ML18078A857

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Requests Proposed Change to License DPR-70 Re Safety Tech Specs (App a) Involving Section on Containment Structural Integrity.W/Remittance of $1,200 for Class II Amend
ML18078A857
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/16/1979
From: Librizzi F
Public Service Enterprise Group
To: Schwencer A
Office of Nuclear Reactor Regulation
References
LCR-79-03, LCR-79-3, NUDOCS 7902220028
Download: ML18078A857 (8)
v • d • e


Text

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Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 Ref. 79-03 February 16, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Gentlemen:

Mr. Albert Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE DPR-70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analysis of the changes to Facility Operating License DPR-70 for Salem Generating Station, Unit No. 1.

This request consists of a proposed change to the Safety Tech-nical Specifications (Appendix A) involving the section per-taining to Containment Structural Integrity.

This change has no safety or environmental significance and is, therefore, determined to be a Class II amendment as defined by 10CFR170.22.

A check in the amount of $1200 is enclosed.

The next Type A leakage test is scheduled for the upcoming outage (commencing on March 31, 1979).

Since the proposed change influences the conduct of this test, we request that you complete your review of this amendment by March 31, 1979.

This submittal includes three (3) signed originals and forty (40) copies.

79022200:<~

The Energy People Very truly yours, F. P. Libr' i

General Manager -

Electric Production 95-2001 (400M) 9-77

Ref. LCR 79-03 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-272

  • PUBLIC SERVICE ELECTRIC AND GAS COMPANY FACILITY OPERATING LICENSE NO. DPR-70 NO. 1 UNIT SALEM GENERATING STATION Public Service Electric and Gas Company hereby submits proposed changes to Facility Operating License No. DPR-70 for Salem Gen-erating Station, Unit No. 1.

This change request relates to Safety Technical Specifications (Appendix A) of the Operating License, and pertains to the section on Containment Structural Integrity.

Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY By:

FREDERICK W. SCHNEIDER VICE PRESIDENT

)

SS:

COUNTY OF ESSEX

)

FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the request for change to FACILITY OPERATING LICENSE NO. DPR-70.

The matters set forth in said change request are true to the best of my knowledge, information, and belief.

Subscribed and sworn to before me this l,-a day of rk... ; ' 1979.

Jersey

. My commission expires on b

~ 1113 BARBARA VALLEE A NOTARY PUBLIC OF NEW JERSEY My Commission Expires Nov. 8, 1983

PROPOSED CHANGE CONTAINMENT STRUCTURAL INTEGRITY TECHNICAL SPECIFICATION SALEM UNIT NO. 1 Description of Change Ref:

LCR 79-03 Change the surveillance requirements of the section on visual inspections of the containment structure to be con-sistent with the current, approved, version of the Westing-house Standard Technical Specifications.

This revision will also conform to the requirements of 10CFR50, Appendix J.

Reason for Change The current surveillance requirements go beyond the require-ments for visual inspections of the containment structure as specified in 10CFRSO, Appendix J.

Conformance to the cur-rent requirements would extend the critical path of the outages in which the Type A test will be performed.

Safety Evaluation The revised surveillance requirements conform to the require-ments of 10CFRSO, Appendix J and have been accepted by the NRC in the current version of the Westinghouse Standard Technical Specifications.

Therefore, this change does not involve an unreviewed safety question.

  • I I

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION 3._6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200°F.

SURVEILLANCE REQUIREMENTS

/

4.6. 6.1 Concrete Surfaces The structural integrity of the concret_.e/

surfac shall be demonstrated by determining through inspection _tjtat no apparent anges have occurred in the visual appearance of th oncrete exterior su aces or the concrete crack patterns. Inspect*

s of the concrete shal be perfonned during the Type A containm leakage rate tests (referenc Specification 4.6.1.2) while the con ainment is at its maximum test pres re.

4.6.1.6.2 Liner Pl at The structural inte~*ty of the containment 1 iner pl ate shall be de mined during.. tile shutdown for each Type A containment leakage rate t t (refe ~hce Specification 4.6.1.2) by a visual inspection of the pla a

verifying no apparent changes in appearance or other abnormal radation.

4.6.1.6.3 Reports An.j~1tial of any abnormal degradation of the containment structur~*:-'detected during e above required tests and inspections shall;.te made within 10 days fter completion of the sur-veillance re

    • ements of this specificati and the detailed report shall bes mitted pursuant to Specification 9.1 within 90 days after comple
  • n.

