ML20105C621
| ML20105C621 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/15/1983 |
| From: | Liaw B Office of Nuclear Reactor Regulation |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19303B912 | List: |
| References | |
| NUDOCS 8312230321 | |
| Download: ML20105C621 (11) | |
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DEC 15 i_:5 Docket No. 50-416 MEMORANDUM FOR: Cecil 0. Thomas, Chief
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Standardization & Special Frojects Branch
.~. Division of Licensing
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FROM:
B. D. Liaw, Chief Materials Engir.eering 3 ranch Division of En-ineering
SUBJECT:
PROOF AND REVIEW 0F GPAND GULF UNIT 1
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. _ _' :.... TECHNICAL SPECIFICATIONS _
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As requested by your letter dated Oct ber 4,1983, the Materials
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Engineering Branch, Division of Enginee-ing, has re/iewed the Grand Gulf Unit 1 Technical Specifications. Tne sections reviewed wre 4.0.5, B4.0.5, and 3/4.4.6 on pages 3/4.4-17 thru F4.4-20.
Tnese sections are acceptable, except that the pressure-te cerature li:mit curves in Figure 3.4.6.1-1 do not comply with the closure fla ge.
pressure temperature safety margins in Paragraph I'i. A.2 of Ap:.endix G, 10 CFR 50, which became effective on July 25, 1983. We will be sending to all licensees / applicants a generic letter infor::ing them of th.e revised regulatory requirements. In accordance wi:n that let.ar, the pressure-temperature limit curves in Figure 3.4.6.1-1 may require revision.
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This comment has been coordinated with Mr. Donald E. Hoffman cf your
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B. C-Liaw, Chief Ma.te.-i.als Engineering Branca -
Division of Eng:.neering cc:
R. Vollmer D. Hoffcan D. Eisenhut M. Houst:n F. Miraglia B. D. Lins W. Johnston C. Chen:
E. Salliva, W. hazeinn S. Fawlicki R. Ki ec:.t.-
D. Brinkmar.
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l PART 50 0 DOMESTIC UCENSING OP PRODUCTION AND UTlu2ATION O".' + ppen.e - Teogbe.se p--
ou,,,em.nted es fooome for,,ec,u,e Repuumsee A,.Ferrit6c meterfel*meses carbon and toughnese during synaen hydroetstic teete I
low.eBoy seselew higher aGoy steels including and any condition of mensal operetles.
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thciteding anticipated operationei 2"a6/e e/Ceasemes e stedeless eBoys of the tax senee, and occurrences:
L!stmdecem and Scope moreging and precipitanos bordening steele L Reector veneel beldine meteriale must l
E Dennitions with a predemmaatly body-cented cubic have Charpy coper ehelMergy ' of no less
!E Frecture Toughnew Twee crystal strecture.
gy* yg 7
h 4 M Nmah and must monum y,Inserv6ce Requi terveneel
- Mystees hydmatode teste* aseene ou upper-shelf enerfy throoghout the life of the
- -^' system leakage and Doldine Newde Eydrustetic pressure teste and all system msel of no less taen 50 ft-Ib (sal) unim it le demonstrsted la a ment er approved by the L M and Seeps leshage end hydrostatic pressure teste Dsrector. Omco ef Nuclear Reector performed during the service life of the Regulation. that lower weises of apper. shelf This appeedte specifies hectore toughnese pressere bensdary is compliance with the energy wig provufe maryne of eefety egeiset requiressante for ferreds testariale of ASME Codew Secties XL og g,,,,,,,,
C."Specified susuous yield strength
- fracture egievelent te sene regiered by ecolant pressere 5eemeiery of acht water messe the minissum yield strength (in the Appendia C of the ASME Code.The lateer anclear power reactere to provide adepaw emirrediated conditteelof a motortog edition end addende of tie ASME Code mergene of esfoty daring any esadines of specl8ed to the commerection code under permitted by peregraph 3 Lase (b) of this part omrmed operudes. lseinding angesposed which the===y===* ie built under $ 50.sse et the tune the emelyeneismade are to be operational one syssene of this part.
osed for the purpoose of pareyephe IV.A.t hydrostatic testa. to which the prmere D.*Referense temperature
- means the and IV.A.2 of this appendia.
boundary may be subksted overits servies reference tesepermlerew RTees. as densed in
- 3. When the cr're is not crtt! col prosauro.
De AsME Code foram the basis for'ee the ASME Code, temperoture theite fr.e the reactor vnosi must
- Infetime, 3 "Adlee*ed refersees temperesere* muna be et Imt es cesservettve a th obeeined ingestueenof the Appmene.*AsM,E es referesse temper eue u adiunted for by followma de awebede of analyse and the Code
- messe the Ameneen someiy a irradiseses eaeme (see Secties V or im required anyne of feiy of Appendte c of Moshem.eelIossesse Beder and preneure Appendialby adsung to A7serthe the ASME Code supplemented by the Vessel Cod 51f me seedse le spesa8ed. Se le"pe'enere shan.mossered et the 30 lbib requirements of Secean V of this appendia.
referases le se Seetsee EL Divinen 1.*Reles (411] level.la the everage Charpy curve.for la addibon, when pressere enceede 20 for Commereceae of Neelaer power Mass the irradiated motortel relauwe to that for the percent of the preservice sistem hydroeteanc r%=r====a= * *Secdos XI* means Seedom XL Drvieses 1.* Rules for Immervice 8==r==d=
., enarrediatedasseerteL test pressere. the temperature of the sfeeere F.*Beittiae* or *Bentline ropes of reactor f!snee regions that are highly es.eemed by the E of Nuclear power Mont Componenta.* If ne
- vessel
- messe the repos of the roector yeeeel.,3 emperature of the rneeenalla th belt preioed must escoed the reference
- edities or addendele r aa-d the espdcable (eheit meterialincludmg weide, heet spected t
a ' ASME Code odinom and addeeds and may
- m. sense, and plates or forpass) that direct!Y g by at leses 1FF (e*Q for nennel operstfem E !!astodone and medilissueos thereof are g announde the effective be. gat of the acuve
- n. and by so*F (50*Q for hydromene preneure
. upectaed te 15 Mas of this part.
