View source for NUREG-0521, Responds to Request for Summary Data Re Releases of Radioactive Matls from Nuclear Plants.Forwards NUREG-0521, Review of 1968-78 LERs & Overview of History of Regulatory Effluent Limitations

{{Adams
| number = ML20136B106
| issue date = 07/23/1979
| title = Responds to Request for Summary Data Re Releases of Radioactive Matls from Nuclear Plants.Forwards NUREG-0521, Review of 1968-78 LERs & Overview of History of Regulatory Effluent Limitations
| author name = Denton H
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee name = Lundin B
| addressee affiliation = PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE
| docket = 05000320
| license number = 
| contact person = 
| document report number = NUDOCS 7908150763
| document type = CORRESPONDENCE-LETTERS, NRC TO OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT, OUTGOING CORRESPONDENCE
| page count = 21
}}

=Text=
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: 3.        Overview of History of                                                        NRC PDR i
Regulatory Effluent Limitations                                           Local POR EEB Rdg NRR Rdg L. Gossick T. Rehm                                                                                                     '
E. Cornell R. flinogue N. Haller D. Muller                                                                                                   '
F. Schroeder D. Vassallo H. Denton                                                                                                   l E. Case D. Eisenhut J. Miller                                                                                                   j OELD G.Ertter(ED0-6747)
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              '. 5 d ot t i. c25                                                                                       Ot:11 4". A STATE IN5PECTION ON 1/26, TWO-ONF HAtf I NCil RELIEF valve 5 WERE ITt.o Ctn it s                                                                                    Rt"OvFD ft E C auS E THEY Dif, uut NEff CODE. I s tE HOL E S t itE V LEFI WERE teO i CAP Aut. .i t o:..      S i tt e                                                                   PED 5 40 feF R E N()V A L WA5 NOT RECORDED.
s '' - 12 '. 4           o tt il f e        * ** l L F *t C *f!V I NG ittE SPFNI RE5IN5 fROM ilth S P L te l RCSIN LANK 5 AN HNPLANNED 40atts. . GisNg-t it. 4 4 0 l u s t'. I .451 ! " A.e r;* 's t SYN              OC.* l lO                  1220F2            itLLCA5E OF '4 ADIO ACi l vF GASSES OCCORRFD.
OiH'm u t o4 r4 Cues $u it si s UEF?C1IVL P 4 C. ii C t i'8 t! 2
                      ,   3,,,q g ;
rFutcoutE5 FOR H ANDL i'tG RE 5 5 t4 wfRE IN ADE Ct#4T E .
221 (UtlE5 '" P 511CK                                                                                                                                                             _ . . _ _
waa,-/                                                            WU1t                      C #,l t i l       F Alltetf Of PRE 55090 Cma l Rfit VALVE PCV-GW-107 TO CLOSE AttowED WASTE GA5                                 ,
i; i s t al:! n a t i v, f :.          .'a n t i ., - N i svi 0C6138                    070171            t'E it'F t PPL55U1E 10 ExtEED RELIEF VALHE Il5P51Gl. U4 PLANNED CASE 005 REtEA s it it. ?                                                                         U1 ': A r         u felt t Cm E D . RE6'ORI AO-52-13-05 t . f inh , e." a t i iis uh
          ..s e stuitie                                                                                            thst Ll'oe OF_ C084405 t ON 5 Ou l0 AT IOf 4 PROOuCI5 ON valve SEAT 440 5IEP PRFVENT Fi VALVf CLO5URE.                                                                       ______-
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!        VUeni[ laat                                                          's -192 8                    04 2'* F F             ILtd 77-21/lLI. DuRIr:G NtlRM AL OPERAftDN A CHErisi 445 PERFORM.4G A RO sil
!            G4, dantu s t                   sit = rt A >M I 515 OITF38                                    C52%ff                  J wASIC GAS SYSIEH VOLUNE CalCtJLAlleN. li wAS DETFRMl'4FD TH4 IHFRE WA5 J Al Vf 5                                                                                 10 -t' A T            A NEI OlCHEASI l '8 SYSTEM VOtuMC. A SYSTEM CHECK WAS P E '4 F O R M E D ANC A IJ AK C ut* Pi ttiL N I FillesM                                                                                  lita D I Al*FR A .P' VAtVE wA5 DISCOVERED. Ibl5 IS NOT A RtPFililVE EVENT. AffC
                 ;15                                                                                                           C I I' O PARI hA5 RFPLACFD I N K l'40.
                  **AR ilCut A f 2                                                                                                lite D i at'l St AGM ON A 2" GR ifettE L L Dl%PHRAGM VALVE HAD FAILED. EXAMINAllOrt 0 2 50.104 tJC l luial                                                                                          F fitE DI APHR AGP lticlC%IED Ail %CK UY A PEIROLEUM OASED SUBSIANCE. THE DIA wA5ft 4615P a> At t! ult sit:G. Vr.i in aiP                                                                Pas t&GP tea 5 stEPLACED leIIH ONE IN KIND.
                                                                                                                                                                                                                                           +
I lWi- l                                                              'p 0-02 H                   070974                 AU4. 2 LOG. *t AD I Al l ott AL AttM RECEIVEU. A **055 8 0L E L E AK AGF PATH FROM AN 150
             'i t '. 4AD:OACI .eSit M t I G t. *i i SYS G i n 3 t l.                                       O!!9Fs                 LATED WA58F G A5 Clif4 PRE 550R 00tiL D 'It AV E ExtStro FOR 28 DAY 5. A MAXIPUM POS 1 At. VE 5                                                                               2 - h e; t's           SlHt E We. EASE OF 172 Cuttle 5 UF xE-131 W A5 RELE ASED IO IHE Aux. BLOG. 150 CuttPO 4f *4 8 I All o tF                                                                                  -2BS/14-143
               & \5 aOfiL 2 ' A '.                                                                                                  1504. A l lPN V A L V e; ObeG 92 3 t>R       A5 FOUND NOI FULLY CLOSED AND Cout0 NOT BE CL I f t Lu.t t t )
05 r, p g g;,tt l E L Y . 10 RE4504 15 M *3Owf 4 A5 YEI.
I sle+ tit a .         4 4 -) *. .
                                                                                                - - ~ .
IattitN PC l'ai - 8                                                  3C-t'005                    O l l 4 F 4'           50't V5 Y OF UIlLITY I tlN'aE L Ol5CtH5ED fil4 T FLOOR WAS CONISMINAIED 'lY IHE IM LIG 't AD I O A C I seit? **C4A:.5 NT SYS 0C1998                                               020!! T4              P98:PF't ora lNAGE OF 100 GALLONS'l1.84011 fir R ADID AC T IVC t. lyOID W A5 f t.             Tite Lunett k'4f Cth 2                    iel t IPt-ICictE                                    2- wt EK                  5A*se ELEVATU9 Pil O't A l tw His REEta plt 1GGtD AND It'E ARE A POSTED FOR t40 00M e t_*t % Wl at t cude.4                                                                                    P I '43 l Af t-4-4 -4 3.
i 1t't8 4 H pla tlLut sIE                                                                                                   l '' t $ 1ND-E LS V A i n't Pli D't A l *a W A5 I ttCOR* [ C I L Y DELIVED 10 DE CONNECTED 10 I l.cAtt                                                                                                       HE i.A s i e. CottFCTICN SY5lEM. AC TH ALL Y . IllE DR AIN L INE W A5 OP[te-E'40E0 IN I Jiit iI Y Its a'er a                                                                                     i s t'  UIIt iIY IUNNEL.
(JCo g :-l                                                           16: ~ 02 s, )                O l l i f e,            177-33 Ita ADWERI Arti (tfLFASE OF ).2 CURIES or LiculD RAnin4CilvifY 10 UNRE                             ,
FE.owAffa 5)ST "5                           . ;ia :I t0L i       o le?>13                     n203F6                 S T'l l C F C AREA. P A IN-CE *45.t A10R HY CR OGE*: COOLER GA5KET LFAKED CONIANINAIIN oEal st .. le tN ~. .c4 5                                                                2 -h F t es            G l tJ'11'4F . Des t L CI NG s f H Anh SRD 4 F VELS A!aD G A5E MLtai.
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a f a.u l 9 lato*/                                                                                                      Cr e tCil f t POOCEDuuEs t taCRMAL MEIHOD OF TESIING FilR SIEAM GENERATa)R LEAK i.2 Cu e lt                                                                                                 hA5 auf U5f f.. U tilf R P C R 50'41E L FRRORS AL $tt INVOLVEO.
I A w 5 s.vt ttf le:,. it f u tet $ li. t"            D t t l et ,
a' Col J-l                                                           ia -0 2 t.1                  01107F                  I T T- S i Da 1/15/77           A tt 5%DICAllON OF A PRIMARY-in-StCONCARY LEAK IN istE Hi siE R F: AT /5Til
* P.rd C', W SY)                            OITU62                       02037F                  I ti" ONC J - T een 00Gil $1EA" GEteF R A Tost" 10T5Gl ftESULIED IN A SHUTUOWN OF OC0ta E Lowed et NI C out oui W tlCA*.L3                                                          S G- D A Y             L u;41 f I 15EL         .t o-2 69/ F F -21. As A RE 5teL T OF EFFORIS 10 LOCATE THE SEAEING ot M Li tvr reH;e-~:ene n                                                                                      5fLAM SENF2 A T111 IUBE. AN 1 -8 40V E R I E .NI RELFASE OF RAulOACilVITY OLCURREO l '.u l H                                                                                                 WH I Cit "KC7[0EP IDE LIPlis 0F TECHNICAL S P E C I F I C a l l0te ).9
                      *I 4 f esp E                                                                                                    CC't t .t
* t Y l o e*1HC E otrt ES . 1940 SIEAM GENERATOR WA5 N0f DRAINED ANO st F F I L L'E D H J E ,a is         6. i . I                                                                                     wltH CtfAte HAIFA. U E l l E V I .'sG T HE W AIEit 50 UE CLFAN. II W AS .Nili SENT to R a l 5: t e r.t Gr _ og,, g:a,gg gs                                                                         go;.,g 3 g r , g,,ca rF OR E THf MPl. ANNE C STELE ASE l
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C HPPO. et 'll /                                                       Evt'ai DAIT/                                                                                                               ,
C10%E Cthd /                                tD I MLI         '4.1. / % POR I H A l '.; /                                                       EvFN! 0F5CRIPTION/
tC I & IH:= /Cn'a ll' e t / w l / t DC                 C H a l q ut. til .          RI petri IYPE                                                          CAUSL OF5CRipilON t ' t. q t . l - 2                                                          31 '12 T 0              10n17,             175-199 titsPL A.4NF O REl f A%F HF RAOlOACrivE LIOutC f Rutt THE QUENCH g aran itne ti. R its l H R t MI f M i la .#t i SYS O l Me55                                               12 2') T 2         t) UGH A t r e st Y VAlvC Af40 Ate HPF N-FNDE D 8'I PE INIO THE IUMINE BtIILDING $ UMP
* l P L 5.8 t i l l't. 5                                                                O f t t', R         . 4300I 10 (0:4555 MAy HAVE BEEta R EL E ASED DUR ING 1974 AND 1975 t)i f i L i i v i e* 1t le. L au*tt5 I 14.0 8 ,
* E x t 'sF. t'                                                                                             OEF ECil vE 8*ROCE DU6tE s Cutt l NG SYSIEM TUaNOVER llNITBAL S T A tt f uP I THE PlPE C Anoul 30 Co t t 5                                                                                         tsi FU1 A SICAM GPaER A IOJ FLis5tl wAS NOT IDENilFIED A5 A *l UNCOMPLETED,liEM f on ts.iH 10441              t-    sm l L 71. 4 0 su       t' .                                        .
            *' I t . 11-1                                                                e i- 12 8 5           0%C4FF              ITF-89/stl ~t RtlM 2/2f/76 I!! 5/3/FF. AN Av F R AfiE SCO G AL LON S PE R DAY LEAN O 4#1 5YS ' Oft '.At                        tu s
* Lii al                C l f F )'8            0t.017 7           t'CH1100 14 thE 55W/RRCCh stE A T ExColANGER "R". ABOUT 2.34 Cl OF CS-117 TH siE Al LxthAsG 45                                                                         10 -u t y E PR E DO** lti Af s t ISOIOPC.wAs 1ELEASED.RLSE CONCENTRAlluN WA5 WlIHIN Limits.
Lis*Pil (c 11           iIe is to t 18.010
                       'A4f!Liit \ll                                                                                              ll' Cal l!!D OT G't AD& f i tlta Uf A IqE AT f RCitAttGF R IUDE C AUSED LE AK AGE. Ul5CHAPGC
: 2. 44 Ll4LS ISf3                                                                                              C 04Al =Alft Arf 4L V 5 l s . i4 AC I A I I ON **0N I T O R I NG OF 55W UUTLET. Ata0 IMPROVED tr 4 Int Aut at t V . ) tt ! s #C W A lt t ei?o W A I F 84 I (vi'a f utt Y MLNlfOs8Er46 AI4 F TO PRECLUCE RECURRENCE.
          ;u t t. CIII'5-t                                                      %,        ^2i4            975f75            Or.5 Ae'PL 2D L aureDft v w AT ER W45 INanvERIENTLY Ol50ttARGED in THE RIVER DURING e 8 .. 4 ADIOTCl ni i .: H& s t ,e*i l 5YS                           0130'12                   612515               fil 509t AR C,0 sjf fisi "A"      FLOOP OR A lts S AMPL F I4f4K 0U0 IO IMPROPFR L INI UP OF
                   ..OtTH .f .4 T t at s '' tif f Wet It ant f                                               2-# E s            W A t '/ i 5 kHICit RESULIED IN L AU'40R Y 44AtEP nEING ADCED 10 THC "A" FDST DURIN PF,t stas ett          ?.494                                                                           '', II5 DISCIWtGE 150-258/F5-868 t40u10
* l s i t; t t                                                                                             l't's '4 A l fl
* E R'4 01 l es NOI C L il5 E L Y CitECKING VALVE CLO50RL. ABOUT 150 GAL LONS LL55 t H Ut           1. 2 4.9 t l L %                                                                    8 ;8    O't 51 ** t* 8 8 0 WAIER WA5 O I SCit AR GF D.       I1985 WAIER 61A0 LL55 ACilvliY THAN THE 6t i v t -4                                                                                               f451 h4frR.
s u sa 4 r - t                                                          ', ") - S / s 3             IBOF74           tosPt OstiC i*s0 HNCONI'4Ct LE O .t E L E A S E OF RADIOACIlVITY F' TOM IHE SITE OCCURR t int 5 Y 5 I sl1            8t' 1C 10 (
* t Hill        ral l 21 *e                01t^73            Er Ov654 A 15 UAv l' E lt l C D . A SiOW L E sk FROM THE *tEACTCR COOLANI 5YSTEM IO e i 11 c a Z l a t a ~i . 8 5                                                             2-hfEA             I6*F 40'er tSGPsE R A T I vf HEAR E x CII ANGF R L OM P ON E.N i COOL i t4G SYSTFM AND THEN IHR t_ O"e. e s'; 'a i F a tt u tE                                                                         Du its I H r. C OM P 0 tie.c f ConLING WAFER stE Al E X CH At4GE R INid Tete JAMES river WA5            ,
1l9ut0                                                                                                        8 tif f L t)a t' A I t'. 8 AU- F %-I il sg wPt IC                                                                                               Sl ow LFars IN SfVERAL teF AI E X CH ar4CE R S Af40 T H E t4 A f uts E F A ILORE C All5E O IHF l.4 t utlES                                                                                                  ifAF. UNE S u+t r.E I At4K tEVEL ABARN AND ONE RADIATION MONliOR AL50 F A ll E0.
j                      eve:s alvt:
e                                                                                                  45.045 G A t t O' 5 A:40 2.4 CteR if S WE ft[ RELf45ED.
t       S ud it y - t                                                            > N2 9')                  1220 f 4          t!NPL A 1'4LO RELE 450 OF LOW L E vtl RAOlGACTivE COMPONENI COOLING WATER IO TH C.):lt S YS F D4 A tt int < e e nre t                               0148F/                     0 8 2 .9 F >      E J4MES river Otit l NG A Ura l i OUIAGE. P I NeiOL E LEAK 5 IN TWO IU8E5 OF THE CD of a t CtLHaura5                                                                          2-W5En            **P O'40 I CCOLINC HEAI EXCHANCER (EAKEE) 3A9 GALLON 5 IN 18.25 HOUR $3 APPftOx                        *
                     ; d ee tl -s t ra f  I' t i t. u 'i                                                                     I t' A f fl y 120 Cull [5 WA5 'tElf ASED.' A000f                   1. 3
* 10 1- 10 PERCENT OF MPC. 1A0 Ilt s t a                                                                                                 161 e u t t u tta t i t.                 l                                                                      Cut l A l's CH"st l as4TieJN5 OF COMPONENT COOL ING SYS TEM PUMP APsD ltE A T EXCHANGER ti t ' Cu ifs                                                                                            5 C AH5FD F ECE55lvF Sf9055 ljte IHE I tniE S . CAU5tNG MF.CHANICAL FAltuRF.
                      ;sH.s  t    livt3