This report shall include a descri

  • on of the condition of the ncrete, the inspection procedure, the tolera s on cracking, and corrective actions taken.

.SALEM - UNIT l 3/4 6-8

)

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CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY (Reinforced concrete containment)

LIMITING CONDITION FOR OPERATION 3.6.1.7 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.~.1.7.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not confonning to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.7. 1 Containment s'urfaces The structural integrity of the exposed

  • accessible interior and exterior surfaces of the containment, including the liner plate, shall be detennined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of these surfaces and verifying no apparent.changes in appearance or other abnonnal degradation.

4.6.1.7.2 Reports Any abnonnal -degradation of the containment structure detected during the above required inspections sha1l be reported to the Commission pursuant to Specification 6.-9.l.

This report shall include a description of the conditon of the concrete, the fnspection procedure~ the tolerances on cracking, and the corrective actions taken.

\\

~-ATMOSPHERIC 3/4 6-lOAAA March 15, 1978 1,

l

(

PART 5IJ e DOMESTIC LICENSING CfF-PRODUCTIOt~rAND UTILIZATION FACfi.ITIES

  • ~~

~

low. H*is reasonably achievable* If lhe appli pro~dH reasonable assurance lhal the pro hi&her quantity will nol result in annual doses 10 an individual in an unresuicted area in cxces.'

of S millirems to lhe total body or IS millirems to the skin.

- <:. Por ~

10CIUI* IU)d r>dlQllCttT*

atanal ID,parttcul&ie form UoH ~ack

~Wl'1 relsaeod to ~e atmmphm:

'. L

'1"he.calc:ula~ &D.D!-Jal &ot&I quanttt7 af

'att rsd1oac:C1V11 lod!.ne &Dd radlOM:tl'H m&-

-.n.ol m ~~

form nom all 11e1:1t-

--*.-1$CI. :awclear power rellcilor11 at a ate lllit>ultl nat.r-e.u:: 1n aD annual dOM or dCM

~~at.

to* -T mp.zs of.. wdln~

.a4ZI 'UJ!fJ~lc""1 ares trom all. paUtwaya ~

~

.1D -cems ot 15 mJ.lllr*ma. llil dew-

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lhe* cloee or dOM commlt.zi:imit. Ula portk>n thereof due to Intake ot r~o&C't11'e APPEJnta: :S ftlllAllT aEACTOa CONTAIJfllElfT LZAltAGI: ftn'*

DIG l'O* WATl:ll-COOl.D rowa ll&ACTOU I. Introduction.

n. Esplanatloll of tenna..
m. Leaka.1e test. requtnmenta.

A. Type A teat..

  • . 'l'YP*. \\at.
c. T'7i>e C teat.

D. Penodlc retest acb.eduJe.

IV. Spec!&! test requlremez:ita.

A. Conta.lnment modUka.tlom.

B. Multiple leakage-barrier contalz:imenta.

V. Inspection and reportm1 ot teat.a.

A. Containment Lnspectloll.

B. Report of test reaulta.

I. IJmlODVcnDK

~

1'la *tie food patt....,.. ma.7 be One of the condltlona of all operattnir

~ e'l'a~~ as Cle Jocst1oca wbfte t:h* food Jlcense1 for water-cooled power reactors u

~ path_,-1 ao~

  • ni.t; &.Dd.

spectfted ln I so~t(o) ta that prlma.ry re-v

  • - !l.: 'rbe calculaW a.nnt111il ~

tt~nttty 11etor containment.a *hall meet the contaln-lr or ~lSl In g3MIOU3 emuents lbould not ment lea.kage test requlreme::.ta set. forth LI. ~

1 ruie *r~ esch Ught-water-cooled In this appendlit. These test requirement.a o

nuclear power reactor at a site.

provide for preoperat.lonal and periodic Teri*

~

JS. Not.wtthsta.ndi.llg the guidance *1n para-11ciatlon by test.s of the lealc-tlgb.t Integrity grapb.s C.l -and C.2 !or a partJcula.r site, 1t an o! the primary reactor conu.tnment, and *JS*

6pipll~ r~*a pe:mtt w oonstruct a light*

t.ems a.nd compon*nta which penetrate con-

  • ~:.U<Cioied :aulllea: power R&etar boa pro-talnment of water-cooled power reactors,