com and edtecent regions of the reacter
- teste and leek teste, unlese e lomme De ASMEBailer anditsenere vessel Code has been sporeved for faserparados by veneel thes ase predicted to experience teropeture can be feet.asd by show*ng that sufficient neutros radiatica damage to be the mergns of safety for tsoas repoes ween referenes by the Dtrester of the Federal Nepater. A modce of any changes mode to the canadered in the selection of the most they are controlling are equivalent to these meterfalloessperosed by referesse wiu be limating motorial with regard to raciation required for the beitline when it le pebilshed to the Fedmai negleses. Copies of demage-contro!!ing The tusel8censo subnested for the pressere temperature tisoite nuuse doecribe O
the A*NE Boiler and pressere Vemmei Code
!!I. Fmcrum TaughmoseTease the methods of analyene ased.
may be purcheesd hem the Assences Society
- 3. Whos the cose is casacal(other thee for af h Engeserm Umsted Engissertog A.To demon aretecom; ance with the 2
Center.346 Iset 4Fth St.New York. NY f>ecture toughness requiremente of Sections the purpsee oflow. level physico sensek the 20D17.14 le else eveliable far toeposeen et the IV and V of this appendia.femtic meterials tempererare of the reesser veneet muss not be Nucteer Regulatory Camadassen's pobGe muss be tested in accordance with the ASME lower than 40*F (2 *Q above the simiseen Desument Room.1717 H Soest NW, Code end. for the beitline matenals the test Permsomble temperature of pareyeph 2. of thia secdos nor lower thee the mieuause regaaremente of Appendan H of this part. For Weekington,aC.
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De sequeressets of this appendia apply to e reactor vessel : hat wee canencted to se Perrmessbie temperseers far the inserv6ce eystern hydroetette pressure sees. As the feHoseng senteneim AqME Code earlier than the Sumrper 19F2 exception may be made for boiling water Addenda of the 13r1 Edition (under I 5M5a reactor vesesse when weter levelis wit'ne the f
Noem--The adequesy of the fressene Imaghnese of eeher fernete mesestala not of this partJ. the tractare toeganese dera and I
sesend is this esades shall be desseneereced date snelysee must be suppleniseredin a normal ronge for power operados and the menner approved by the Director. OfHee of pressure le less than 20 percent of the L
to the Deresser. OfRee of Nesiser Reester Neclear Reactor Regeistoon, to demonstrete preservice system hydrestatic test pressere.
in this case the nunsases pennissable W as selaevideal came beste.
equivalence with the fracture toughnese temperature is 80T(33*Q above the A.Cerben andImBoy feryone M pia requiremente of this Appendis.
forgings. caesinge, and pape wee epocifkd
- 5. Tess methods for seppiemental fracture reference temperature of the cloeste f!asse mesensa yidd serenges not over sacos pe6 toushness teste described in pareeraph V.C.2.
regions that are highly serreest by the be64
[3e5 Mpek and to these weds spes Sed of this append!z must be subrmited to and pmioed.
4.!f thereiono Assilethereacterdettag mbeimum y6eid noengthe poseer than 54005 approved by the Director. Office of Nucteer systeet ydmmade pmum woes wleek pel (348 Mpel but met over eness po6 (ets Mpel il qualined by emme meshede equiveisset 88'*' 8'8"I*8'"* pnw to tenung.
M e.h m e mne m W w C. Au m toughnm tm pmgrante to these demorebed in perspeph G-2110 of the conducted in accordance with peregraphe A wmpeta most be eG7(33*Q ebove the l
A5ME Code es denned la pareyeph II.A. of and 8 of this section most comply with ASMg ediusted reference temperature of the roector M mesm hym h to i
this appendia.The latest edtuon and Code mquammwe fw cadrenon oheet ends (se WW mmM M addenda persntted by perspeph 50.5Se(b) of egmpmm que atan of W pemnnd i
this part et the time the amelysis to made is to and retertton of recorde of 'hese functions of this appendrd S. !! there is fuelin the reactor during t
be used fw e and of the test date.
E Weide as ested==== in system hydroseauc preneure teses or leak teets, the requaramente of persymphe 2 or 3 of 88889e3e WWA pmgresh R of IV.Freasuse Toegboose R,
gg', appendia.
this section apply, dependsne on whether the C. Metensie for beiting and other types of A. The pressero.reemanina conrponenre of core la cuetical durung the teos, festenere unth spec Aed annimasa yield the reactor coolant preneure boundary that
& Reector veneele forwhich the predissed stansthe not over 13 aces pas (see Mpe).
are made of ferntte mater ele must meet the requiremente of the ASME Coce
- DeAned to Asym E tat.ro and -es winee are Niasseersted by esferummein Appendte Pt.
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vetoe of uppee.ohelf energy at end of Efe 1, temperoture-Was na those given the B. Reactor vnaeh th.tt d.s not meet the I
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below se ft4b or for wheen the pro 6cted beltline metanaLThe reou ta.together w:th cendidone of paresrsph fLA.of this value of edimased reference toeparorure et the resuha of other pertinent annealing.
Appedia must heve eew beltline maariale n
and oflife seenode 200*F(erQ must be efects oeudies, are to provide the basis for monitored by this Appendix.
desegned to pernut a thermel anneeling establishing the ed}eeted reference LThat part of the servedlance proyam mostment et a sometenety hesh travpersture trespereenre end upper helf energy after conducted prior to the first capsele to resever maten el foughnew properties of anneshns ne resc*or veneel m ay connnue
- nthdre=al must meet the requirements of ferntic masonela of the ructor veesei to be operated oniy for that serv'ce perted the edf tion of ASD4 E 133 that is carrent ce beitune.
withis which the predicted f setur, the laeos date of the ASME Code to wbek tonshnese of the beltune repon malenals the reactor veeeel was purchased. Later V. !amervtan,,
_ Vase,l sausfies the requ.rumanta of Section IV.A. of editions of ASTM F.tas eney be used but Beides M this appendia unne the values of adbasted faciuding caf f those edloons through test A.The eNeets of neutron radietion on the referesse tesaparetore and apper shelf energy For each capsule withdrawal ofier July *a.
referesse teenpsensure and upper sheif enew that include the efects of anneeling and 1983. the test procedtree and repornas of reesser veneel beishme sietervels. Including embesquena irredianon.
requiremente meet meet the requiremente of weida, are to be povestsel fWem the results of
& The proposed proyame for seetafying the AS34 E tea 42 to the extent practical for the perdesnt renaden e# sets osedlee in adattee
_ _ of Secdome V.C and V.D. of this configurocos of de spemame la ee omomia.
to the evasite of the essvedlance proymen of appeeda are to be reported to the Director.