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                               -                                                        .=.                -                         _                                                                                                        . . .
LER OUTPUI Ott CCilVIIY QELEA5ES                                                                 _                                             j F R O P' 1969 in iniE PRESENI OUIPOI 509TEU 'l y Ist''F OF tCilvity. FACILIIY AND EVENI DAIC                                                                                                     , !
FACitilV/
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id Pt' .t l t.; A T F #                                                                                    EVEhl DESCRIPilON/
                                                    .C I Fa tta/CO 4);; si / AP f /LHL              LH .Iful       IG. REPO9I fvPC                                                                                                 CAU5F OESCRIPituas S H 44 : V etel al-4                                               sc ')241           l t: 2 t T 2            lis-lol HPePL ANNED 1 Ell ASE OF 4ACIOACilVf LIQUID. AFIER CLEANING iliE WASI 114 t a'll H AC I W5ff site 43r#81 SYS 4143673                                   103 tis                 F HOICtW T A set SWHil. THE RF511RIE WAS PUMPE0 10 DRUM 5 IN THE SPC*si FUEL C
                                             'I'*Es.s 1T11 % 5                                                         7-WCEn                  Air Ad[ A. P R50NNCL INCCRRCCILY DeAINED 8RO G ALLONS CONT A f te tNG 7. 8 CURIC 48LfLLilVL P''OLL Cts te s                                                                     5 g Cara g t i g g *gIO A s t ata p 5[w(R well Cl4 EMPilES INIO IttE Ga0tlND P4E Ast IHE PLA I 1001'.;                                                                                         ta l .
Ne l l Cen A I S-                                                                                   GElECil/F PwOCEDt31L5 ANC PER50Pa[L [RRORI IlsF CA$K ARFA FLOOR ORAINS WER 2.1 C16 :11 5 .                                                                                  C s<ll L .t eF Lc D . ANil P E q 50*aNE L p l c NOI PROPERLY 10ENilFV THE DRAINS.
VN 4G          't ; A *   **t   t a l ,
t es tL Y                                                          S M2S t            IO2tia                  10 4
* 7's-105 AFIFR CL E Ai4 t NG THE WA5TE ttol 0UP IANKI IHE RE5touE WAS PUMPE P=,l til - 4 016231             1C387>                 H TH O2tfFS IN ItsC SPFN! FUFL CASK AREA FOR IEMP siORACF. pCR50NNEL I NC OR Llu 4 G islaCT 4 T ti :* 4 s t ra f 'if5                                                                  tCCILY Ost a l'sE D 180 Gat t r*45 CONT AINtasG 2.1 Cl ICUBAtil INio IHE FLOOR ORA PIPf5.Fillt's,5                                                              2 - me IIK UL F 'X I I VE ."10CEdot[5                                                                     I t? wHICat E VEtsIUALLY EMP T IES l '4 T O IHE GR0uND NEAR THE PLANT. SURRUtiNDING
: t. t ;;t t i h Lt'*D H45 SALI-WATER WATER T AliL E ANO *so *0iAHLE WATER 5tjPE'l lE S .
DEFECilVF P10CEDumf5 tND PER50Nt4E L E R8t0R: THE CASK ARCg It00R ORalt45 WER                                                ,,
                                            ' A.t i t cut n II                                                                                 E '40 T LADELED, AND PL65CNNEL DID NOI PROPERLY 10ENilFY ittC OR AI NS.
8 2.1
* 1-Liis at i ptosi su aces pa 1 at i
50-4211            Pil a r e.              IEa F6-223 OUa l esq A ROUTINF PUMPDOWN OF IttE FUCL Olt 5TORAGE I Ar4K SUMP o V '. H ".t h a t    V.1'lK t. E - l t1. RAultlaCT 66 f 8; M .1 4.t !.!.ii- 5YS U l st: F6                            06067.                  N F / 2 0.HP[ u A TOtt NUI I C Ct1 AMNORNAL WATER LEVEL IN THE PU"P Pli AREA. INVES C up i's P 8 E s t C 3tM '.u l aartlCAdLL                                   2-WEEK                  it";4flON REVEtLCD THAI WATER WA5 'UP4NING IP4 IHRu ELECT *t lC AL CottCults IHA P L '* $G aNL t Ut <t e ' t I bee P E IN 00MHurstCATIOta Wlin THC CONDE te 5 A I E 580 RAGE TANK IC5fl MHAT. A                                             '   "
L liso lo                                                                                          5 s FPt e: UF THE WATER 5He aW E O THAI 88-3 WAS PRESENT. WATER LEARCD 10 REVER.
etI a f u aL ist.1 C AU5F. Wi5 THE EEI5TENCE DF TWo L E AK AGE P AInt5 OUI OF THE C5i NOAI 10
: 1. t, Cl al- l IHC SintF 01AIN SY$ TEM Aten AN INADVERIENT UVERFLOW OF fitE CST.
l CSI 10 CO*8 se' C i lCO I tiVtu                                                                                                                                                       ,                                      ,
l i
vH l's a 1t' sL H. !                                               3a-n2 t c,         922ti F 3               THt %I's E JFCIOR Ol5 CHARGE GA5 MONI TOR al5 PEGGEO filGH. IltEN DROPPED LOW.
siti a Sit ar 5tte>I y ses , ru st                            C l 2 2? e.        038175                      W 55HR I UM LEVEL WAS Ott5FRVFD T II RE OROPPING. IliE 4tfx . BLOG. STACR M p t. A l C x C i A't y tt s                                                  7 :vF C n              IT ils"4 A L AR'* E O.         THF MAXlMUN 15 MIN. "tAIC OF 2 CURIES PCR SECONO WAS Noi                                             !
COMPolt'al I s l a. t e s t.                                                                     CtC"EOFD AI A *d Y IINE. I'20-2 fit,/ P S-41 M 1
* I H,t s                                                                                                                                                                                                                             [
s'l a LOP E                                                                                          SPP A't EP. I t Y % PRINAilY in SECU*4044t Y LEAK IN SIEAM GENERATOR '8' CAUSED THE                                                r Hts Chitr5                                                                                        18:4Pt 4 8 4f D REL L ASES.           A F i r4 AL R E POR T W il.t. FOL L OW.                                                    )
4Ha l t. i tg y ,ef i t til eG gr .I sutty-l                                                          ' 5'l-02 tl0         0A0375                  175-15) CURI:sG NO.1 MAL OPFRATION AN tJ4PLAfdNED RELEASE Or RA010 ACTIVE MATE                                                      ;
                                      .ia, MtulHACT w 3 I 5                    t* 4 7 t rtat I SY5 013I11              091975                  titL F10M THE SITE OCCU1 rep. APPROP8tl ATE OPER AT ION AL PROCEDURE 5 wERC FOL                                                    i
                                          / l e* E S , F l f l l H F.                                                  2-WLEK                  LCWED I ti ISOLAIE Tite *tEL E ASE .
COMeu 4Pe t t SILinF                                                                                                                                                                                                               j
                                       ** ; A i uft i 14T095                                                                                          00ureksE;.T I Alt uREI A Lot sE F I TIING Ons "D" OVERHE AD GA5 COMPRESSOR AL L0i4 E 2n.S Cl T H 1.t                                                                                 O t i ft .tCC NC R AD]OACilVC PATERI AL in LFan It4IO THE GA5 STRIPPER ROUM AND I AU411lARY 4 0;. . vr al i n A f ** 5.*sd u t                                                  0 THC v 'li tt af in's VENI.