,poad;bucftlne ~la.12t eoutrol measures Sto and esta.bllsh the acceptance criteria for re~ce 'the po;w;lbl* sources of radioact.ln auch test&. The purposes of the tests are to lodllle *.1:el.!llllli.ea, and tb.e calcU1Ated ann.unl assure that (&) Jealcage through tb.e prl-qua:itttles takl~g Into a.i:cou:nt. 11uch control mary reactor containment and systems and mee.sures exCffd tb.e dein;n objec~rn qua::i-components penetrating primary contaln-tlttes a; for1:r. tn p:i..."11.graphs C.1 and C.2, ment shall not exceed allowa.ble leakage rate the requirements for deelgu o?1jectlves for Talues a& 11pecll1ed In the technlcal apecl*

udJaact11'e Iodine an4 rad'1oaatln matenal ftcaUons or associated bases and (b) periodic ln partlctil&te form 1n gaseous emuent.a may 1urvell!ance of react.or containment pene-be deemed to have beeon met provided the tratlons and Isolation Talvea ls performed c:a~ul~ annual totaJ quantltJ of all ra-so that proper ma.lntenance and repairs are dto&etlft Iodine and rad1o9Ct1n matertal In ma.de during the service Ufe of the contain*

particulate form that may be releAsed In ment, a.nil systems and com;:ionents pene-ga.seou.s emnenta d~ not e~

tour times ~ tz-atlng primary containment. These teat.

the quantity calClllat.d pursuant to para- ~.requirements may also be used for guidance s;:~ CJ Ir In est11bllshlng appropriate containment 1.1. leakage test requirements lz:i technlca.1 specl-m 11catlons or associated bues for other t;pe1 M or nuclear power react.on.

5 Such in-plant control measures may include treatment of steam generator blow-down tank exhaust, clean sream supplies for turbine gland seals., condenser v:icuum systems, containm1ml purging e"hausl and ventilarion exhaust systems.

and i<peci3! design features to reduce contami*

n:1ted sream and li4uid h::ikage from valves and other sources such as sumps and tanks, as ap*

propriate for !he rype of reactor.

ll. EitPLAMATlOM OF 'l'EallU A. **pnmary react.or containment'" means the structure or vessel that encloses the com-ponent& of the reactor coolant pressure boundary, as del1ned ln I S0.2(v). and se"es as an essentllllly leak-tight ba.rrter agalnat the unoontrolled relea.se of radioactivity.to the environment.

B. "Containment lsola.tlon T&lve'" mean.s any valve which ta relied upon to perform a coz:italnment Isolation function.

c. "Reactor c:onta.lnment leakage test pro*

gram" Includes the performance ot Type A.

Type J;I, and Type C testa, de.scribed In ll.l",

II.O, and II.H, respectively, D. "Leakage ra.t.e** tor te.st purposes la that leakage which occurs In & unit o! t!me, stated as a percentage of weight of the original con-tent or containment a.tr at the leakage rate test pressure t.hat escapes to tbe outside atmosphere during a 2t-hour te5t period.

E. "Overall Integrated leakAge rate" means that leakage ra.te which obta.lns from a sum-mation or leakage through all potentl&l leak*

a.ge paths Jncludlng containment welds, valves. 11ttlngs, and components which pe.ne-t.rate containment.

P. "'Type A Tests" means tests Intended 'to measure the primary reactor containment overall Integrated leakage rate (1) after the containment ha& been completed and ls ready for opera.tlon, and (2) at periodic. intervals there~ter.

G. "Type B Tests" means tes~ Intended to detect local leaks and to mea,sure leakage across each pres.sure-containing or leak.age-llrnltlng boundary for the following primary reactor containment penetra.tlons:

1. Containment penetratlo.U wnose design Incorporates resilient seals, g!ISkets, or sealant componcls, piping penetrations fttted v.1th ex-pansion bellows, a.nd electrical penetratlor.s 50.39 with ftexlbl* meta! aeal...... mblln.

. Air lock door aeala, tac!Udlng.door operat.

ln1 mecha1:11am penetration. w.blch are part ot the containment preuure bou1:1dar7.

I. Doors with resilient Hall tw paket.a e:ii:-

. cept tor ae&l-welded doora.

t. Componenta other th.a.n thou listed 111 1 D.0.1, ll.G.2, or II.0.3 which muat. meet the ac:cepta.nce crtterta In III.B.3.