For each capoule enthdrewel pner to Taly "!L Appenen H to thee part.
OfDen of Nuclear Reactor Regulation, as toe 3 eithw the 1syt the tem or the 1 set
& Reactor veessie may coettees to be openned in i 5tL4(e) of this Part for review edition of ASD4 4148 may be used.
opereted only for that service pened within and approval os as individual case beeis as
& Suminance specimen capsules muss be wench the reqeisements of Seccan IV of this lease 3 years pnar to the date when the located near the ins.de veneel well fa the appendia are sedaded wome the prodlcted prodcted tracture toughness !avels wdl no beitline repos so that the specimes veine of the edte. sed reference tunpuyerere temger endaly the regenrements of sectzesV B trredlanon history dup 3 cates, to the entset and the prodcted veine of the oppew of thee appenda.
pradeaMa withis the physical conseresets of emergy et the sad of the serveen pened to the eyeseen, the nostron spectruse, esseumt for the edeste of rededom on the temperature history, and maximsm neuerus thesants temehneen of the beitune maasnela.
8-esponenced by the reactorveessi These prh are to be made for the Appede h_ Vessel Masertal famer surface.If the capsule bolders are 8" "u88'8PNFem ettschect to the venasi weU or se the veneel rededen medimens se the atacal locados on the crack front of the assumed flaw."The Table of Conteet, cfadding. construccon and innervice faspection of the attachmenta and attachment highmee adjusted referomes tassporarm and mwm welde must be done accordas to the the lowees uppe=easef aesrgy level of all 16e U.Surudlanca Wm
'"""'"f*'"***""'**I beltline mecenaleiseas be used te vertfy that
..DI 3, pert dTest Rheulie
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2 the frecnere '4a=== requarwnents m I attachments to reactor veneele even to a endened.
ll; LImmedesnes
- SectionsIIIand XIof the ASMECode.The
" design and location of the capsu:e beiders
! CIn thment that the mquirements of a The purpose of the matenel survallance
. Section VA of:his appenez cannot be
"" proyam required by this AppeedLa is to m a au pennstinseroon A 1
- settaSed.reactar veneels may continine tEbe I moreforchansee in the frec:ure toughness capsuln. Acceleretad irrediados caWe ir.zy be used to addidon to the required opwated provided a3 of the following
- propertfee of forntic matenals in the rsactor ruteiraments are nedened veeeel beltline repon oflight weter nuclear nurnbw of surm!!ance capsulee speaSed in M E 165.
S L A volumetnc emessinetfom of toopercent power reactors resuldne from esposure of of the beitline materials that do not setsfy these meterials to neutron irrediauon and the L A pmped withdrawal odedule mrust the requiremente of Secdon VA of this thermal environment. Under the pregrarn.
. be submitted vnth a tedrucal hatificadon eppenda la ainde and say flawe tracture toughnees test data are obtained
- therefor to the Director. Office of Nuclear chorectertmed encording to Sectios XI of the frors tnotenei specimens exposed in Reactor Regulation, for appresel.The ASME Code and as otherwise soectf!ed by surveiUance capsules. which are withdrewn proposed schedule must be approved pner to the Director. Off!ce of Nucelar Reactor penodically front the reactor vessel Three
, implementation.
Regulation, date wdl be used se descnbod in Secuens IV C An integrated servellance proyam may 1 Additiemal evidense of b fracture and V of Appendia G to this part.
be considered for a set of reactore that have toughness of the beitilse metenole after ASTM E146 7%-79 and -41"Standant sunilar design and operenne featurne.,The esposure to neutron irrediation is to be precdes for Conducting Servallance Testa representative matecele chaean for obtained from results of supplemental for IJgbe-Weter Cooled Nuc!eer Power survedlance froen each roecser to the set tesy frecnire toughnees seese.
Reactor Veneela." which are referenced la the be irrsdisted in one or teore of the renesere,
- 3. As emelyses is perfonned that foGounne parayephe, have been approved but there must be en adequate doenmetry conserveuvely demonstratea. making for incorporedon by referenca by the Director proyen for each reactor. Ne ruuducnos in the=
apprepnate allowances for au uccertainees, of theFederalRepeter. Anoticeof any requiremente for number of metanale to be the esistence of equavelens morpas of salesy changes made to the metenalincorporered irradiated. opeamen typse or noseber of for coattneed opereuen.
by refonnce wiH be published in the Federal specimens pw reactor is pennitted. but the 111f the procedurve of Secdon V.C of this Regisear. Copies of ASTM E 185-7% -79, and amount of testing may be reduced !!the appendix de not insucete the existence of as
-4L may be obietned from me American imidal readte agree with predictione.
equi,eient esfory merpa, the reactor veneel Society for Testmg and Metenela.191g Race lessyssed envet!!anas preyene must be beetline may, subtect to the approval of the St. phdadelphia. pA 1910L Copies wdl be approved by the Dtructor. Odnem of Nesiser Director. OfBce of Nuclear Reector evedable forinspecdon et the Caennesmon's Reestor Regulaties, ce a : O _ bases.
