective insulation. Table 6. 2.2-3 sumuurizes the type of innulation and the quantitics f or all equipment and rl ping inside the containment.

The materials of construction of each type of insula tion a re listed in Table 6.2.2-4.

pe rma nent insulation assemblies are attached by stainless steel straps and f asteners of the expansion type which prevent overstressing of the lur.ds or 1

da mage to the innulation coverings due to thermal expansion of the equipment l

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/kC fll ICI s o e

s 4

Insert 3 These temperature detectors will be used in lieu of the intermediate range Area Radiation Monitors required by Regulatory Guide 1.97 Rev. 2 for detec-tion of Containment Sump Leakage past the packing of valves 2CS-B00lSA and 2CS-8002SB (Type C variable). -In an accident resulting in failed fuel, and l

when the Containment Spray pump and LPSI pump are used for shutdown cooling, extremely high radiation fields could exist in this area. Any additional ex-posure from the 3/4" leakoff line would not be detectable, even with lead collimation.

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9 6

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