B. Type C Testa" means tests Intended to measure containment Isolation yaJ*re lea.ltage rat.es. Th* containment. taolatlon T&lves ln*

eluded a.re t.hoae tbat:

1. Provide a direct connection betweea the Inside and outside atmosphere* of t.he pri-mary reactor contalmuent uz:ider normal op*

eratlon, aucb aa purge and TentllatloD, T&euum reJlef, and lnatrument v&IYCs:

2. Aze required to close automatically upon receipt of a. containment Isolation signal Ill res;xmse to controls ll:lt.ended to e!rect con*

t&lm:~ient lsol&Uon;

3. Aze required to.operate lnten:alttenU7 under posta.c::ldent conditions; and
t. Are In main steam a.nd feedwater pip~

and other syate"~ which penetrate contain-ment of direct-cycle bolling water power reactorw_

r. Pa (p.s.1.g.) means the calcula.ted peak containment lnternM pressure rela.t.ed to tbe design basis accident and 11peclaed e:th.er In the technical spec~c&tlon or &s6oclatcd bases.

~- Pt (p..s.l.g.)

m~ns the containment.

Tessel reducl:peetlon tn accordance with V.A. shall be p"rtorm"d as a prrrequ_!S.lt~.

to he erformance of T\\"pe A tests.touring the per10 i>eTweerit'hemtt"l:t1!v"'ilo?"the con-t:iinment ln!'-pection and the performance or the Type.A test, no repairs or adjustments shall be made so that the C'o:ila.lnm.. nt can be tested In as close to the "IW Is" condition as practical. During the period bet"O;een the September 1, 1978 l

.,_PART 50 e

. ~

DOMESTIC LI.SING OF PRODUCTION AND.LIZATION FACILITIES.

l'l':::!.:>r shutdow:i !or re!uellni;. or other co:1-ve1~it'r.i. lnt.eT\\*als. bui.In no c:i.se at. Intervals l:~!lter than 2 )"e!lrs. Atr locks lhall be tested

it G-mon:?t tntt'rv!lls. Howevier, air loclts

,,*:1i~h :ire o;:ie::ed during.such lntcr\\*ala, shall h<* tr,.ted a!ter each opening. For primary rc:i:i.or C'onralnn1ent penetr:i.tions emplorlng

a. co:-.tmuous le:i.i<:i.ge monlwrlng aratezn, T~-p~ B tc.-ts; except tor tests o! air locks.

ma,*. notwl:hst:1nding the test sch.:dule spcc-ll\\pd u1~der III.D.1., be per!ormed e\\*&ry other rPac::or shutdo"'*n tor refueling but !n no csse at lnter\\*als gre:i.tcr than 3 year.s.

3. Ti;pe C ti:stJ. T)-pe C test& shall be per-ror1ned during e:i.ch reactor 11hutdown !or re.-

fueling but In no case at !ntenala creater th1.n 2 :rears.

IV. SPl:ctAt. TESrlNG REQ11UZ:ll:ICNTS A. Contllinmmt modification. Anr major

  • modlftcatlon. replacement. ol a component whlc:h. 1s part. of the p;lm:lry rea!:tor con-t:i.ln:nent boundnrr. or resesllng
11. seal-

"'*eJcted c!oor, per!e;1*mec1 11!ttir the p:-eoper:i.-

tion:i.l ll'akage rate test sh11.U be followed by either a. Type A. Type B, or Type C test, as app!lc:11ble !or the are& alrected by the mor:11-11c:ition. Tbt! measured leakage Crom this test sha:t be Included in the report to the Com-mission. required by V.A. The accept:i.nce cri-teria. of III.A.5.lb). III.B.3.* or III.C.3.* P.S 11.p;:iro;n:*i11te, sh:i.ll be m:t. Minor modUica-tions, rcplac.-mei1ts. or reseiillug of aeal-v:elded duors, per!or.ne!S directly prtor to the c::mciuc:t cf a scheciuled T)l>e A test do not requ;re 11.se~arate test.

B. i.tlultiple leakage bamcr or 1ubatmos-pl1n-ic colitainments._ The primary reaci.or containment barrier or a multiple barrier or subatmospheric containment shall be sub-

g Jec:ed to Tj"pe A tests to verify that its leak-

~ age ra.te. meet.a the requirements of tbla a.p-a: pendiic. Other structures of multlpllt barrier

~ or suba.tmospheric containments (e.g., sec-

= ondar; containments !or bolling water rea.c-r; tors* a.nd. shield buildings for pressurized 1 w::i.ter reactors that enclose the entire prlm&ry reactor* c:ontaimnent or portions thereof) shall be-subject to Individual te!ts in accord*

ance With the procedures 11peclfted in the tec11nica.l ::peciftcstlo:'lS, or associated bases.