Reyeletion, be given a thermal anneeling Public Document Room.1yly H Stroes NW, Criterne for approval teclede the fouewing
- Weehington. D.C emmenderedoest treenneet te recovw the fractere toughness of the metensk The doyee of recovery is to be II.Survedleman Propen Criterta me design and opereting fennees a(the rmeers in the est must be suf5omedy.enmaler onesaured by teenne seditional speamena ne 28 tens 8WM *nce FmFer't 's to pennit occurate compensone cithe he beve been withdrown fro a the uirmi r mector moois f r wh2ch it can predicted amount of radienon damage as a
[deervatively dernenstrated by eaalyncal serveillance progree capanilee and that have function of total poww carpet.
been ensealed undar b sania umeet.
e applied to emportmental data and 1There unset be adequese arrangement for teses perforreed on compereble vessels. -
date sharing between plante.
snaking oppropnete ellowances for ad 3.There most bir a contingency pies to
, y,, % 3, gg er ' eI he es enie. that the esaure that the servedlance proyam for such C of the A&Mg Cada the resbeses seedsper.a is be p**h Bestr n IIsence (E>1MEV) at the end reactor wdl not be popardised by operneos emed are these preessed far the mesomed esw faere of the way geomet the veneel wed.La. at the o the design life of the meet wdinet exceed at reduced power level or by an extensied dessem pean en tm armee heat of the pomuse.ed 10" n/an*
antage of eno6w resawimen which data
- 8S are expected.
May 31,1983 5 0-18
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TECHNICAI, SPECIFICATION PT,0BLut 5 DEET :
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Responsible Supervisor
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Tech Spec
Reference:
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Problem
Title:
kl6'C S 1 t r / TG~M/n* ruse' l15 l7 C u s s e' s 1
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Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
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Safety Significance:
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Anticipated Resolution: G U M e. orc' To b n 7>.~s m s'/ toc' lF
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NRC Response to Item (NRR/IE):
NRC Notified:
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Dispositicn:
Items Closed: (Hov)
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Date Ti=e cc:
J. E. Cross R. F. Rogers 3
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.,7.e PkhlT!!O e DOMESTIC LICENSING OF PRODUCTION AND UTIUZAT10N FA
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ppendia G--.Frecum Taughness IL De8mideas supplemented ae follows for frecture A."Fernue matertal means carbon and sovannese dunne systern hydrouanc teeis
% ** 3 ToWe of Content.,
low eHoy Heele. higher alloy steeis includies
- "d""Y**"d'"""*3'P"'"-
eG stainless a!!ays of the 4xx senes, and includire enticipated operanonel LIntroduction and Scope maresma and precipitation hardemns steele occurrecn:
- 1. Reactor vessel beirfine metenets musa E O'08'D'"'
with a predominantly body. centered cubic IU.Frecture Toushneu Test:
crystal atructn have Charpy upper-shelf energy
- of noless IV. Fruc'2re Tousham Requirements 3, Systens hydrostatic tists* means all than y3 ft-Ib (Ica;) rutiaily and must maintain V.!asemes Requ rementa-ReactorVessel preoperational system leehage and apper.sheif pergy throughout the hfe of the 8e am MatWals aydroseauc pressure testa and all system vmel of no lese uten 50 ft lb (6ef L ulen it is L!atroducties med Scope lesi6 ate end hydrestanc pressure inta demonstrated in a manner approved by the performed dunns the service bfe of th, Director. Office of Nac!eer R rector Tbs appendis specties frecure toushnene pressure boundary is compliance with the Reguleuca.that tower vstuas of =pper sheif requiremmente for ferntic matart ala of ASME Code. Secuon XL megy wdl provide morpne of aefety esmet
- "'*""d*'"**88' 7not"pneemm boundary of!isha watw C."SpeoGed muianum yield sinneth" trecrure equiv lens to those requie.d by maan the nununure yieid stnngd (in die Appendiz C of the ASMICode.Thelatest E,
enarradiated condident of a matettal edation and addende of the ASMICoee 8pecified in the cometruction code under penmtted by pareproph 50.53e(b) of this part sermd operados.tacludaag unc!pased which the component le bu It under $ 5a38e at the time the analyssa is made am to be operecesel occurrences and symann of thJe part.
emed for the purposes of persymphs IVA1 bydreesatic testa, to whicf the prenure D."Refersee tampmture" muns de end IW of thra appeda.
boundary raay be subtected ovetre service reference teroperature.RT.,, as daGned in 1 When the core is nor ent: cal preneure-21 dae.
The ASME Code feries b boas for'ce the ASME Code, r
temperature tinuts for the reecor vesee6 most I."Adiunted reference teerpero uro* meene be at lesse ao conservenve se those ootamed paa of tMe Appendia."ASME Code"essena the American Society of the reference temperorum os ediumed for by following the ewthose of enalysie and the Moebenecal Ensunsere Bedar med Preneure trradieues effects (see Seenon V of dus required marpaa of safety of Appendia G of VeneelCade.11ne esenseis openfled cc Appendial by adding to RT.or the the ASME Code. _ J _ ed by the reference la to Soccan CL ofwis.es 1. "1tulee tmpweture shiff, measured at ce 30 ft-lb requirernents of Saccon V of this appendiz.
for Construcnee of Nuclaar Poww ptant (411) level.in the averste Charpy curveJoe In addition. when pressure encaeda 20 Components." "Secnoa ;C" ansana Sectica the irradiated matenal relaave to that for the percent of the preservice syssent hydrostauc
%L Dmmee 1. " Rules for !survice Inspecuos unitrediated matenaL test pressure, ce temperoture of the closure of Nuclear iWwer Ptant Camponesta.* If no F."2eitline or ~3eitline reson of rencor f!ange regions cat are htsbly eareened by de -
- edition or addende is nosofied the appilcable ' * "sami* means ce region of the reactor yesses, boit pniosd must escoed tae reiarosca O ASMI Code scanon and acdonda and any
- (sheil matenallncludirts weids heat sLTected 3, tempweture of tse matwtal La those repons sones, and plates er far gutsa) cat directly c
- by at lesse 1:U'T (SrQ far normal cperstion
- limitanons and modificauona thereof am m
specf!ed un 113?tsa of this part.