_                                                     _                           m   -
LER DUTPUT OH EUENTS IHVOLUING RELEASES                                                                                        '
FROM JULY. 1977 THROUGH DECEMBER. 3977 OU T Pt4 T $0RIED BY FACIL1TY TVPE. FACILITY AND EVENT DATE FACILITY /SYSILM/                                                                                                   FORM & CONTEf4T OF ACTIVITY RELEASED /
C ur1PDHt H I / C OMP0HE H I SUBCODE/                                   EVENT DATE/                                 AMOUNT OF ACTIVITY /LOCATIDH OF RELEASE /
HElitOp UF DISCOVERY /                               DOCKET NO./        REPORT DATE/                                STATUS OF REACTOR /                               2 PDHER cal 95E/CAUSE SuhC00E/                                LER HO./           REPORT SOURCE /                                      EVENT DESCRIPTIDHI
              ,      NAHHFACTHRER                                         CONTROL HO.         REPORT TYPE CAUSE DESCRIPit0H i
CRYSTAL RIVER-3                                                05000302           090777          GAS                                         HOBLE GAS                                                    I CU;lPRESSED AIR SYSTEMS + CONT                            77         04T        091577          ta$ CURIES HOBLE GAS                        RELEASE TO TURBINE BLDG VENT TO ATM0                          i VOLVES                                                         019000          LICENSEE         STEADY STATE OPERATIDH                                                      099 Ho SUBLOMP0HENT PROVIDEO                                       PHR             2-MEEK          (ER77-1073 HODE 1 OPER.--UHPLAHt4ED RADIDACTIVE GAS RELEASE TO TURBIHE BL UPERAllOHAL EVENT                                                                                                                                                                                        l DG. OCCURRED & RIPORTED IN ACCORD WITH EHV. TECH SPEC 5.6.2.A. REDu!10AH
           .      CONP0HEHT FAILURE                                                                               CY N/A. HOBLE GAS RELEASED TO TURBINE GLOG. FOR 12 ilRS & 40 MINS.              UHPLA CAUSE SUBCODE HOT PROVIDED                                                                     HHED R ADIOACTIVE - 43 RELE ASES H AVE BEtts REPE T IT IVE BUT FIRST OCCURREHCE i                 An iUtl A T I C SWITCH CD (ASCO                                                                 AS A RESULT OF THis CAUSE.
DURING MAINTEHANCE ON HYCROGEH SUPPLY SYSTEM. RADIDACTIVE GAS FROM MAKEU                                 '
P TAHK LEAKED BY VALVES TO TURBIHE BLDG VIA VENT VALVE.                                                  ,
CLAvtR VAttEY-t'                                                   05000334           072577         LIQUID       _
HlXTURE                                                         ,
DEttlH HATER HAAE-UP                                        77          04L       081777          3.4 CURIES TRITIuH                           SENER 10 rider VALVES                            .
018835         LICENSEE-         STEADY STATE OPERATIDH                                                        088                            )'
tiu SUBCOMPDHElli PROVIDED                                      PWR             30-DAY         (77-75/04E3 R.G. 1.16. ETS 5.6.2.1. OPER MODE 1. 6B PRIMARY GRADE HAT DPE R A T lot 4 AL E VE tel                                                                      ER STORAGE !ANK HAS DISCOVERED DVERFLONING.             TANE C0ttT AlHS RCS HAKEUP HA PERSO u4EL ERROR                                                                                  TER. APPROKINATELY 9.000 GALS OF WATER HITH TRITIUM CONCEHIRATIOt4 0F 0.
C AtISE SueCODE stG T PROVIDED                                                                1 CURIES PER M LITER HAD DVERFLOWED. PORTIDH OF WATER ENTERED STORM CRA                             .
IIEH 180 T APPLICABLE                                                                            IH. RIVER WATER CONTAltlED HEGLIBLE QUANTITIES OF BACKGROUND TRITIUM.
IN PREPARATION FOR DRAINING HATER FROM TAHK. VALVE LINEUP HAS PERFORNED WITH THQ WALVING ERRORS IN VALVE L it4 E UP PROCLDURE.
DEACH DOT 10H-3                                                    05000278          100477         GAS                                            HALOGLH REAC COOL CLEANUP SYS + CONT                                  77-049/04T-0        *01877          0.0807 CI 0F I-831                            UNIT 3 BUILDING VENTILATIDH STACK                               t et E A T E XCH At GERS                                            020412        L I C E t4S E E   ROUT!HE STARTUP OPERATIOll5                                                   050 8tEATER/C00LER                                                 BWR      "
2-HEEK          1-131 RELEASE RATE FRON UNIT 3 VENT STACK EXCEEDED T.S. 3.8.C.2 FOR A 24 R0011HE 1 E S T /IttSPE C T I GH                                                                     HOUR PERIOD. VENTING OF RNCU REGENERxTIVE HEAT EXCHANGER AT RATED PRESS DEFECilVE P90CEDORES                       4       ^7 , , '
* URE AND TEMPERATURE RELEASED I-131 IN EXCESS OF LIMIT.0PERATOR INVOLVED 840 1 APPLICAstE                                                                             IN vet 4TlHG RECEIVED I NS I GH I F I C At4 T UPTAKE OF I-131. ENVIR0ttMENT AL MILE SA FLRffX. INC.                                                                                     MPLES INDICATED NO ADVERSE SAFETY CONSIDERATIDHS. RELEASE RATE WAS LESS THAN FOUR PERCENT OF T.S. LIMIT HITHIN C HOURS OF INITIAL SAMPLE
    .                                                                                                                                                                                                                      ?
RELEASE CAUSED BY VENTING RHCU REGENERATIVE HEAT EXHANGER HITH IllGH I-13 1 CONCENTRATION AT RATED PRESSURE A t4D TENFERAIURE. CORRECTIVE ACTIONS IN CLUDED REMOVING RHCU FROM SERVICE TO REPAIR LEAKS. PLACING EQUIPMENT CEL L EXHAUST Ott SBGT AND IMPROVING PROCEDURE FDR V244 TING RMCU.                                                 .
t
                                                                                                                                                                                                                           ?
I L   . . . .                              _      _

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                                                                   - . . . . . - - . .                  .                                   .                 . . _.~ _.                                                                                 .-- -
LEC2 OUT Pui ON 'EUEllis INVOLVlt4G E1E L E ASES FROH JULY. 1977 T H R OU Gil D E E E t10 E R . 1977 OUIPUT SORTED BY FAClltiY TYPE. FACILITY AND EVEHi DATE F AC i t liv /SYS T E tt/                                                                                                         FORM & CON T E tt i 0F ACTIVITY RELEASED /
CunPU::E tti /COMPONt tei SUBCODEI                                           EVEHi DATE/                             .            A H00 t4T OF ACTIVITY / LOCATION OF RELEASE /
STATUS PF REACTOR /                                                                                             % POWER ItETHOD Of DISCOVERY /                                 DOCKET t40. / REPORT DATE/
CAUSE/CAUSE SUBCUDE/                                   LER tio . /           REPORT SOURCE /                                                                        EVEHI DESCRIPTIOtt/
N1HUFACTUREN                                           Cotif ROL HO.         REPORT TYPE                                                                            CAUSE DESCRIPTION Htif tB0 t u t BAY                                            . 05000133            072277            LIQUID                                                                         PARTICULATE Ll4 RAblOACI WSIE HAHAGNHi SYS                                 77- -         03L      082177            2. 3 3 CI               .
RADWASTE FL DR TO OH-SITE EFF. CAHAL INSI RHt1Et41 A 15 0tt
* CuttiPOLS                                  018848         L IC E t4SE E       SHUIDOWN EXCLPi REFUEllHG                                                                                                                         000
           .. 180 SUBCut1 pot 4Et1T PROVIDED                                       BWR             30-DAY            (77-021 Att UNH0HI TORED R ADIO ACTIVE LIQUID RELEASE TO THE EFFLUENT CANAL colliltaE T E S T / INSPLC T IUta                                                                      OCCURRED INVOLVlttG LESS THAtt 2000 GAL L0teS OF CONCEt4IRATED WASTE CONTAINI C uttPottEtti FAttuRL                                                                                   I4G CS 137 AND CS 1 3 '. . THE CONCEHIRATIott F O L L OW i tlG DELUTI0tt Its itIE EFFLUE CAUSE SUBCODE H0f PROVIDED                                                                            Hi CAHAL WAS LESS Ill AH 9.7 X 10-6 UCl/HL.
AulOCott ItIDUS I R I E S RADWASTE StsH P PUHP AUTO START SWITCH (AUTOC0tt FLOAIROL) AHD LEVEL ALARtl (HAGt4ETROL A 152 SP-SS3R BECAHE OR WERE IHOPERABLE DUE 10 CORROSIGH But LDUP.
HuttBut D I DAY                                                     05000133            072277            LIQUID                                                                        PARTICutATE LI4 RAD 10ACI WSIE HAHAGitHT SYS                              77             03L      080277            2. 33 CI                                                                      RADWASTE FL. DRAIN 10 OH-SITE EFFL.
It3SIRUMErfl Ailutt + C0t4I ROL S                                   019172          L IC E t4SE E       SHUIDOWta EXCEPT REFUEllHG                                                                                                                  -     000 1 Hu Sut*COHPutittli PROVIDED.                                         BWR             30-DAY            Ott JULY 21 & 22. All UHtt0HI TORED RADIDACilVE LIQ 10 RELEASE 10 THE EFFLUE k tlu l l H E I E S I / I t4 SP E C T 10H                                                               tti C At4 A L OCCURRED IHVOLVING LESS ill AH 2000 GALS OF COHCENTRATED CS 13 7 A Cut 1P0HE H I F A l t ilR E                                                                             HD CS 134.       THE CONCEttiR AT I0ta FOL LOWlHG D I LU i l 0tl I t4 THE EFFLUEt4T CANAL M CAUSE Su tt L U D E HOI PROVIDED                                                                      AS LESS ist AH 9.7 X 10-6 UCl/Hl.
A U i OC Oli t ilDtiS T R I E S Vt lindell Y AftF E E-1                                  05090278        97e678      HIXfURE                                                                ltA10 GEN                                                                 l NEACI0lt CORE                                     78-422/0%t-t 888278             0.0778 CI I-838                                                        VEtli ST ACK TO Airt05PHERE E UEt Et t flEttil                                     623838       L IC EttS E E      SHU100tlH EXCEPT REFUELING                                                                                                            get S H B C Dtti'OHi tti Hof APPtICABLE                                 St-DAY      DURING OPER AII0ft OF t1(CH ANIC AL V ACUUtt PUt1P F0t t oulttG tt0RtlAt SHUIDOUH OF ROUTillE IESI/INSPECTIOI                                                          REACIOR AND AUG11EttIED OFF-GAS (AUG) SYSTEN. SIACK t*08tE GASES AftD RA0101 C 0t1F DH E til F Alt tfRE                                                        ODlHE tEVEt5 IHCREASED tsuRING THE PERinD JutY I. 1975. THROUGH JHt Y 5.
F1Etif AHIC al                                                                   9978. RADIOL 00lHE VEHf STACK 5AtlPtE5 SHOWED IHAf IHE 2A I-839 REPORTING GtHERAt ELECIRIC CO.                                                              LEVEL OF EIS 3.8.C.2.C WAS E xCE EDE D 7/6/78 AT I400 TOTAL I-838 RELEASED FOR IHIS PERIOD WAS 7.8SE-2 Cl. Ittis EVEHf EXCEEDS OHtY tittIIAL REPORil NG REwEL. NO S I CH I F I C A!1T INPACI UPUtl PU8 TIC HEAtIH OR SAFEIY.
DURittG 6/78 BE FOR E 5ttt110018H. $JAE ACIIVIIY INCRE ASE D F Rott H0Rnat <5000 10 25.600 ttICPDCURIE5/5EC. INDIC AT It4G DECR ADailott OF FUEt CLADDING. AT 5 ttufD0uH REACIOR VE55Et I-tSt C ollC . taA5 2.26E-1 UCI/ tit . UPON SHulD0uf t OF react 0R 8 AUG SYS. FUEL EL Et1tHIS W/Df f t CIIVE CL ADDlHG Wit t BE REPLACED A i REFUEt DUTAGE. R ADIC ACIIVilY W AS VENT ED tt0Rt1At t Y.

     .   /
ENCLOSURE 3 The maximum allowable releases of radioactivity from nuclear poi;er plants as ex-pressed in the regulations have uncergone two somewnat major revisions since the first commercially operating f acility, Shippingport in 19b7. The initial effluent limitations plus the revisions can be summarized as follows:
: 1)    Prior to 1971 all operating reactor licenses tnat were issuea naa maximum effluent limitations which corresponded to off-site concentrations equal to the values in 10 CFR Part 20, Appencix B, Taule 11.         In general, tnese con-           '
centrations if continued over a year period represent potential ooses via the innalation and drinking water patnways of 500 mrem to tne whole bocy or 1500 mrem to the tnyroid, cepending on tne racionuclides in question.
           '2)   With the issuance of staff proposed "As Low As Practicaole" (ALAF) cri-teria (Feaeral Register, Vol. 36, No.11, Wecnesday, June 9,1971) the then AEC oegan imple.nenting more restrictive raaioactive effluent limits J
with the issuance cf new licenses. Tnese proposeo ALAP criteria limitea the releases to a small percent of the 10 CFR Part 20 limits, i.e. , a small fraction of the annual 600 mrem whole Docy cose. The actual cetails of these proposeo criteria and the rulemaKing proceecing that followea are too lengthy to discuss here.           A copy of tne June 9,1971 Feoeral Register no-tice is attachec for your use in unoerstanaing the initial ALAP criteria that was used in establishing maximum release limits for plants licensea after 1970.
I i
: 3)    On May 6,1975, the riuclear Regulatory Commission issueu its cecision in the rulemaking proceeding concerning tne criteria "as low as practicaole" for racioactive effluents (40 FR 6439). The Commission nas furtner amenceu the regulation to incorporate tne tenn "as low as is reasonaoly acnlevaole" 1
(ALARA) not to reflect a change in tne criteria, out rather to .use a lan-guage that more clearly cescribes its intention. The 14RC 1s currently in tne midst of imposing Technical Specifications ana Limiting Concition of Opera-                    !
l tion on all operating LWRs that implement this ALARA naling.             The major uit-        l 1
ferences oetween tne staff proposed rule in 1971 anc the t1nal rule tnat was                   l issueo are 1) effluent limits' are on a per reactor casis ano not per site and 2) tne absolute curie limitations wnicn were initially incluceu to limit population cases have Deen replaced by a cost-cenet1t type approacn wnicn                      J l
is site cepencent.
The actual racioactive effluent limits from nuclear power plants are not expressed
  ;     as curie quantities out as cases to an inciv1cual. These cases are calculational limits whicn cepena on the racionuclices present and the envi ronmental patnway s.
A copy of tne final rule (Appencix I to 10 CFR Part su) is enclosea for your use in perceiving tne current criteria for releases of racioactivity from nuclear pcwer plants. The staff is presently implementing tne "As Low As Is Reasonaoly Acnievable" type technical specification limits on radioactive effluents on all nuclear power plants. Presently all operating plants have tecnn1 cal specifications caseo upon the staff proposeo ALAP except the follcwing plants:             naccam Necx, San Onofre, Yankee Rcwe, Dresden 1, :sig Rock Point, Lacrosse, anu Uyster Creex. For tnese facilities, tne effluent limitations are caseo on tne pre-b71 criterla (i.e., concentrations of-10 CFR Part cu).