V. I:.o::.PEC.;"101'1 AND REPOP.TINC OF TICSTS*

A. -Con*~,;t i11spectwn. A. general tn-sp~::tcn of the acce,;sii:ile Interior and exte-nor sur!aces or the c:mte.inment structures a::ld component& sh11ll be perrormed prior to any T;pe A test to uncover any evidence of structun1l deteriorallon which ml\\Y al!'cct either the containment structural integrity or leak-tightness~ I! there Is evidence of

  • structural deterioration, Type A tests shalt not be performed until corrective action ts taken in nccorda.nce with repair procedures.

nonc!estructlvie examinations, and tests as specified In the applicable code speclfted in I 50.55a. at the commencement ot repalr work. Suell struc:tural deterioration and cor-recth*e actions taken shall be rep::irted as pa.rt o! the tei.t rti11ort, submltt.ed In accord-ance with V.B.

B". RC'port of test re~ults. 1. The preopera-tlonal a.nd periodic tests shall be the subject o!. a summary technic:nl report submitted to leakage r.* !e test cS:ita for the Type A te.;;t resul t.s " the extent n~cea&ar; i.o demon-strate the acceptability or the cont.:i.lnrnent*a lHkage rate In mec:;lnit the accept.me, criteria.

3. Por H!:h prrlcxtlc test, le:i.k11ge teat re-a:1tts Crom T~-pe *'* B. a*1d C tests &hall be re-ported. The report sh::iil contain an analysis a:1d lnte:pretatlon o! the Type A test relulu and a 1ur.1mary an11.l;s1s or periodic T;pe B ltl a.nd Type C tests thAt were pertormed slnc;_e

~ the la.st Type A test.. Leaka£e test results

~ from '1'3'pe A, B, and C tests that !Ailed to ff: meet the acceptance criteria. or llI.A.5(b),

CD Ill.B.3, a.nd III.C.3, res;>ectivelr, ahall be re-M ported In a separate accompanying summary nport that Includes an analysis and lnter-pretatlon of the test data, the least-sqtiares ftt analrsls o: the test data, the Instrumenta-tion err.>r 11nalysis, and the structural condl*

tlor1s o! :!le containment or componients, U any, 111*l:kn contr!buted. to the !allure ln meeting the :icceptance criteria. Results and an11!yses of the supplemental vertlficatlon tes: emplored to demonstrate the v::illdltr o!

the Jei1.l<age rnte test n1P:isurernents shall also bo included.

the Director of Nuclear Reac1or Regulation. U.S.

Nuclear Regulatory Commission, Washington.

D.C. 20555,t *appro"l(imatel)' J months arter the conduct or each test. The report sha.ll be titled '"ReRctor C.:>ntslnment Build-ing Inregrnted Leak Rate Test."'*

Cr

2. T!ie report on the preopernt1on11l test shall lncl11de 11. schematic arrangement ot the leakage r:i.te measurement. system. the. ln-struri~e::ltatlon used. the supplemental test method. a.nd the test pro;r:i.m selected a.s ap-plicable to the preoper:i.tional test, and al!

suhsequent periodic t~sts. The report shall co:Halr. :Ill a.nalrsis :i.nd i:iterpretatton o! the Am.,nd"d 38 FR 5997.

tAmended 41 FR 16445.

50-41

~IZ lt-ZCCS Jl:YAL174TmN Mon:.s L Required aad Acoeptal>:e l'eatu.rM ot E'!"a?uatl.oa Model..s.

IL Required Docwnentatlo12-z.. Sl:Q17tllED AMD ACC'C'TAJIU J"!!AT'lnU OP TIO l:'l'Al.VAnO~ KODICLS A. &ouroe* of 1&Ht dt.trtnv the.tOCA. l"or th* beat aourcee llsted tD p&n.gT"apbs 1 to 4 bel07 It llhall be asau:ned ~!)at tbe reactor h!!.S been operating con,l.tluoualy At a power level at 1".st 1.02 tlzne* tbe l!cell.5ed power le-rel (to allow for auc:i:. uncer"'..&1.Dtlea u l.C*

stl'\\Jmentatlon. error}, Yttb the mu:imum peaking factor allowod by tbe t.eehntcal meel.Acatton.s. A range o! po"lrltr cUstl"!button.

ab.apes and peslclng taci.ors reproesentlng power dl.str1but1on.s that may occur o-nr tbe core litettrne sb !Ill ~ a:uc!led a.nd t!:le o:ne

&ele<:ted ahould be that which ~ul~s l.n. tt.e most severe calcu!ate-d eonseauences.- tor the spectrum ot postulated breaics and Wigle ra.uures analyzed.