- surrounds the effacuve botant of the active
- and by 90*F (50'Q for hydrovianc pressure The ASMZ ".ader and 35sa re Vesaal cere and solacent regono cf ce reector
- testa and lee's tears, unieve e lower Code boa been approved for tacorporenen by wsoei that are prodcted to esponence tempwerure can be teenfied by showmg can reference by the Directer of the Feceret socient neutron radianca damage to be the marpne of safety for those repoas wame Rapster. A nouco of any changes cade to the considered in the seiection of tne most they are controiling are equivalent to those satertallooreparated by reference will be hmiting matenal with retard to raclance required for ttle beauine when at la publtahed ta the Fedusel Reyesse. Copies of damage.
controf!!.",5 %e tuanfication subrnitted for O
the A3MZ Eoder and Presauro Vesses Code
- the pressure temperature lirmita crust descnbe III. Frnaum Tousa.nwe
- Twie the ciethods of analysis maed.. i may be p.irchamed from the Amencan Sacety of Meenanical Emoneers. Unated Enguwering A. To demonstrete compliance with the 1 When the core is crtucal(other than for Canter.344 East enn St.New Yore.NY fracture toughnna requirements of Sections the purpose of low. evel phyenes treask the 1Cm7. It la alas evettable fsr inspeccoa at the IV and V 'of this appendia. ferritic maternin temperature of the resctor vessel tavot not be Nuclear Regulatory Commisaien's PubGC muss be tested in accorcence with the ASME lower than 4rF (22*C1 above the minimus Doc nneet Room.L*17 H Street NW..
Code and. for the beitline malensis. the test pe-missable tempwaturv of paragspb 2. cf Waahington.D.C.
requirements of Appendaa H cf una part. For this section not lower than the rununu;n The.,_-- Jo of this appsedia apply to e enctor vessel that was construced to na portrusable temperature for the innervice the fedewme metanela AqME Code earlier than the Sumrner 1972 eystets hydrostanc pressure test. An Mean-The odequacy of the t scnire Addenda of the 1971 Edition (under 150.35a excaption may be made for bodit.g watar totaghness of otaer ferritic metenala not of this partk the fracture tauganus data and reactor vesseis when weter level is withm the cowred ts this escnon shall be dreenetrated data analyses must to suspiemonted in a normal tense for power operation and the to the Director. 015ce of Nucjeer Fuctor manner approved by the Cirector. Cffice of pressure is ten rase :n percent of the Regulanen, ce an indtvfdual case bases.
Nucienc Reector Regulation. to demonstrate preservice syseem hydrostatictres promeers.
A. Carben and low.eitoy ferrttic steel plate.
equivalece with the fmenim toughness in Ws case the nunannun peansaaWe forynge. castinge, and pipe with spec Hed
"'"'rements of this Appendia.
tercreratureis eo F(33*C1above the IL Test methods for supplemental fracture reference tetnpersture of the closure f ange manimum yield strugthe not over 50.000 pai (344 MPol and to those wtth soecfled touahness testa descnbod in paragraph V.C.2.
regions that are highly stressed by the boit of this appendia must be submitted to and
- presced, miniavuse yield soengthe greater thea StLODO psi {344 MPol but nos over stLaos pas (att.
approved by the Director. Office of Nuclear 4.1f there is no fuelin the reactor durms MPolif qualified by esang nethods equivalen, Ruc!W Retuladon. ;neMo tunng system hydrostatta pressere tests orleek C. A!! fracture toughness rest preysms tests. the mintmute permisemble teet to these descnbod in paragroph G mo of the conducted in accordance with paragraphs A tempersture must be co-F(33*C) above the ASME Code es deGned in patogroph ILA. of and 8 of this section most comply with ASME adiusted reference tempereture of the reactor this appendia. The latest edman and M mummmu for catiksnon ohnt vnM mawaiin se ma dat is addenda permitted by parserson 50.55a(b) of equiprnent qual:Ocaun ofint perud con 4 (u sodd in parapoph M thta part at the time the anetysis is mace is to and retenrion of recordt of these functions of this appendisk be used for the purpose of this parograph.
and of the test data.
1 !! there is fuelin the reactor during
& Weida and weed heat.affected zofies in aystem hydtestetic pressure tests orlank,
the matertels specfled in paragraph I.A. of IV. Fmesum Toughene Requisemets tute. De muirements of pareyephe 2 or 3 of this appendia.
Gis action apply. dependmg on whether the C. Masertais for belliri3 and other '77ee of A.The pressureretainina cornponents of cor, is c.itual dutt:'g the test.
g,steners with spectied muumum yield the reactor coolant pressure boundary that
& Reactor vesseis for witich the predicted strengt!!s not over 13(L000 poi (see MPs).
are made of ferntic maternis must meet the requirements of the ASME Code
%.4 La ASW E no.re sad as *ea are
'naperoise try reference ss Appenesa H.
e O
E O-47 May 31, th e
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r t " ' ~ ~ PARTWo DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES o
entite of uppee. shelf energy et end of hfe is tempereen canditiona as done given de B. Ructor esseels thrt d.s not mee the below 50 ft4b oafor wbcts the prediend belthne matensL N nodia, togeht mth conditions of parsgraph C.A.of this e
value of adtussed reference temperature et the reents of other perunent annealms.
Apper: dix must have their beluine materiela m
end of hfe amoneda.oo F(93*Q mut be effecte studies, are to provide the basis for monitored by tjua Appendix.
desiyted to per mt e mermal anneshng establishms the adtuated reference 1.Dat part of the surve*Uance program treatmeer at a rafficently high tempcature tempersrure end upper onelf etieagy after conducted pnor to the fbst capaule to rouxrvee emaienal toughness preperries of annealms. The rescer vessel may certtmue widdrswas must meet the esquarezenLa of fernue teeseriala of th reactor ses nel ta be operated only fee det aerwce pened the edacon of ASDA E 113 that is current on beit!!ne.
undia which b prediced fracture the (same date of the ASME Code to wtuch toushnesa of be beithne regien metenals the reactor seenel wee purdame<L Later y, % e _ u _ _
%,,, y sansfies the requ.rements of Section IV.( of edihona of ASTM E tas an.sy be used, bei gg die appendLa usms the vslues of adjusted including caly those editions througa 1ML A.De effects olnestros radiation on the reference teroperature and upper. shelf energy For each capsule withdrawal after Idy 'A referense tenseersnee and uppee shell energy Gat include the effects of annnling and toes, the test procedwee and repornaq of reactar esanel beithme o esenata. Including subsequest irrediauon.
requirements must meet the requirements of welds are to be predicted from the results of L De proposed programs for satisfymg the ASTM E1642 to the azient precocal for the CC"E moon of the epeannes Le the espesia.
perument radianen efects seedles in oddattee requirements of 3ecnoma V.C and V.D. of this 3
to the remslie of b surecuence program of sppendia are to be reported to tne Ottoctor.