.     -   - -     - - - -      -   -     -.-      -                                          =- -
1 l
l Another on-going item that may be of interest to you is the implementation of the           l EPA's Uranium Feal Cycle Standard (40 CFR Part 190). In addition to the ALARA criteria of 10 CFR Part 50, Appenaix .1, the NRC will also be 1mplementing to all operating LWRs the environnental radiation cose stancards present in 4U CFR Part 190. The standard requires reasonable assurance tnat no member of the puulic is exposed to raciation from the operation of tne' uranium fuel cycle, wnicn includes nuclear power reactors. in excess of 25 mrem to the whole body ano 75 mrem to the thyroic during any 12 month period. This stancaro becomes effective December 1, 1979. The NRC's impler.entation of this regulation is Deing achievea tnrougn tne implementation of the "ALARA" criteria.
i Attachments:        ..
: 1. 6 9-71 FR Notice
: 2. Appendix I to 10 CFR Part 50 l
l i
l l
l l
l

      !(
4 o LA-1 PROPOSED RULE MAKING
: 20. Specincally, experience with licensed tion which may, on a temporary basis, AT0wpmlu tyggY LHanuUUmmlW10Rpfly y MQ1 Ulight-water-cooled nuclear power reac. result in exposures h!gher than the few tors te date shows that radioactivity in pen:ent of na,tural background radiation.
[ 10 CFR Port 501                                   -ater and alt emuents has been kept at but weu within radiation protection LICENSING OF PRODUCTION AND                                   low levels- for the most part small per- guides. Recogmtion of the need for this UTILIZATION FACILIT1ES                                 centages of the Part 20 hmits. Resultant operating flexibility 13 currently stated in exposures to the pubUe living in the 150.36alb).
Light Water-Coofed Nuclear Power immediate vicinity of operating power                                        The Commission believes that the pro.
Reactors                                     reactors have been smau percentages of posed guides .' . design objectives and Federal radiation protection guidese          timating conditions for operation for The Atomic Energy Commission has The Commission also noted that, in light water-cooled nuclear power reac-under consideration amendments to its                          general, the release of radioactivtty in tors set out below provide a reasonable regulation 10 CFR Part 50. " Licensing                                                                                                                                                    .
of Production and Utinzation Facilities.',
emuents from nuclear power reactors basis at the present time for implement.                                               i now in operation have been within ranges ing the pnnciple that radioactive mate-                                           )
which would supplement the regulatten                          that may be considered "as low as prac- rial in ecuents released to unrestricted                                            j with a new Appendix I to that part to ticable," and that. as a result of advances areas should be kept "as low as prscti-provide numerical guides for design ob* in reactor technology, further reduction cable." As noted in the amendments to                                                                       '
jecuves and technical spectacation re- of those releases can be achieved. The Part 50 published on December 3.1970, quirements for limittng conditions for operation for light-water-cooled nuclear amendments to Part 50 published on De. "The term 'as low as practicable' as used cember 3.1970 were intended to give in this part means as low as is practicably                                               '
power   reactors   to keep emuents as low as practicable.
radioactivity             in appropriate     regulatory efect, with re- achievarle taking into account the state spect to radioactivity in emuents frorr of technology, and the economics of im-                                              .
On December 3 1970, the Atomic nuclear power reactors, to the qualitative provements m relation to benefits to the Energy Commission published in the                                                                                                                                                          i guidance of the Federal Radiation Coun- public health and safety and in relation Fantut Ramsvra (35                   F.R.         18385) amendments to 10 CFR Part 50 that c.il that radiation doses should be kept to the utilization of atomic energy in                                                                          l
                                                                            . as low as practicable''. The proposed the public interest." The Commission wiu spectned design and operat'.ng require-ments for nuclear power reactors to keep                       guides set out below are intended to pro- continue to evaluate the appropriateness vide quantitative guidance to that end of these guides for light water-cooled nu-levels of radioactivity in emuents to un-                      for light-water cooled nuclear power clear power reactors in light of further ressicted areas as low as practicable.                         reactors,                                    operating expenence.
The amendments provided qualitative                                                                                                                                                        l
                                                                       '        The proposed numerical guides are           Under the President's Reorganization                                        j based on present light-water-cooled nu. Plan No. 3 of 1970, the Environmental te      ing wh d                    ect s 'an operations meet the requirements for clear power reactor operating expertence Protection Agency (EPA) is responsible keeping levels of radioactivity in emuents and state of technology (including recent for establishing generany applicable en.
as low as practicable.                           '
improvements). In developing the guides vironmental radiation standards for the the Commission has taken into account protection of the general environment The Commission noted in the State- comments and suggestions by represent. from radioactive mater!als. The AEC is ment of Considerations published with stives of power reactor suppliers, elec- responsible for the implementation and the amendmenta the destrability of de-                          trical utilities, uchitect-engineering enforcement of EPA's generally ap-veloping more de$nitive guidance in con- firms, environmental and conservation plicable environmental standards.
nection with the amendments and that groups and States in which nuclear                                        EPA has under consideration generally it was initiating discussions with the power reactors are located on the general applicable environmental standards for                                                                     ,
nuclear power industrF and other com- subject of dennitive guidance for nuclear these types of power reactors. AEC has petent groups to achieve that goal, power reactors. Meetings were held by the consulted EPA in the development of the                                             '
The Comm! Won considers that the Commission with these groups in Janu- guides on design objectives and limiting                                                                         1 proposed numerical guides for design ary and February 1971. The participants conditions for operation set forth below                                                                        l objectives and technical specifcation in these meetings were provided an op- to control radioactivtty in emuent re-requirementa for limiting couditions for portunity to express their views on the leases. If the design objectives and op-operation for Ught water-cooled nuclear need for more definitive guidance for ersting limits estab!!shed herein should power reactors set out below would meet design objectives for Ught water cooled prove to be incompatible with any gen-the criterion "as low as practicable" for nuclear power reactors to keep radio- erally applicable environmental stand-radioactive materialin ecuents released settvity in emuenta as low as prac- ud hereafter established by EPA, the                                                                            j to unrestricted areas. The guidance ticable; whether the guidance should AEC will modify these objectives and would be specincally applicable only to be expressed in terms of waste treatment umita na necessary, light water-cooled nuclear power reac. equipment requirementa and perfortn-                                    The proponed guides for design objec-tors and would not necessarily be appro- ance spec!Acations or numerical criteria tives and limiting condJttons for opera-                                                                 ]
    ,,       priate for other types of nuclear power on Quantities and concentrations relenaed tion                           for light-water onoled nuclear power                                       !
,I           reactors and other kinds of nuclear to the environment; and to suggest what faciuties.                                                     equipment or numerical entens would reactors are consistent with the basic tsdiation protection standards and                                             j As noted in the Statement of Consid- be appropriate at this time.                                        guides recommended by the international erstions accompanying the amendments                              Generally. the participants favored Commission on Radiologteal Protection to Part 50 pubushed in the PsosaAs Rzo. numerical criteria. Views were expressed (ICRP), the National Council on Ra-
:stra on December 3,19*0. the Com. that the criteria should be derived from distion Protection and Measurements                                                                           !
mission has always subacnbed to the potential doses to people or in the form (NCRP), a.nd the Federal Emiistion                                                                            1 i
general principle that, within estaoushed of quantitles and concentrations of radio. Council (PRC), (The functions of the i        radiation protection guides, radiation active material emitted to the environ. FRC were transferred to the Enytron.                                                                         I exposures to the public should be kept :nent. Some opinions were expressed that mental Protection Agency pursusnt to as low as practicable. This generai ; rin- present technology (including recent im- Reorganization Plan No. 3 of 1970.)
ciple has been a central one in the " eld provements) is such that !!ght-a ater- These standards form the basis for the                                                                      i of radiation protection for :nany years. cooled nuclear power reactors can be Commission's regulation,10 CFR Part Operating Ucenses include provisions to designed to keep exposures to the pubuc 20. "Standuds for Protection Against limit and control radioactive eSuents in the oSaite environment within a few from the plants, Experience has shown percent of exposures from natural back- Radiation", In this rega.rd, the NCRP that Ucenseca have general!y kept ex. ground radiation.                                                     announced on January 26, IS*l, the re-
* posures to radiation and releases of                              The partic: pants also stressed the im- lease of NCRP Report No. 39 " Basic
            'radioact vity in eMuenta to levels well ports. nee of opersting Sexibility to take Radiation Pmtection Cnter:a". 'Ite                                                                        I below the limits spec *ed in 10 CTR Part :nto scount unusual conditions of opers. NCRP noted that a ID-year study by the FIDIs At afGI5ftt, vot. 34, No.111-wtoNflD Ay, JUNI 9, IU1 ATTACHMENT 1 W

i'   1
                                                                                                                                                         \
1A-2 PROPOSED RULE MAKING Council has conormed the validity of areas as low as practicable will be speci. come into contact air tratel, and from most of the basic radlauen protection fled for other types of nuclear power many :.cttttt:es commonly engage'l In by criterna presentJy used by governmental reactors on a case by. case basts.                   the pubhc.
agencies to regulate the exposure of the             Neither wou!d the guides necessarily        Specif!c proitstons or guides for dessen population and of radiation workers The be appropriate for controlling level 8 of obfectires. The proposed guides for rad).
dose limits for indiv1Mi members of radioactivity in emuente from other idnds onctive matenals m liquid emuents the pubhc remain '.c Of rem per year of nuclear faelhtles sich as fuel reproc. would specify linutations on annual and the yearly dore lim's of 0.I'l tem per essing plants, fuel fabricatan plants. or total cuantitles of radioactn e matertal' person averaged over the population is radioisotope processmg p'.snts w here the except tritium. and annual average con.
unchanged. These limits are compatible design characteristics of the plant and centrations of radioactive material in w:th the limits and guides recommended nature of operauona mvolve d15crent emuent prior to dilution in a natural by the ICRP and the FRG and apply considerations. The Commission is glving body of water, released by each light.
* to exposur,a from all sources other further considera tion to appropriate water-cooled nuclear pouer reactor at a than medical procedures and natural amendments to its regulauons to specify site. The release of the concentrations background.                                       design objectives and limiting conditions and total quantity of radioacute mate.
The NCRP.!CRP.TRC recommended for operauen to mmimize levels of radio. rial from a site at these levels is not likely                   .
Ilmits and cuades give appropriate con. activity released m the operation of to result in exposures to the w hole body sideration to the overall requirements of other types of heensed facilities such as or any organ of an Individual m the off.
hesjth pmtection and the benenetal use reactor fuel reprocessms plants.                      site environment in excess of 5 milhrema, of radiation and atomic energy. Any                  Espected consequences of Fwdes for In deriving the guides on design objec.
biological ef'ects that may occur at the design ob;ccitres. The proposed guides Live quantitles and concentrations. con.
low levels of the 11m!ts and guides occur for design objectives for light-m ater. servative assumptions have been made so mfrequently that they cannot be de* cooled nuclear power reactors have been on dilution f actors. physical, and biologi.
tected with existmg techruques The selected primanly on the basis that ex. cal concentration f actors in the food standards 6etting rroups have added to 1stmg technolorv makes it feasible to chain. dietary intakes and other per.
the numerical rutdance the general design and operate light-water-cooled tment factors to relate quanuties re.
admonttlon that all radiation exposure nuclear power reactors within the guldes, leased to exposures ocstte.
should be held to lowest practicable level- The design objectives are expressed m               The proposed gtudes for design objec.
This admonition takes into account that terms of guides for limiting the number tives for radioacuve materials in gas-generally applicable standards or rules of quant 10es and for limatmg concentra. cous emuents would hmit the total quan.
estabbshed to cover many situauens tions of radioactive materials in emuents, tity of radioactive maternal released from must necessarily be set at a higher level It is expected that conformance with the a site to the ocsite environment so that than may be justif ed in any given indj. guides on design objectives would achieve annual average exposure rates due to the following results:                     noble gases at any location on the bound.
e cep 1lity of a given level of               1. Provide reasonable assurance that ary of the site or in the ocstte enviror..
exposure for a particujar activ1ty can be         annual exposures to individuals livmg ment would not be likely to exceed 10 determmed only by givmg due regard to the reasons for permitung the ex.
near the boundary of a site where one or millirems. Annual average concentra.
posure. This means that, within the basic more !!ght. water-cooled nuclear power tions at any locadon on the boundary of standards of FRC. NCRP and ICRP. dif, reactors are located. from radioactivity a site or in the offsite environment from ferent limitations on exposure levels are released m either hQuid or gaseous emu. radioactive todmes or radioactive mate.
appropnate for various types of activtues ents from all such reactors, will gen. rnal in paruculate form would be limited depending upon the circumstances. A erally be less than about fi percent of to specified values, level that is practicable for one type of average exposures from natural back*                  The proposed guides for design objec.
activity may not be practicable for a dif. ground radtauon.' This level of exposure tive concentrations specif.ed for radio.
ferent type of activity.
is about 1 percent of Federal radiation active todmes or radioactive material in The proposed guides for design objec.        protection guides for Endividual members particulate form would include a reduc.
tives and limitations on operauons set of the public.                             tion factor c! 100.000 for Part 20 con.
forth below would be specifically appl 1             2. Provide reasonable assurance that centration values in air that would allow cable to light-rater-cooled nuclear power anntal exposures to sizeable population for possible esposures f rom certain rada.
reactors. IJgh t-wa ter. cooled nucjear groups from radidactivity released in oacuve matenals that may be concen.
power reactors are the only type of power either liquid or gaseous emuents ! rom all trated in the iood chain. Resultant reactors that are being installed in rela, light. water cooled nuclear power reae. exposures to indinduals offsite woujd not tively large numbers and on which there tors on all s _s m the United States for be expected to exceed 5 m11hrems per is substantial operating experience in the the foreseeable future will generally be year. The reduction factor a ould include United States. The guides would nog less than about 1 percent of exposures a 1.000 factor by which the maximum necensorily be appropriate for control. f rom natural background radiation. This permissible concentration of radioactive                  '
ing levels of radJoacuvity m ef5uents from level of exposure is also less than 1 per. todine in air should be reduced to allow other types of nuclear power reactors. cent of Federal radiation protection for the milk exposure pathway. This On the basi.s of present mformation on guides for the average populauon dose, f actor of l.000 has been derived for radio.
the technology of these other types of These levels of exposure would be in. active lodine. taking into account the
* reactors. It is expected that releases of distinguishable from exposures due to milk pathway. However it has been ar.
radioactivity in emuents can generally be variation in natural background radia. bitrarily appbed to radionuclides of kept withm the proposed guides for tion. would not be measurable with exist. todine and to all radionuclides in partic.
light. water. cooled nuclear power reac. mg techn1 Ques. and would be estimated ulate form with a half-life greater than ters. The Cammission pians to develop from eSuent data from nuclear power 8 days. The factor is not appropriate for numerical guides on levels of radioac. plants by calculational technicues. These todme where milk is not a pathway of tivity m eduents that may be considered levels of exposure are obviously very low exposure               or for other der any actual           radionuchdes conditions            un.
of ewosure.
as low as practicable for other types of in comparison with the much higher ex.
nuclear poEer reactors such as gas cooled posures incurred by the pubhc from The f actor is highly conservative for and f ast breeder eactors as adequate de,        natural background due to cosmic radia. radionuclides other than loditie and 2s                  ;
sign and operaung experience is ac.
tion. natural radioacurity m the body applied only because it appears feaMble Atnred. In the meantime design objet. and m all materials with which people to meet                these average ned .tnnual   very lowexposure levels. The rates?.peci.
of 10 tives and technical specinc' ations f or lim.                                                nulhrems from noble gasm and specified itmg conditions for operation to carry               Aversee expmures due to natural bacli.
out the purposes of keeping levels of rreund rad:stion in the United States ar, concentrations of radiolodines .and par.
radioactivity m eduents to unrestricted in tre range of 106 125 millirems per year.          ticulates at any locauon on the bouncary l
l FIDERAL RIGilfilt, VOL 36. NO. Ill-WEDNts0sY, JUNE 9,1971 i ..
l