?. The Initial Sklr!!d Enl!T"~Y tn the Tiul.

Tbe ate-!l.dy-state temo-en:ure dt.atri!>u,loD.

and stored e:nergy 1D the fuel be!cre the !ly-potbetlcal accident shall t.e c::i.lcu!a::ed for th" buni-up that ;telc1s \\be blgb=it calcu-lated ciaddl.ng tecperature ror. op~!onall::".

the hlgbes:.:a.lculaud r..o~d ene,:n.) To a.ccomp1Uh tbl..s. the tl:len::ial cond~ct1v1t.y ot the 'C'O. &ball be eniuated a.s a runctto:i f1!

burn-up and temperature. te.ltlng ID.-:.O con-alderatlon dl!rerences In ln!t!al dens::y. and the thermal conductance ot ~e gap bet.~n the UO, and tha cladd:.ng aba!l be r.&!uated a:i a function of the b:un-up, takU1l l.nto consideration fuel de~catlo?:? and e:i:paD*

sion. the composition and pre!l.SUre o: t.b.e p.ses w1tb!Z1 the fuel rod. the Initial cold pp dtmenston With 1ta tolera:icea, a.nd cla.ddl.ng creep.

2. FisS'!m!. Heat. Pts:s!on heat shall !)e ca.l-g culatl!d using resctlvity *!ld reactor lt1nettc::s.

Shutdown reactivities re.suttmg from tem-a:: perature5 and voids shaU be gt~e::. the!:

i.. minimum plausible va!ues, lnclud!.!!g allow-

~ ance !or uncertainties, :or the ra:ge or P-'we:-

dlstrtbutton shapes and pealct:o.g rac:o~ 1!1-d!cated i.o be studl.ed above. Rod tr1p &Dd !.J:l.-

sertlon may be a.s.su.aied I! tbey a.re calcul&~

to occur.

3. Decav of Actinides. Tbe beat from the ra.dt06cttve *decay of aetlnldes, tncludt:g neptunium and plutonium generat.?<t du.."'1:cg operation, a.a well a.s Isotopes 0: u..-s:l!um.

1 shall be calculated IZ1 a.c:cardance wtth tuel cycle calcul.atlollS and kno= rad!O&Ctlve properties. Tbs actinide doca:; heat cboee~

man bit that appropriate fOC' the tbeo !.l1 t.lle fuel cycle th&t ytekla the b.!g:est e&lcul.a.ted fuel temperature during th& LOC.<\\.

t. Fisricn Produ.ct Decay. n:e bea: gen-eration rates :!'rom radlc&et1ve decay or Cs.stc:i products shs.11 be assum~ to be equal to 1..2 times tile vaJue11 tor l.IUinlte cpera~ time ID the ANS Standard (Propoae<l Amer1c:&A Nuclear Society StAndard$-"'Decay Energy
Release Rates PoUowt::.g S?l.utdo**n:1."

o!

'C'ranlur:n-Fueled Thermal Reactors". A?-

proved by Subco=lttee ANS-S. ANS Stand-

.ards Committee; October 11171). The ~

tlon ct the locally generated ~

energy t?:at ls c!eposlted ID the !uel ( IJ:clud:..Cg the cl&ddlug) may be d~ere!lt from 1.0: t!:le value used ahall be ju.stUied by a. suitable calculation.

S. Metal-Water Reaction Ri:te. The rate of energy relea..s., hydrogen ge::e~tlou, and claddl.,g oxldat1011 !rem the me:al 'wa.:~~ re-act ton shall be caJcul11ted uslllg the B:i.ker-

.Just equation (BS.:-er, L. *.Just, L.C.* **stt::1Jes or ?.fetal Water Reactions at High Te:n;:i~:-a tures, m. Expenmel!tal and Theoretical Studies or the Zlrc:o11ium-\\>a:e:o Resctlon.'"

A?.'L--6548, "page 7, Ma.y 19o2). The reaC't!o::i sl::l:ill be assumed not to be st..a:n li.::tl~ed. Fo:-

rods whose cladding Is c:alcu.la.:ed t~ :n.:pture during the LOC.\\, the Ir.side c! t!"le c!:.:!d!:ag shn.11 also be o.ssumed t<:> react a.!t~r tl:le rup-ture. The cnlculatio!l ot the reac:t1011 ra~e o::i.

September 1. 1978

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