Tw eed capsule mthdrawal pner to [4y 3.
Apperdna H to this port.
OfSco of Nuc!aar Reector Reguleuca, as 23 either the t371 the tors, or the tsat B. Reector veneela may continue to be specRed in 5 54t(a) of his Part, for renew edacon of ASD4 E 188 may be used.
eperated only for that sermes pened within and approval on an indindual case basis at a Surmilance speamen espau =o mual be whcds the requireements of Secuan IV of this least 3 years price to the date wnen the loccted near the tnaide vnsel well in the appendis are sacs 6ed usans de prediced preeteted *rac ure toughnesa levels wiu no britLas region so that the specmen and the predicted veine of the opper. shelf of thas appendLx.
- trradianon tristory dup 3catan, to the extant vajee of the adhasted reference rompersrure longer sensly the requirements of sectiain V 3 procticable withan the phyescal constresets of energy at the med of the seretco pened to the eyamn. the neutrue spectrum, acesset fee the effects of rediados as *he temperature history, and maadanum neotron bacrure tougheses of the beit!!ne matenela, fluence npeneced by the reector veessi Does ;eueiseene are to be made for the Appends H 2-VeessiMaesnel gnaer surface. If the capeuJe heldere are Snevendames Jh= ogress Restuaremesas attached to the veseA wail or to the vessel radia.am emesiamone et the cndcal!ccados am the cred front of the assumed f!aw.* no Tchle o/ Contents cfadding construcces andinnervice inspe at.achmenta and anachment h W= edlunted reference tamperature and
- 1. Introdocion welda tuas be done occording to the t2m lowees upper seenf energy level of all the
. gg g,po,, og 7,M,, g, m
. mqmnments for penament structural H. Surwinanca
- beitline materials muss be used to venfy that
- attachments to resetor nemeia ipv t to
- the frecnee 'aqaaama reqwrements are senefied.
- I laer-~-
- SectionsIIIand XIof the ASMECada.De a
f C In the event that de requarements of C
De purpose of the matenal surve:Useca
= dwen and locat. ion of the capsula holdere Secnce V 1 af bis appendia cannot be.
I progrecs requared by this Appericia is to E". Acca ano.af ed.ranc:ce vesset.s esav concaue tdbe
- momter chantes in the t ac.re toitshness
=c s
sled imladon caWe epers'ed peuvrded all of t e foCow=3
- propenses of ferntic mater ais as the reactor may be used in add! on to the requa.-ed we. as are saastled:
vessel beitline repon ofligan water nuclear nurnear ci surmUance capsules W.,a ASD4E181 L A volumetnc exanunation of100 percent power reactors resulung from esposure of m
of the beithee etatensla tast do not sansfy these matenais to neutron irrad;suon and the.
4 A proposed vnednwal amme the requir-ments of Secnon V.S. of das thermal envtrenment. Ur. der 5 program, be submued wid a tedrucal haaricacco s
appendam is made and any caws fracture toughness teet data are obtained therefor to the Director. C5ce of Nucieer charecreatsed accoremg to Sect:en XI of the frem metensi specmens exposed in Reactor Regulanen. for epprowaL ne ASM2 Cace and as otherwise spec:fied by surse: Hance es;suiet, which are withdrawn proposed scaedule must be approved prrer to the Cineter. C5ca of Nucesar Reactor penodicaily freet the rescar v,ssul. Dese
.tmplemtauon.
Repalanon.
cata wtil be used as desenbed in Secuocs IV C An integrsied serveiUancs program may
& Additional evidence of de fracture and V cf Appendia G to t%s part.
be considered for a set of reactore cat have toushnena of the befulme mstenals after ASTM E IWr3. -79 and -4L -Standard sunilar design sad operenne featurem.,%e exposure to neutron trradianon is to be Procnce for Conducting Surverilance Tests repneentanve matensie chenen for ootained from resst: of supplemental for I.ilat-Water Coosed Nuclear Power survetuance 6.es each react Jrin the set may fracture touanness seers.
Reactor Vesaeis.' wruch are referenced in the be it-adisted in ene or more of the rsectors.
1 An anasysia is performed the, followmg persgraphs, have been approved but dere must be en adequate d-atry conaarvstave*y comonstretes. maiung for incorporeuen by nference by the Director progrom for each reactor. No reduccom un tha-appropnais salowances for all uncertainues.
of theFederalReipasar. Anonceof any requirements for number of matanals to be 2e eatatence of equivaient margins of safety changes made to the matensiincorporated trreciated. epec:nen typee. or member of for coonnued opersnan, by reference will be publialted in the Federej specunene per mactor is peruutted, but the D. If the procedures of Section V.C of t.%s Regweer. Copies of ASTM E :w?1 -re, and amount of tenung may be reduced if the oppendia do not indicate the existence of an
-4L may be ottamed from the Amencan totaal results agree with predicnons.
i; equitstent safety roerftn. the reactor vessel Society for Testing and Matenals.1916 Raca telegrated sieveu;amos peowsme muss be belttine may. sectect to the opproval of the St. Miladelphis. PA 1p101 Copies wvil be approved by the Director. CfMen af Nac>eer i
[.
Director. Cf!?ce of Nuclear Reactor avadable for utspecuen at the Cornauesion's Reector Ragulanee. as a casedry esse beesa.
Public Document Room.1717 H Street NW.