lA-3 l
l PROPOSED RULE MAKING of the site or in the ofsite environment erage exposures to large population of this notice in the Proeut. Rectstra.
provide reasonable assurance that actual groups aOuld be less than 1 millirem per Comments and suggestions received af ter annual exposures to the whole body or year,                                                that penod wiu be considered if it is prac-any organ of an individual member of                                                       ticable to do so, but assurance of con-the public will not exceed 5 m1111 rems.         Guides on techniest spee Acaffons lim- sideration cannot be given except as to na condHaons M ope @on. The pm* comments !Ued within the penod spect-Th'P"         d guides for design objec. p sed guidance would include provtstons fled. Copies of comments received may be uves woul pmvide that an app 11 cant for developing technical spectf1 cations examined in the Commission's Public for a permit to construct a light-water- with respect to limiting conditions for Document Room at 1117 H Street NW" cooled nuclear power reactor at a par
* operation to control radioactivity in ef- Washington, D C*
ticular site could propose design objec- fluents from light water-cooled nuclear              I* ** "            *               "#
* tive quantities and concentrations in po er reactors during normal operations
* amended by adding the fouowing sen-emuents higher than those spectfled in Tt.e technical specifications would be in-             nu at EM eM M paragram (a),
the guides. The Commission would ap- cluded as conditions in operating 11 prove the design objectives !! the appl 1* censes. These provisions are designed to g 30.34s Design objecum for equip.
cant provided reasonable assurance that, assure that reasonable eNorts are made                   mens to control releases of radio.
taking into account the environmental to keep actual releases of radioactivity in                 *eti'e rnaterial in effluent >--nuclear characteristics of the site, the concentra* emuents during operation to levels that               Power reactors, tions and total quantity of radioactive are within the guides on design objective             (a) * *
* The guides set out m Ap-material released by all Ught-water
* Quantities and concentrations. It is ex- pendix I provide numerical guidance on cooled nuclear power reactors at the site pected that actuallevels of radioactivity design objectives for light-water-cooled in either liquid or gaseous ecuents would in emuents will normally be within the nuclear power reactors to meet the re-not recult in actual exposures to thi design objective levels. It is necessary, quirement that radioactive material in whole body or any organ of an individui. however, that nuclear power reactors de- ecuents released to unrestricted areas be in the ocstte environnient in excess of 5 signed for generating electricity have a kept "as low as practicable.**
mmintns per year,                             high degree of rehability. Operating flez-         .         .        .       .       .
The proposed guides for design obj.ec* lbility is needed to take into account              ,.. Secuon Ma of M CM Pan M b tives (expressed as quantitles and con- some variation in the small quantities of centmuons in ecuents) for light-water- radioactivity that leak from fuel ele- amended                  by adding the following sen-e at W end M paraM @ .
oooled nuclear power reactors are ments wtuch may, on a transient basis,
    .suciciently conservative to provide rea- result in levels of radioactivity in eclu- 5 50.36. Technical .p.cificadons on ef-sonable assurance that, for most ents in excess of the design objective                           fluents from nuclear power reactors.
locauons ha ving environmental char
* quantities and concentrations.                     .         .       .        e       e acteristics likely to be considered ac-The proposed guidance would provide          (b) * *
* The guides set out in AD-ceptable by the Commission for a nuclear power reactor site, increases in radiation      perating flexibility and at the same time pendix I provide numerical guidance on exposures to individual members of the        assure a p sitive system of control, by a limiting conditions for operation for public living at the site boundary, due       graded scale of action by the licensee, to 11gnt. water-cooled nuclear power re-to radlod :tive material In either 12cujd or r           ases of radiosMty U rates of actors to meet the requirement that gaseous ecuents from operation of light-     release actually experienced, averaged radioactive materials in eSuents released water cooled nuclear power reactors at         over any calendar quarter, are such that to unrestrteted areas be kept "as low as the site will generally be less than 5        the quantitles or concentrations in emu- practicable."
milliterns per year and average exposures ents would be likely to exceed twice the         3. A new Append 1.x Iis added to read to sizeable populauon groups will gen-s4n @c@e quanWes and concen* as f oUows:
etally be less than 1 millitern per year,      trations. The proposed Appendix I would Amworz I-Nuussicac ocinas ros Dusran pr vide that the Commission may take           on,scTrvts ann trumwo Counmous rom Nevertheless. the guides provide that the      appre;.tlate action to assure that release Commistion may specify, as design ob-                                                         orraArrow To Marr rm carmion "as Low rates are reduced if rates of release of       as %CrtCA31.E* ron RaptoACTrYB hlAm!&1.
quanes and concentrauons in cuents             rw W-wamem NAs Ma f d oactiv        t rial above back un      actuany expertemd, amaged om any               aren men in either liquid or gaseous emuents to be     calendar quarter, indicate that annual released to unrestricted areas that are                                                       Sterzow 1. Introdu.etum. Section 50.34a(s) lower than the speci$ed quantities and rates of release are likely to exceed a provides that an app:tcation for a permit to range of 4-8 t!mes the design objective construct a nuclear power reactor stau in-concentrations if it appears that for a quantitles and concentrations. Release caude a description of the prettmanary design particular site the spectSed quantitles       rates within this range would be expected of equtpment to be instaued to maintain and concentrations are likely to result in    to keep LM annual exposure rate 2 M. c utr 1 ver radioactive matertats in raseous annual exposures to an individual that                                                     and itquid ectuenta produced during normal vi uals ocstte within a range of M          reactor operauons, including expected op-would exceed 5 millitems, mrema per year durmg the quarterly eruttonal occurrences. In tue case of an ap-Conformance with the proposed guides period. In the proposed guidance on tech- placatt6n sled on or af ter January 2.1971, the for design objective quantitles and con
* nical specifications, provtsion would be application must siso identary the desten centrations in ecuents would provide made for an appropriate period of time objoett'es. and the means to be amptored, reasonable assurance that the resultant for all licensees of light-water cooled for keeping leve s of radioacttre matertat whole body dose to the total population nuclear power reactors to implement the in emuente to unrestncted areas "as low as exposed would be less than about 400 guidance with respect to f acility P''#*****''
man-rems ' per year per 1.000 megawatts operation.
electrical instaDed nuclear generating to         e th a rete      of   toIe effr Pursuant to the Atomic Energy Act of nuclear power reactors to unrestrteted arm capacity at a site from radioactive mate- 1954 as amended, and section 553 of utle during normal reactor operstions. :neluding rial in liquid and gaseous emuents. Av.      5 of the UrSted States Code, notice is npected operational occurrenees, are kept hereoy given that adoption of the follow,      na low as praetteable".
ing arnendment to 10 CTR. Part 50 is cen,       This appenetz prcetden numerical guto-
        ' A useful measure of the total exposure                                               ance on cesign objectives and ;tmiting condi-ot a large number or persons ts the man-rem. templated. All interested persons who tions for operation to assist appucacts for.
The exposure of any group of persons men.s-   wish to submit comments or suggestions and holders of. licensen for Ita tt-s a ter-ured itr man-rema is the product of the nutn. in connection with the proposed amend- coo;ed nue: ear power reactors in meeting tue der of persons in the group times the average ment should send them to the Secretary requirement that radtoactive matertal in esposure in rems of the members of the of the Commission. U.S. Atomic Energy emuenta reimed from tame factutas to un-Jroup. Thus. tr encu marnber of a popuis-                                                  restricted aream oe kept "as low as prac-tion group of 1 multon people were expo $ed Commissten ,Nashington, D C., ~, ,545, tienbie". This guidance a appropriate only to 0,001 rem 11 mt!!trem), *be total man rern Attention: Chief. Public Proceedings for ugnt. water-cooled nuctest power reactors exposure would be 1.000 man rent             Branch, within 60 days after publicaticn and not for other trpes of nuclear factuues FECI AAL stGilri.h VOL 36, NO. I' %WIDNtIDAY, JUNE e,1ert