Certa (ce approval bactode the fouowu.
l' Regulanort be given a thermal annesiing Washington. D.C considersoona:
treetment to recover the fracture touganets of 1.
e design and optedag feesuru of 6e the metenal. De degree of recovery is to be IL Surv=Ha-Program Cntena macmre in the est aruet be esSctmady aiaulaa mesured by tessu g seditional specmens tnotene autmuance premm is to per=ut accurate comoensons of the that have been witxrewn from tne
- mect"' Mms W *mca at can presicted amnt of ndianos damayan a survet!!anca program capsulee and inst have He n
n uca fus2cton of total power corpuL been anneaied uncer the same nme-et.
methods appised to experimental date end L nere must be adequate anungessent fee testa performed on compareble veneels..
data shortng between plants, an88tn* 8MynH* a weMee fM a4 1 The must be a contuigency plaa to e hr esame.a is easirwe taes roue. Appeedia u en anun e asu a
that the maeure t3at the survetUance pet 9rman for eech C 4 uw ASMI Cade. the psdances commneme to to peak neutron fluence (E)IMTV) at de end reactor wtU not be isoperthsed by operecon used om um== omected for uw suwned one sanne et the =e, throegn tree es : we4 La at uw of the design life of the vessel will not exceed at redeced power kvei or by an extended de* esse pean un me croce base cd vw peerme.e4 10" n/cm*
cutage of another reactor from wtuch data 8' fen are expected.
l May 31.1983 5048 1
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" TECH SPEC PRIORITT" Punchlist Item # e9 /9 Tech Spec borr J.4./e.1-[
i Priority 1A TO:
Manager of Nuclear Plant Engineering i
FRCE:
Chairnan, Prioritization and Disposition Chair:sn
SUBJECT:
__ Technical Specifications Punchlist Item i 2Il C
PDTS:84/ D O \\\\
DATE:
.3 / t o /4b 4-The subject Tech Spec ites has been deter =ined by the Dispositien Co=sittaa to.
require Engineering support.
DETAILS:
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Please contact Te e_
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,Please refer to the Tech Spec Punchlist itam nunber in your respon:se. Forward your response to I-3,
- 7. ; u k. e_
J. C. Roberts Chair =an LLJ/JCA:sub cc:
Mr. C. L. Tyrone Mr. J. E. Cross a
Mr. D. Stonestreet 5
Mr. A. S. McCurdy Mr. S. Hutchins Mr. J. Hendrf File (Tech Spec Records)
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TECHNICA1 SPECIFICATI0'i ?.RO*45.E![5 MEET Item Ni:mber _ 219 Priority: __ r IA
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Identatico Dy Daco Ronpearible Supi.rvinor ~
Tuch Sps: Refercncca figure 3.4.6.1,1 I
a Probics Ticist Pressura/Tennerattire 1.fmfr Curveta
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The preasure-tsuperatura limit curves do not co= ply with the closure fla732 peca-e
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sure-tosperaturs asiocy margir.s in Program IV. A.2 of App. G to 10CFR50.
Proof
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Safat Significance No ur t.,
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Anticipated hasolutient E.-;ua:: tod$:or:tr.: if the fit,ure vi;i rsqu:rc res*sion.
05N Aro nt11eeYed $s sa le ty conc =fly(sysVI, }p{e:l_ &* Q Yu.}g/#/ettec) E 2l,14 &.
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" TECH SPEC ?RICRI T" Punchlis Item i se, ATM.)
Tech Spec Se e Attacked Priority 5,e ATh(4),
To:
Manager of Nuclear Plan: Engineering FROM:
Chairman, Prioritization and Disposition Chair =an SL*3 JECT:, Technical Specifications Punchlist Item #
see ATTo.chl.
PDTS:84//)O/M DATE:
7//o /7'l
'l* ch Spec item has been de:e =ined by the Disposition Coc=1: ee to The su'ajec:
e requir.: Engineering suppor:.
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,Please refer o the Tech Spec Punchlist item number in your response. Forward your response to G,. 7 2',.ver
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/J.C".Rober:s Chair =an LI.J/JCR:sub cc:
Mr. C. L. Tyrone Mr. J. E. Cross Mr. D. Stones:rce:
Mr. A. S. McCurdy Mr. S. Hutchins
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Mr. J. Hencry Pile ("'eca Spe: Rec::ds)
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" TECH SPEC PRIORITY" MEMO TO:
J. F. Pinto, Manager of Nuclear Plant Engineering
~
FROM:
C. L. Tyrone, Proj ect Manager SdBJECT: Handling of Tech Spec Review Items
". l
- ~ - - -
~ " ~
d TSRO:
84/CCQ1
~
DATE:
March 11, 1984 This memorandum confirms our conversation of 14 arch IT,- 1984
'At that * --
time, your assistance was requested,in resolving discrept.ncies on eleven-s priority 1. items.. Since then cvo items have been added. '-These ite=s are all-previously identi*1ed items which recuire early resolutics with the NRC. A response is needed on these ite=s by 12:.10 PM on March 1~,1984.
A list is attached.
_ Further= ora, all items of any priority identified (cr previously movn) which are being handled on this program require expediticus handling. This includes areas where requests are originated from oth'e'r-interfacing-
~
C organizations such as the Plant or Nuclear Services.
In any case where conflicts regarding highest priority is not clear, I as available to p ovide clarification.
It is suggested that you arrange 7 day a week.rupport in this area as it is needed and arrange for all N?E personnel who vill be involved in this effort to be available (or on call) in a nanner that v111 support the Tech Spec Review program.
O SHH: sad Attachment cc:
J. 3. Richard (v/a J. P. McCaughy (w/a)
T. E. Reaves, Jr. (w/a)
J. F. Pinto (w/a)
S. M. Faith (v/a)
J. E. Cress (w/a)
J. G. Cesare (w/a)
- 7. H. Cloninger (w/a)
G. 'J. Snich (w/a)
R. J. Green (w/a)
L. R. McKay (w/a)
R. C. Fren (v/a)
L. C. Surgess (v/a)
D. 'J. Stonestreet (w/a)
File (Tech Spec Records) (w/a)
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.s LIST OF CU?JFiT PRIORITY 1 ITDIS REQUIRING NPE SUPPORT PDTSg8,4/
?/L #
Date Sent
~~
o 001 199 3/10/84 002 180 003 '
3/10/84 033 004 3/10/84 054 005 3/10/84 001 006 3/10/84 016 007-3/10/84 015 3/10/84 008 198 009 3/10/84 202 010 s/10/84 213 011 3/10/84 219 3/10/84 012 083 013 3/10/84 168 3/10/84 O
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UNITED STATES f
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WASHINGTON. D. C. 20555
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DEC 15 1983 Docket No. 50-416 T'
MEMORANDUM FOR: Cecil 0. Thomas, Chief J.$iIW-t-rv-Standardization & Special Projects Branch
. S%.' "
Division of Licensing dyY 7. dr.