w                      -.              . . . -
W4
* l PROPOSED RULE MAK!NG                                                                                 ,
4 sec. !!. G uides on dessen obiecto rs for higher than thnaa spm:ned in thone parm- emuen ts to unrestricted areas as low as br a t-tr a t er . coo;rd ut. clear pouer reactors graphs rnay he deemed to meet the requtro* practicable.
heensed under 10 CFR Ps's 50. The guides ment for keeping ; eve!n of rad:an.ctive mm.                                Sect. ton 60.36a(b) provides it.at beenaces for design objectives sempreued as quantities tenal in eftuents to unrestncted arms sa kow cmu M guided by cer%a:n conaiderations in and concentrauon2 of radioacuve material as practicable if the applicant provid e res* estabtlahing and ernpiemenung operattng to emuental for Mght. water-mo)+d nuclear morable usurance that:                                                   procedures 1. hat take 1.nto scoount the need power reactors spec: Sed in paragraphs A and                     1. Por radianctive snatenal above bac k- for opersung Sesiburty wttue at the same B of thts section are authelently cortsertative ground in Dquad emuenta to be reloaaed to ume amure that the ucensee will erset his to provide reasonable s.asurance that. for unrestricted areas by all light.m-ster. cooled best e!! ort to key levels & redloactive ma.
most locations having enttronmental chara nuclear power reactors at a site. Lbe pro = terial in emuents as low as pracitonble. The acterlauca likelv to be corundered acceptable poned higher quant.tues ur concentrations guadance act fona below provides Incre spe.
by the Comfrussion for a nuc ear power re-                   will not result in ar.nuM exposures to the cite guadance to teensees in thns respect.
actor sate, resultant increases in radiation whole body or any organ of an Individual in                              In using the guides set forth in section arposures to individual members of the pub.                   excess of S milltreins;
* and                        IV.it is expectea that it abould genermIly lac hving at the alte bouncary, due to opera
* 2. Iror radioactive noble gases and tod1 Des be feasible to keep ave age annual releases tion of ught. water cooled nucjear power re-                  and radloacuve material in particulate form of radioactive material tn e!!!uents from actors at the site. 31u generally be less than above background in gammus emuenta to be ug ht-e ster-coo:ed nuc! ear power reactors 5 percent of exposures due to r.atursJ back- reieued to unrestricted areas by all 1.sht.                          within the levels set forth as numerkal ground radiation and average exposures to water.mcged nuclear poner reactors at a ette, guides fcr design oD}ectiver in acccon U sitesbie popuistion groups w1U generally be the propaaed hagber quanttues and conce.n= above At the atme time. the licensee is per.
less than 1 percent of exposures due to nat*                 trauons wt;l not result in annual exposures mitted the flealbtlity of operation. compatible
* utal background radlauon. Tne guides on to the wnole body or any organ of an andA- with considerations of besit.b and &&!ety, to design oD}ectives for light water. cooled vidual in excess of S In111trems.                                        assure that the public is provided a depend.
nuclear power reactors set forth in para
* D. Notw:thstanding the gTudance in pam. able source of power even under unusual graphs A and B of this sect on may be used graphs A. B. and C above, for a parucular site operating conditions which cnsy t.emporaruy by an appucant for a permit to construct tte Comrrissaaon may specify, as guidance on result in relenaes higber than such numerical a light-water. cooled nucJear power reactor design ob}ecures. Iower quantiues and con. rundes for design oc)eettes, but st!U within as guidance in meeung the requirements of centrattors of radioacu ve matenal above levels that masure that actstal expmures to                                            l l 50 34a ta) that applications filed af ter Jan"             bacsground tn et!!uents to be releasen to un. th4 pubtle are small tractions of natural                       l uary 2.1971, toenttfy the des 4n objectives, restricted areas if it appears that the une of background radlauon. It is espected that in and the means to be employed, for keepicg the destgn oejectives dancnbed tn those para. using tble operstional textbtuty under un-leveits of radioactive matenaJ in emuen a to grupbs as ukely to result in releases of total usual operaung conditions, the iteensee wiu unrestricted areas a.s low as prac" cable.                   quant,ities of radjonct re mater:a; inom a;1 exert bis best eff orts to keep levens of redlo.
A. For radioactive matensi abov bac h hght water-coolad nuclear power reactors at active materia) in emuents w".t'in the nu.
ground in liquid emuents to be released to the alte that are estimated to cause an an-                             merical guides for design objectives.
unrestricted areas by each hght wiuer-cooled nual exporure in exceas of S maturems to the                            Src. IV. Oukfer for limtring condif tons for nuclatt power reactor at a site:                              whole body or any organ of an individual in operation for Itp4 f-water. cooled n uclear
: 1. The estimated annual total quantity of the of! site environment froni radjonctin ma*                       power reactors. A. It rates of release of radno.
radioactive mater:aj. except trittum, should terini above background in either 11 quad or acttee matemala in ecuents from lacht.
not exceed 5 curies. and                                      ga eous e!!!uents                                    water. cooled nuclear power reactors actuauy
: 2. The astimated annual average concen*                     Src. UL Gufdes on fechnical spectftcartons espertenced, a verag ed over any oalendar trsAlon of radioactive matenti prior to datu* for limit mp condif tons for operation for quarter, are such that the eettmated annuaJ taon in a naturni body of water. except trit
* Jigh t.ro t te. cooled nuclear power reactor 8 quantitles or concentrations of radlonctive tum, abould not exceed 0 00002 macrucurse lacensed undee 20 Cf A Pors 50.The guides on materia.1 in eft uenta are likely to eseced (20 pimeuries) perliter: and                                lim!ung concisions for operauon for 11gnt. twice the design otr)ecun quanuues and
: 3. De estimated e.nnual averste concen* water.cooied nuclear power reactors act forth concentrations set forth in sectiot. U above, i.rsuon of trttlum p1or to dilution in a nat*                below may be used Dy an appiscant for a the licenre abould:
utal body of water abould not esce*d 0 005 Ucense to operate a ught-water. cooled nu*                                1. make an invesugadon to identify the interocurse (5.000 picoeuries) per 12ter                     clear power reactor sa guidance in develop
* causes for such release rates: and B. Por radio.idive material above back.                                       g               , g ggg                                    ,            g taJ uantit or                        e mate     to be   to kHP I"ela M radioactin matenals in to retace nch Nmae rates M the esign re%amed to ttnrestricted arma by 80 light,                                                                        im) : and water-cooled nuclear power reactors at a 51tg                                                                       3. report these actions to the Comm1 salon E                                          00 0
* abould not reau!L in:                                         epure of mmWS d W puMC SWd M                           g g pggag of pgjegge og raggonegget me.
: 1. An annug antage exposure rate due to esumted oro dismbuuona in 2e enMron. terial in 11guld or gaaeuus effluents actuaDy noble gaade at any lomtion on the boundary ment of radjon(*stu mtenal relmaed in ecu. espertenced, averted over any calendar of  the site   or  in  the excess of 10 culhferns; and o,ffsate     enetrontnent  in     e ntJ Phr estimates of estternaj esposure the quarter, are such that estimated annual rem rnay be conaldered equJe&ent to the rad; quantitles of concentrations of radioacute and account abould be tasen of the af pro. material in eSuenta are likely to esceed a
: 3. Annual aveange conceStrationA at any priate payancal parameters (energy of rad;a. range of 4 8 umes the design ob)ccute locauon on the bou.noarT of the site or in tnon, sbsorpuon coefhcients etc 1. Estamates quanutits and concentrations set forth in the c3&lte ene".ronment of ?tdloactive lodines. of in1ernal dose commitment, in terma Of section U above.8 the Commi.ston will take or rndloacuee mater %! In paruoulate form                    the common urut of done equlVOence trem) with a half life g* eater trAn 8 days, in es. anould be generaJ17 cona atent with t.be con ' lease                apg repra.ste rstes areaction to naaure reduced.          that50.36a(s)
(Sectton    suCh re.
cews of the concentr%tiorJ in aJ speo:!)ed in vent &ons or assumptions for ondcujational (21 requires the Licensee to submit certain Appendix B. TsDie U. Column 1. of 10 CTR purpmee most recently pubushed by the in. reports to the Commission with regstd to the Part 20. divided by 100.000.                                 ternauonal Comminanon on RadJotogical P'ro. quanuues of tbe princips! radionuclides C, Notutthstanding the guidance in para. taction whJch appa duec.4 to intaaen M reieased to unrestricted areas. It also pro.
g.spha A and B above. design object 19en, radioactive materlaj from air and smer and vides t. bat. on the baats of such reports and bemed on quanuties and concantrations of those appucable to water may be applJed t                                any additional information the Ctanmission radioscu te rintenaj above tackground in totakes from food. Tbm connnuona or na                                  may obtain from the Ucensee and othere.
sf uenta to be reJenned to unrectricted areas, sump o                       o   4                            to 1.be Commission may from time to time e    or      ur nronuum-60, stronuurn40. or radionucaldee require the Ucen.see to take sue.h actaon na s An esposure rate suCD :. hat a hTpothetical of iodine For thme radionuCMdM 2e blow. the Commlaston deems appropriate.)
individua4 mnunuoualy preaent .n the open onJ and physica2 aasumpuona of P7tC Report                               C. The guides for limiting conditions for at acy location on the boundary of the site No. 2 shcntJd be used. It is manu                                    opersuon deacribed in pararapts A and B e n :             S                ne       e e vt. o . ei na listed in Part of this section are appiteable to technical ur an n            er                               1 rems *nts neoccta the red ucuc tn t.he 20. Append:s 3, woje U would result .n espmures to a teal ind:ridual thsa would annual doses of 15 rems to the *.hyrod                           a         a       e rstes within (2 tis rarufe would be be aforded by the dia Aree trom he alta the concentration of stron*Jum. 9 e                                                               ann a e         te rata boundary at which the individuaJ !s located. Llum 90 would result .In anc                                                        o                a range M 30 exposure to the gor.aas   so       ems per year du26 mis quanery pr         f       e he in av d           :s no re     t s P'      -
a the area.
or red bone marrow.
1971 fgDikal REGl57tt, VOL 36. NO.111-wtDNf 5LnY. J int 9, i           m m - should read " D nillirens" l
l

M T 2/L2 X 9 %kaT                                                          K & r- M C M M atad:            T
    ;                                                                                                                                                        o.
I 1A-5 PROPOSED RULE MAK!NG specifications included in any lleense au.      Scations should be developed to carr7 out       ($*c.161,68 Stat. 049; 42 U.S C. 22ol) t .oriztcg operation of a light-waterwed the purposes of keeping levels of radioactive t,uclear power reactor constructed pursuant material in emuenta to unrestrteted areas             Dated at Washington. D C., this 4th       1 to a construction permit for which applica. as low as praotteable. In any event, all holders day of June 19'll.
tion was nled en or af ter January 2.1971.      of tacenses authortt.ing operation of a light
* For the Atomic Energy Commission, ror light water cooled nuclest power reactors water cooled nuclear power reactor abould, constructed pursuant to a constaiction per. after (36 months frorn erecttee date of this                              W. B. McCoot..
mit for 'th1ch appilcation was f. led prior to guide), develop technica. spectAcations in                  Secretary of the Commusion.
January 2.1971, appropriate technical spect. conformity with the guides of this Section.           (FR Doc.71-.8049 rited 6-4-71:8:51 sm)
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          ,. -                                           = - -- .-                              -                                    -              ._                            _           -.. -
PART 50 o DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES gTtpb B.1:
ta) no Commienton snay spectfy, as guld.
V
  'I                 , ture Tougbotes Requiremente?                           Aspassoca 1- NirweascaL Otrtors rea Dus24sr B. The a.djusted reference temperatures for             Oniscrrvas asta Lrnarruro Corrorrtoso rea             ance on design ob)ectleen. a lower quantity of the beae Instal. best.aSected none, and weld                OrsaaTion to Mast Tws Carrrazon                       radtonctive material above background to be metal aba!! be obtained from the test re-                 " As Lnw AA is Heasonablv Achsevable"* For              relenaed to the atmospbare !f It appears that g.g~
suits by addtag to the reference temperature               RaJioartne Material in LightMaler-Cooled Nu. the use of the design objectives m para.
the amount of the ternperature abitt in the                                                                       graph B 1 La titely to result in an estimated
                                                                                 ,3g, j ,mer Hearmt Ufluents Cberpy test curves between the unirradtated                                                                       annual esternal dose from gaseous edtuents M                         6W          to any ind Instertal and the treadiated matorted mena =
o,ed at the = foot. pound level , that pmad- 2= ma annitcaa= <- a p r=>t                          enre., o< .iftdual mmi, ems    in an tounmetric,ted me tota bod area  to
                                                                                                                                                                                         ,; ,nd t ct a nu          po    r                        (b) measured at the $6 mt! tatern! exponaton                                               g                                   Deatgn ieest, wbicoev., temp.,stu,o otfC is ,,ea          e,.                        a                                                 of objecuese
                                                                                                                                                              . oacti,e    based mm upon a b_ighero qua.n bee. , ut, rhe htgbest adiu.t.d ,ef m noe and the lowess upper.abelf energy level of
                                                                   .,erature  gen. ogea       j        ia=yt=gt,eg -      ta mund to b. reieased to the atmes,be,e than 2e quanuty spectbed i enaeous and 11aund edtuent.a preduced dur.                 w% deemed m meet tbs ,n pamgraptr     eqa,,menta B,o.1 ,
m the beium. matence oui be ua.d to                                                                d                                                                          -
vMtfy that the fractu,e touone. requi,o.
inerda of section v.B. of Appendia O are
                                                                              ;ng,=;r=s gg grgg,.=ge=4;e-r e.,mg ievels of ,ndioscu,e meta,tu m gamus effluents as low as is reasonbly achiev.
of an applicauon Sled on w after January 2.                able* if the applicant provides reasonable as.
                        **                                                     1p71, the appilcauon must also Identify the               surance that the proposed higher quantity will
: 27. Espost or Tser asetrtTs                  design objectives, and the moana so be em.
ptoyed, for kwptog levola of radioactlye                   not result in an estimated annual e sternal dose N A. Each capsule withdrawal and the resulta                materialin effluents to untestricted areas as low g from gaseous effluents to any indevidual m un.
                   @ of the fracture toughness tasta aball be the              as is reasonably acheevable.'                        w restricted areas m excess of 5 mittarems to the
        '          U subject of a summary technical report to be                    section 60J6s contatna provisions de. $ total body or 15 milhrems to the skin.
z provided to the Director of Nuclear Reacto,               algud to masure that relenaea of radioactive g C. The omiculated annual total quantity u Regulation U.S. Nuclear Regulatory Commis,                insterial fmm nuctest p w*r M*ct m to u== m of m!! radiomettve todine and radiometive ma-g sion, Washington, D.C. 205 5 5.t The repor                mtricud maa u               n          a         a o                n paruculate fortn above bacAground shall                                                  tions incJuding expected operstiond occur-include a schematic diagram of the capsule locationa in the reactor seemet, identtacatson.       ""("'       '" "P' ** * * '' '' "'' "O "* **} to be atmosphere Breleased uCAN pown from Mactu in   eneb    itsbttoweter-cooled edluente viu not result in an eettmated the of specimens withdrawn, the test resuita, and               Thi8 Appendiz prortdes numerical guides for design objectives and limJt.tng concluona              annual done or does commstment from such the rotationanto of the measured results to            for opernuon to aantal applicants for, and                 radioactive lodine and radionctsvo snaurtal those predteted for the reactor vessel belt,.          holders of, licensee for light. water. cooled              La particulate form for any indtrndual in an une reston.                                            nuclear power reactors in meettog the r,.                  unrestrteted area from M1 pataways af ex.
B. The report shalt stao include the dostm,         qujnments of $ $ 80 34a and 60.36a that                   pueure tn esceen of 18 Inultrema to any organ.
etry measurements perfo*med at each spect,             radtoncuve mateMal in eheda w ased                             E In addhn M 2e proMatone of para.
men withdrawal, analyses of the reeutta                                                                           Fmpba A. E and C abwe the appilcant which yield the calculated neutron fluence            from tune facmuse to unne ewd anna be                      aball include to the redweste system gj which the reactor vessel bettJLne region haa kept as low as is reasonatsly achsevable." Design itema of roamonably demonstrated technot.
objectives and limitsng conditions for operation recetted at the time of the testa, and corn. E conformsng to the guedelines of this Appends:                     ogy that, when added to the system sequen.
tially and in order of dimtntahtng cta t.
partoons of fluence.with the ortgtnally predteted values 'n cshall be deemed a conclusive showing of compli.                    e            n            o a few e c .
C. The operating pressure and temperstm } ance with the "as low as is reasonably achiev.                                ]t f 11mitations estabitaned for the perwa of , able"* requirements of 10 CFR $0.3aa and                              population reasonably espected to be with.
operation of the reactor vessel between any ei $0.36a. Design objectnet and limiting condi.                       Ln 60 m11ee af the reactor. As an interim
;                        two surve111ance specitnen withdrawala aball w lions for operation differir.g from the guide.                     measure and until estabitabment and adop.
be spec 1 Sed in the report. including ant             hnes may also be used, subject to a case-by. case          tion cf better values (or other appropriata
              -          changse made in operational procedures to              showing of a sufficient basis for the findings of          crtterna), the valuse 81000 per totar body assure meeting such temperature limitations.           .*H tow as is reasonably schtenable"* required             man-tem and 41100 per manathyruid. rem (or L.{                                                                     by % % $0.34a and $0.36a. The guides presented             such launer estues as anay be demonstrated T.:" -
D                                                                    in this Appenden are appropriate only for tight.           to be suitable in a particular case) eball be water. cooled nuclear power reactors and not for           used in ibia cost.beneSt analysia.
osher types of nuclear facilitiet                      ]
Bsc. IL Guid4s on design obtecftpes for           '
The rwquirementa at tbla 'pe.rmgragsb I) light.wefer. cooled nuclear poioer reactors 14             need not be cornpfted vttb by persons who eenard 46nder N CFA rart 30. *ne gWdes on                  have Aled apptteuttona for testruction per.
mfts whneh were deckweed on or after Jane damirn t    ob)ecttees est forth in this esctaan to mary 2. W71 and preer so. June 4. Irre. If the snay be used bF an applicant for a permit $ reewmane syneums and equipment deserthed to construct a light-water. cooled nuclear 4r in tAus prettrntowy or Anal estety analyu1 re.
power reactor sa rushw in Inseting the C Port ud e%te hto my >
requirements of 9 60Seata). Tbo applicant b Ouidae on Damaga Ob)setream for Lasht.hter.
aball provide reasonable assurance sbat the owOooled NucJear Power Benetore proposed in following doetgn objecstree wtu be met.                    the Concludtng f9tatement of Position of the A. The enlet.inted annual total quantity of            Regulatory Stag in Doctet4DE-84-2 dated all radioact1re anatartal above background ,
'                                                                                 to be released from each light-water. cooled                                                  -
nuclear power reactor to univstricted arina             .
will not result in an estimated annual dose                  Bac. IIL 1mplementation. A.I. Conform.
or does commitment from lifluid emuesta                   tty with tbo guideo on destgu objectives of for any individual in an unrestricted tres from all pathways of exposure in sueous of                Beetion 11 shall be demonstrated by calcu.
j 3 multrema to the total body or 10 miutrema               lational procedures based upon models and to any organ.                                            data such that the actus! exposure of an B.I. The calculated annual total quantity             indsvidual through approprtate pathways na of all radioactive maternal above bac.tground            un11 Rely to be substantially underestirnated, to be released from each ught-rater cooled               all uncertalottes being canandered trwether nuclear power reactor to the atmcopbers will             Account shall be taken of the cumuisttee not result in an eettmated annual sie doe
* Q ef'ect of all sources and pathways within the from gaaeous emuenta at any toestion near .e plant contributtng to the particular type of ground level which could be occupted by in* C ef?.uent bemg considered. For determina.
dividuals in unrestrteted arena in ereses of             tion of design o6jectives in accordance with 10 milltrada for gamma radiation or 20 mull- [ the guides of Section IL the enttmation of rada f or beta radiation.                                 e rposure aball be mada with respect to i
2 Protwithstanding the guidance of para. =er           auch potentist land and u.ater unage and food patbu sys na cou.16 metually entst dur.
l i ytere and eise wh er, in tbts Appendin              ing the term of plant operauen: crovided, background means redloacttte matertala in                That, if the requirements of paragrapb B of section fit are fulfitied. the appucant sban c ,_                                                                  the enmenment and in the eeuents from                    de deemed to base compiied with the re.
        .==                                                                        ugbt. water.cooied power reactors not gen.
ersted in, or attributable to, the reactors of            quiretnents of pararraph c of mction II
            '1'...                                                                                                                          with respect to radioactive todine tf esti-
                =r                                                                 whica spectee secount ta required in deter, minteg design objectives,                                mattons or exposure are made on the basis j Amended al FR 10445.
* Amended 40 l'R 5 8841 50 37
* h 1978 ATTACHMENT 2

PART 50 o DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
                                                                                                                     ~
of such food pathwayn and Individual neep-                such that the resultine radiation esposura.              CorsetvDLNG STATEMENT oF Pourrsow or Tus tors as actually esist at the time th plant               es,1culated on the sarne basis as the respec-                  Racm.aMa 7 6Tarr (Doc sT-RM M 2) is !! censed.                                             tive design objective esrtosure. would esceed            cas op pasm onim p ucwT waTra.
: 2. The charse.;rtstles attributed to a hg-           one-halt the design colecttwe' annual es,                            cootzn umus ma stacmae posure derived pursuant to Sections if and                                                                              ,,.
pothetical receptor for the purpose of esti-                                                                           A. ybt radioactive matertal above bac k - 'm mating internal done commitment shall take                !!!. the licensee sha!!:
* into account reasonable devtsttoms of indl-
: 1. Mase an intest!grition to :det'Irv th<           ground
* in liquto eftuenta to be releseed to vidust habits from the average. The app 18-               ew-e* for auen releve rates.                             untentr1cted areas:              .
2 Denne and tuntiate a pMgrain of ros -                  1. The esaculated annual total quantity of cant may tAke account of any real phenom.                                                                          au radioactive mat.crial from all light-water-enon or f actors actually affecting the esti-             rective acticn and J. Heport these utions to the appropriate           cooled nuclear power reactors at a alte should mate of radiation esposure, including the characteristics of the plant, modes of dis-                NRC Regional Office shown in Appenois O                 not reeult in an annual dons or dme enmmit-of Part 20 of th.s chapter. mth a copy to the           ment to the total body or to any organ of an ebstge of radioactive materials. physics, proc-asses tending to attenunte the quantity of                 Director of Inspection and Enforcement. U.S.            Indtndust in an unreetricted ares from all Nuclear Regulatory Commissmn. Washington.               pathways of erposure in escoes of 6 mil-radioactive matertal to which an individual                                                                       tirems: and would be exposed, and the e$ects of av'''                 O.C. 20555.t                                                 2. The calculated annual total quantJty of g.gtng erposures over times duttng m*hich de*             altbtn 30 cars from the end of the quarter termining factors may Suctuate.                           during thich the release occurred.                      radioactive material, except trtt.tum and dls-B. The licensee shall establieb an approprt-        solved gaaea, abould not ascoed 6 curnes for B. If the appitcant. determtnes design oh*                                                                   each light-water-cooled reactor at a alta.
jectives with reepeet to rad!onctive todtne               ate surteillance and monitoring program to:
on the basis of existing conditions and if                     1. Provide data on quantitles of radioec.               3 Notetthstanding the guidance in pars-tive material reiessed in inqund and gaseous             graph Aa. for a particular site, if an appll=
pptantial ebanges in land and water usage                 emuents to sasure that the provisiont of par-            cent for a permit to construct a light water-and food pathways could result ut erposures                                                                        ec.oled nuclear power reactor has proposed in excess of the guideltne values of pars
* sgraph A of this section are Eneti basettne in-plant control measuroe s to reduce graph C of Section IL the applicant shall                      2. Provide data on measurthe levels of rs*          the poastbte sources of radnoactive maternal provide estonable nasurance that a mont-                  distion and radioactive materials in the en-toring a nd surveillance program will be per-             vironment to evaluate the relationabtp be-               in liquid ofBuent releases and the calculated formed to determine:                                      tween quantitles of radioactive material re*             qua.ncty eseeeds the quantity set forth in 3 The quantities of radioactive todine               leased in st!!uents and resultant rad;stion              paragraph Al the requirementa for design actuaUy released to the atmosphere and                   doses to individuals from principal pathrats             objecutes for radinactive material in 11guld deposited relative to those estimated in the              of exposure; and                                         efiluents may be deemed to have been rnet determination of design objectives'                            3. Identify changes in the une of unre*             provided :
2 Whether changes in land and u tter stricted areas te g.. for agricultural purposesi               s. the applicant submits an evaluation of usage and food pathways which would result , to permit modtScations in monitoring pro
* e the potentla! for e!'ects from long-term in individual exposures greater than orig M grarns for evaluating doens to individuais - betidup in the enetronment in the vicinity of anally estimated have occurred; and                    $ from principal pathways of exposure.                  $ the site of radioactive material, with a radio-3 'lte content of radioactive lodine and
* C. If the data developed in the surves!!ance '' active half 1tfe greater than one year, to be foods involved in the chanees. if and when C and monitoring program described in pars- C"roomaed; and g graph B of this section and in paragraph B of                  b. the prortstons of paragraph A.! are met.
ther occur.                                                                                                              B. For radioacttre material above bac k-Sec. IV. Gamfes on technscas speculcationt w Section III or from other monitoring pro * @
for limsftsp condt f tons for opera tio*: for             grams show that the relationsetp between                  tround in gaseous eSuents the annual total itef-scater-cooled nuclear potter tractors h-              the quantitles of radionettre Instertal re*              quitnttry of radioacttre matertal to be re-leased in itquid and gaseous ecuents and the             tenace to the strnoepbere by all light water-
, censed under 20 Crit Part 50. The guides ota                  done to individuals in unrestricted areas La             cooled nuclear power reacton at a site:
m limiting conditions for operatton for light-
$ water-cooled nuclear power reactors set forth                 sign 10cantly dif'erent from that assumed in                  1. TDe calculated annual air does due to
- besow may be used by an applicant for a 11-                   the calculations used to determine destFn                 g-ma radiatkm at any location near ground W:
C cense to operate a light water cooled n u*                    objectives purauant to Sections II and III.               leven which could be occupsed by indtrtduals.2 cz.
the Commleton may tnodtfy the qur ntitles at of beyond the boundary of the site should."._.
g clear power reactor as guidance in developing                                                                           not exceed 10 Int 11trads; and                              %3..
.e technical specincations under l SO.36a(s) to                   n the techclea; specMcations decntng the                    2, The calculated annual att dose Oue to Ireep levels of radioactive insterials in effu*            lintiting  conditions for operation in a 11cacse ents to unrestricted stess as low as es reawnably                                                                   beta     radiation at any location    near ground sutbortr.ing operation of a light s ster cooled          level which could be occupied by indletduals a s hie rs hle.
* at or beyond the boundary of the site should Seetton 60.36 stb) provides that incensees            nuclear power reactor-shall be guided by certain considerations in                   Src. V. Efsefke daicJ. A. The guidea !vr             not escoed 20 tut 31rsas.
establishing and implementing operating                                                                                  8. Notwithstandir.g the guldance in parsa 1 mating conditions for operatten set forth in            graphs B.1 and D1 for a particular site:
procedures spectfied in technical spectSen'                th*s Appent!1x shall be applicable in any case                              ,
tions that take into account the need for operating flertb111ty and at the sar se tttne as-          t,n which an application was Blad on or af ter
                                                                 .anuary 2,1971, for a permit to construct a sure tbat the licensee will exert his best                 ught-water-cooled nuclear power reactor.
e!' ort to keep levels of radteactive maternal                             c
* nuC sn ef fluents 35 low RS is re3Sonst'ly GChievat'le.e                                                                6tZhosphere tf it appeart that the use of the The guidance set forth below provides sddition-                                                                     destan cofwettree stascrthed in paragraphs B 3 al and more specific guidance to hcensees an
                                                               .mit for which appitention was aled prior to                and 8.2 ta titely to reeult.in an stanual dose January 2.1971, the holder of the permit or                to AS Indirldual in an unrestricted area in es-thiS teSpeCI-                                             a license authorizing operation og the re-Througn the use of the guides set forth in            actor shall, within a per)od of twelve months this Section it is expected that the annus                                             m        o ml u raleanes of radioactive material in eniuents Um                   5           t go             b. Design objectiven based bn a hifber l
from !!gnt-water cooled nuclear power re-                      -
evaluate     the mesna ernployed for keeping              m antin of radioacWe matenal above back-                         ,
actors can generally be maintained within                 le . e;s      radioac tytty in e uents to un.                                                                              l the levels set forth as numerical guides for design objectlees in Secticn II.                                                                                    fled 2n paragspha B.1 and B 1 may be tieemed
                                                                        -* mc     egdsM -Jorrnshon as e re.                 to tnemt the requirernetria for keeping berets At the same time. the licensee is permitted           gered by e3 40 Jd a (b) .ind (c) not stread y cun-the fientblitty of operation. compatible with             tained in his application: and considerstkons of health and safety, to assure               2, Plans and proposed technical tpectnca-that the pubtle is provided a dependable                  tions developed for the purpose of teeping                    ,,              ,
source of power even under unusual operat,                re;enses cf radioactive matertals to unre.                                                                        ,
ing conatttons which may ternporarily re.                 strteted areas during riormal reactor opera.
suit tu retesses blgner than suen numerical                tions, incitrettng expected operational                                            ,
guides for des;gn objectives but sttil atthin levels that assure that the average popuis.            gyrrernet a low s. as renonar y actueva .                        ,
: l. tions tion exposure       is equivAent   to small friec-                                                                    clear liquid waete streamn (nortnally trit!-
of dosen from  naturaJ tackground     radt-        % min % may C)1 require tr,e hcensee in                   sted, nonse sted, low conduet*vfty eqt:1p-3 atton. It !n expected that in using this opera-               suDmit certain reports to the Commission                  ment dratna a M pump epal lessoff), mrty
         ' 1on a l f1*xtD1tity uncer unusual operating             with recard to the quantitles of '.he principal           up waete s'trviams uriv tna. fly nontrtttaM
        . onditions, the licensee will exert his best             radionSc!) des releaned to unrestricted areas.            aerated. high conduettety tru0 ding wurnpa, e Iforts to neep levels of radtoactive matertal           It also providea that. on the basis of such                tioor and samNo wtation drairns t, steam gen.
in e!!!uents within the numerical guides for              reports and any additional information the               arator blowoown streams, cherr.1 cal waste ten onfectives.                                            Cornmission may oDtain from' the 11censee                 streacs. low purity and h4b purtty liquid ["~
t !! the quant:ty of radioactive material             and otbers, the Commtmaton may from time                  streams (twin regenerate and latwirator' "
art alv eleased in efmients to unrestricted               to time quire the Iteensee to take such sc-               wastest, as apptcpr;ste for the type of reac ~~
areas from a light-water-cooled nuclear pow-               tion as the Commission deems appropriate.                 goy'                                                         _
er &cneter during any calendar quarter La                  + Amended di 6 R 1 ridd 5.
         ' Amended 40 F R $ hkd'.                                  ; Amended C I H 2013 %
September 1,1976                                                                50-38 l
l