FROM:
B. D. Liaw, Chief
. 'M' Materials Engineering Branch Division of Engineering
SUBJECT:
PROOF AND REVIEW OF GRAND GULF UNIT 1 TECHNICAL SPECIFICATIONS i
As requested by your letter dated October 4, 1983, the Materials Engineering Branch, Division of Engineering, has reviewed the Grand Gulf Unit 1 Technical Specifications. The sections reviewed were 4.0.5, 34.0.5, and 3/4.4.6 on pages 3/4.4-17 thru 3/4.4-20. These i
sections are acceptable, except that the pressure-temperature limit curves in Figure 3.4.6.1-1 do not comply with the closure flange
[g a.-
pressure temperature safety margins in Paragraph IV. A.2 of Appendix G,
.}
4/f
- 10 CFR 50, which became effective-on July 126, 198&.. We will be sending..
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to all licensees / applicants a generic letter informing them of the revised regulatory requirements.
In accordance with that letter, the pressure-temperature limit curves in Figure 3.4.5.1-1 may require
't revision.
EV. ? t This ccament has been coordinated with Mr. Donald R. Hoffman of your staff.
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B. 0- L)iaw, Chief t
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Materials Engineering Branch.
Division of Engineering j
cc:
R. Vollmer D. Hoffman D. Eisenhut M. Houston F. Miraglia B. D. Liaw W. Johnston C. Cheng
,e t E. Sullivan W. Hazelton S. Pawlicki R. Klecker D. Brinkman M. Hum B. Elliot
Contact:
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TECHNICAL SPECIFICATION PRO 3LEM SMEET Item Fi:mbert 219 Pricrity:.rfA
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Identatice By Dato itenp.*:n ihie Supe rvi.sar Tech Spac Rofercncot figure 3.4.6.1-1 Probics Titist Pressure /Temperattire t.fmfe Curves
i The pressure-temperature limit curves do not co ply with the closure fla%c pree-sure-ta=perature safety =argins in Progres IV. A.1 of App. G to 10CFR$0.
Prcef and review coccies: from MIS December 15. 1983.
2.
Safat significance
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Ev:;ua:c co de':orntne if the fit,ure vill requ rc ravisien.
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NRC Responsa to Item (NRR/IE):'
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S ENCLOSURE 2 6
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Information Received from Licensee - Priority of potential Technical Specification changes - Sources of potential Technical Specification changes - Technical Specification problem sheets for 240 potential changes - Backup information for 32 high priority potential changes - January 10, 1983, letter from licensee to J. P. O'Reilly (NRC) and January 13, 1983, letter from R. C. Lewis (NRC) to licensee regarding interpretation of Technical Specifi-cations 3/4 3.6 (Source Range Monitors)
A
a ATTACHMENT 1 TECH SPEC PROBLEM SHEET PRIORITY DEFINITIONS 1.
Problems Needing Resolution - Short Term
(?
A.
Safety Significant Item which would require plant shutdown, prohibit plant startup, or require other plant actions to reestablish safe operating conditions.
) QL *B.
Existing. Tech Spec is non-conservative with respect to FSAR or supporting documents (e.g. approved design specs, SER, etc.).
HP&L requires NRC concurrence and/or resolution prior to next criticality.
16~*C.
Existing Tech Spec is non-conservative with respect to FSAR or supporting documents (e.g. approved design specs, SER, etc.).
MP&L requires NRC concurrence and/or resolution prior to exceeding 5% Thermal Power.
2.
oblems/ Enhance =ents Needing Resolution - Long Term 4L~s tt' A.
isting condition could result in unnecessary challenges to
- #ly4[# afety systems or plant transients or is required to enhance 3
lant safety.
i t e.
- 3 5' B.
Errors or confusing ite=s in Technical Specifications which will not result in non-conservative operation with a reasonable dependence on administrative controls / plant knowledge / operational practices; Licensing commitments which require a Tech Spec change; items determined by MP&L to be important.
6~' C.
Could restrict power level or mode changes O [D.
Typographical Errors and Enhancements / Concerns which do not fall into a higher priority 2 SE.
Problems with, or enhancements to Tech Spec sections other than 3/4 (e.g. Administrative Controls, Bases, etc.)
'/ F.
Over-conservative Tech Specs for which changes are cost-justified l
l The factors used to distinguish priorities 13 and 1C are operational
,~
mode requirements (generally Mode 2 requirements are associated with priority IB and Mode 1 with priority IC), fission product inventory considerations (generally priority 13 do not involve dealing with high fission product inventories while priority IC which is associated with i
higher power levels may involve dealing with high fission produce inventories), and relative saf ety significance of syste=s.
Rev 2, 3/12/84 i
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Design Changes which require Tech Spec changes p H.
Pending design / analysis (e.g. Maximum Extended Operating Domain, Exxon Fuel, Single Recire Loop Operation, etc.)
O I.
Others 3.
Tech Spec change not justified (response required)
/2. A.
Item is generic and not included in STS y B.
Others O'/, ca Scs c is S W
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-14Y Rev 2, 3/12/84 A2sd2
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ATTACHMENT 2 i
/1 iDIFOR3ETIcit 701 3/9/34 Ific HEEM210 i
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Louress of Tech Spec Probles items Pachust Items _
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Items identified by NFE at the 1/24/84 r
meeting with NRC 61 N'
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h'. *.".. * ? ' 1. WRC Proof and Review Commenta given to MF&L e er dby 37
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3.
Itses formally submitted to MRC prior to 4.1 1/24/54 (tsesived 6 in WC iM
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MEC ILE tait (1/14/84)
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6.
Additteest Froof and Review Cameents not previendly punchlisted $ # rd from /D0/C ddf* h /CV' N u
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MP&L Eaview Tasa established tq review 39 LCD's/ACT10N's ['x 2.//f/99/
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tsummatatisu Eeview ICSB Comai Miesellaa,W? 2 Vo's ~c.
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(primarily langetasu insuas and commitamata) e comitil'. @ & VfdetcS z;o Tec4 Sjtc MM M
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