PART 50 o DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES low as is riasonsbly echisvsble* 6f ths applicant --                         AppssstrE J                            !!tted with Sixtbt) metal seal assemblies.
: 2. Air lock Coor seala. goctuding Coor operst.
prnvides reasonable assursace that ilm proposed       ,         ,,g         , em        ,         ,gg ing mechanism penettstions which are part higher quantity will not result in annual doses                        m                     a                      of the containment pressure boundary.
to an individualin sn unrestricted stes in escess                                                                       S. Doors with resunent eeCs or gasketa es.
of 8 millirems to the total body or 15 milbrems            ! Introduction.                                         . cept for neml. welded doors.
II. Erplanation of terms.
       .....en mi       to the skin.                                                 111. Lenkage test requtrements.                              4. Componenta other than those listed in "I=."
                            . C. Por re-stve todtne and rmetancttve                  A. 7Tpe A test.                                        ,11.0.1,11.0.2. or ILO.3 o htch must meet the amatartal &n paresculate forta shoes pack.                 B. Type B test.                                          acceptance critetta in III.B.S.                     l ground released te the stanaaphare:                        C. Type C test.                                              IL *"Pype C Testa" means tests intended to
: 1. The amiculated annual tota,1 quaMity og                                                                     measure containment isolation votes testage D. Periodle retest schedule.
ett ruanoactrve lodine and radioactive mm.                IV. Special test requirements.                           rates. The contatnment taotation valves in.
                         .tertal in persnoulate Form from at! Itsht.                 A. Containment mad 1Bestions.                            cluded are thue that:
water cooled troclear power reactore at 6 alts,           B. Multtple leakage-barrier containmenta.                    1. Frovide a direct connection between the steuld cat tueust in an annual emee or done               V. Inspection and reporting of teste.                    tnside and outande atmospheres cf the prl.
mesmatasent.se may organ of am 1sadtvidual                A. Containment inspection.                               mary reactor containment under normal op.
                           ,tanea unressrtoemd atom frase sti patMrmys of            B. Report of test resulta.                               erstion, such as purgo and ventilation, asposure An esoess of 15 mailtrams. In deter.                                                                      vacuum rellet. and instrument valves:
mining the done or does commitment the                                    E IM*080CT3"                                 2. Are required to close automatically upon    l port 6on thereof due to intake of radion.ctive                                                                     receipt of a containment toolation signal to       I loatertAl via 'itse foud 1mthauppe may be                 One of the conditions of all operating                    response to controls intended to efect con.
                                                                                 !! censes for water. cooled power reactors as
                     $ eeshsahud at the locanone wisere the food                 specified in f 50.54(o) le that primary re.                   tainment taotstnon:
g pathouys notammy estatt and                                                                                                 3. Are required to operate intermittently w ' 2. Tise calculated manual total stuantity              actor containments sht!1 meet the contain.                    under postaccioent condit&ons: and                 {
g of amurm!si in gaaeous efDuents abould not                ment teskage test requiregnenta est forth                         4. Are in main steam and feedwater piping w hand 1 curle for each 11ght-watar. cooled                 in tbts append!x. These test requirementa                                                                        l provide for preoperational and periodic varia                 and other systems which penettste contain.
c nuclear power reactor at 6 site.                           SC&tton by testa of the 1stk+ Light integrity                ment of direct. cycle bolllDg water power
                      "         3. NotF1tNtAnding the guldaDee in p&rs.
of the primary reactor contatament, and sys.                   reactore.                                         l grapbs C.1 and C.2 for a partneular slee, if an      tems and komponents ubich penetrate con *                        !. Ps (p.s.l.g.) means the calculated peak spplianct for a permit to conetruct a light.          taintment of water. cooled power reactors.                   containment internaJ pressure reisted to the I
innser.csolad nualmar power reactor bas pro.          and establish the acceptance criterna for                     design basta accident and spec 1 Bed either in
                                                                                                                                                                                                  )
                            .poemd besett e en. plant armtrol measures t to       such tests. The purposes of the testa tre to                 the technical spec 1Rcation or associated baaes.
eedson the possible sources af radiosettre           assure that (a) leakage through the pri.
3rdne releases, and the calculated Enttual                                                                             J. Pt (P s.18.) means the containment quant''tlee t4Dng into account such control          mary reactor containment stad systems and                     vessel reduced test pressure eclected to mesa.
mear;rsa e'sceed the design objective quan.          components penetrating primary contain.                       ute the Integrated leakage rate during pe.
titles art torth in paragraphs C.1 and C 2,          ment shall not exceed allowable leakage rate                  ,ggg 77p, g g,g the requirernents for doekru oc) octaves for          values as spectied in the technical spect.                       K. La (percent /24 hours) means the mast.
fications or masociated bases and (b) periodic               mum allowable leakage rate at pressure Pa radlametive lodtne and ratriosatt+e matenal la particulate form Jn gaseous etBuents may           surveillance of reactor containment pene.                    as specified for preoperational tests in the be deemed to have been toet proftded the              tratione and teolation valves is performed                   technical specifientions or masociated bases' calculated annual tots! quantity of all rs.           so that proper maintenance and repairs are                   and as speci6ed for periodic testa in the op.
dioactive lodine and radioactive tnaternal in         made during the service life of the contain.                 ersting lice nar, mant, and systems and components pene.                           L. IA1 (percent /24 hours) means the de.
particulate form that may be retenaed in gaseous efDuents doch not ertmed four times $ trating primary containme nt. D ene test h                       w ign s     leakage rate 64 pressure, Ps. as spectaed the quantity calmtlated pwenant to part. Q requirements may also be used for guidance in estabitshing appropriate containment g in the technical spectncations or associated g
0: P =." graph C.)                                                  g leakage test requirements in techntest spect. w bases,
            .........e, y $ cations or asaociated bases for other types g M. Lt (percent /24 hours) means the matt.
u;fifM                                                                                                                                mum allowable testage rate at pressure Pt m of nuclear power reactors.
             %F                                                                                                                                  derived from the preoperatio%st test data II. EzrLaMATioM or Trasas                       as spec 10en in IILA 4.(a)(111).
A. " Primary reactor containment" means                      N. Lam, Ltm (percent /24 hours) means the structure or vessel that encloses the com*               the total measured contalnment leskage rates ponents of the reactor coolant pressure                      at pressure Pa and Pt, respectively, obtained bouncary, ma deAned in i 603(v), and servea                  from testing the containment with compo.
as an essentially leak. tight barrier against the            nents and systema in the state as close as uncontrolled relemae of radioacttuty to the                  practical to that which s'ould entst under environment.                                                design basis accident conditions (e g., vented.
B. " Containment isolation valve" means                 orstned. flooded or pressurtted).
any valve which is retted upon to perform a                     O. " Acceptance criterna" means the stand.
containment isolation function.                              ard agalnat which test results are to be C. " Reactor contatnment leakage test pro-               compared for estabitshing the functional sc.
gram" includes the performa.nce of Type A.                   ceptabt11ty of the contannment ma a leakage Type B, and Type C tests, described in II.F.                 11miting boundary, ILO. and ILE, respectively.                                        IIL Ltaicacs Tts7tNG Rroviathstwrs D. " Leakage rate" for test purposes is that lestage which occurs in a unit of time, etsted                   A program constating of a schedule for ron.
as a percentage of weight of the ortgtnal con
* ducting Type A B. and C tests shall be de.
tent of containment str at the leasage rate                 veloped for leak testing the primary reactor test pressure that escapes to the outside                    containment and related systems and compo.
stmosphere duftng a 24.hout test period.                    nents penetrating primary contatnment pres.
E. "Overall integrated leskare rate" means              surt boundary.
I                                                                                     that lestage este which obtair6s from a sum.                   Upon completion of construction of the f                                                                                      snation of leakage through all potentla! leak.             primary retctor containment, including in.
age paths including containment welds,                      stallation of all portlens of mechanical, nuto vaJves. attings, and components thach pene.                 electrical, and instrumentation systems peneE I'*",,'.."*"I"*'"I                                         trating the primary reactor containment P. Tpe A TestaN . means tests intended 'to           pressure boundary, and prnor to any reactor measure the primary reactor containment                    operating period, preoperational and periodic overall integrated leakage rate (1) af ter the             kakm        rm m u @m M M g containment has been completed and ts ready                ,,        gg g ,,
for operation. and t2) at periodic Intervals                   A. Type A test-1. Prctest reou wemen ts.
b Nas h m plant omtrol meeures rnay mtlude           thereaf ter.                                                (a) Containment 1:apection in accordance tensment i.f ste.em yeneratnr blow.duw n tank             O. " Type B Tests" meanA testa intended to              with V,A. sha!! be performed as a preregulatte detect local leau and to rnessure leakag, nhmt, sican steam suppleen for turbme gland             across each pressure.containing or leakage.
to the performance of Type A 4ests. During wak 6nndenser vacuum systems. contamment                                                                          the period between the Anat10 tion of the con.
limiting boundary for the following primary                tainment inspection and the performance of 17.,          purgmg enhaust and wentdatem exhaust systems            reactor containment penetrations:
and vecisi dnign features to reduse contami.               1. Contatrunent penetrations wncee design              the Type A test. no repairs or stijustments 5!.;                                                                                                                               shall be made so that the cents;nment can
_., .,ge          naird steam and liquid teAge from salves and            incorporates resilient sea 2s. gaskets, or sen: ant nther securtes such as bumps and tanks, at at"          componds p1pmg peDetrations $tted WMh e2                   be tested in as close to the "aa s" cond!!!on
               -;naa p&nalon bellows, and electrical penetrattors               as practical. During the pertad betsten the g                               !"Qrtate for the t) pe nf reactor,
                                 - Amended 40 > R 5RR47.
{
September 1,1978 50 39 t

PART 50 o DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES comp!stion of one Type A test and the init14           init111 test shall normatly be used for tha                       (b) Measurement of the rate of pressure tnon of~ the containment inspection for the           periodic tests.                                              loss of the test chausber of the routainment subsequent Type A test repatra or adjust *                 (bl The accuracy of any Type A test shall                penetration pressurtmed with Mr. autrngen.
or pneumatic fluio spectaed in the technical ments tha!! be made to components whose               be vertSed by a supplemental test. An accept.
leakage exceeds that spectaed in the technical        able method to described in AppendLa C of                    epectnestions or associated bases,                      gi specthention as soon as practical af ter iden*         ANSI F45 4-1972. The s upplemental test                           (c) leasage survettlance by means of a tlacation. If during a Type A test including          .nethod selected shall be conducted for suJ5                  perrnanently installed system with provisions . 3.:
the supplemental test spec 1!!ed in CLA.3.(b),         cient duration to establish accurately the                   for continuous or intermittent pressurization potenttauy esceutve leakage paths are iden*           change in leakage rate between the Type A .                  of individual or groups of containtnent pene.
tined which w!!! Interfere with satisfactory          and su pplernental taa t. Resulte from this                   trations and snessurement of rate of pres.
completion of the test. or ahich result in the        supplemental test are accepsable provided                    sure loss of air, nitrogen, or pneumatic f!usd Type A test not meeting the acceptance cr1*            the d1tierence between the supplemental test                 speeded in the technical specification or terta IU A 4 (bl or !!!.A.6.tb), the Type A test     data a.nd the Type A test data is within 025                  associated basces through the leak paths.
aball be terminated and the leakage through           1.a (or 0.25 I t). If resulta are not withtn 0.26                 2. Test Pressure. All preopera tional and such paths shall be measured ustng local              La (or 025 Lt), the reason shall be deter.                    periodle Typo B tests shall be performed by leasage testing metbevis, Repairs and or             rni:.ed, corrective action taken, and a suc.                  Irr.at pneumatic pressurtsation of the cou.
adjustments to equipment shall be made and            cessful supplemental test performed.                          tainment penetrations. either inditsdually c
          & Type A test performed. The corrective sc.               (c) Teet testage rates shall be calculated                in 370ups, at a pressuM not less than Pa.
tion taken and the change in lestage rata             using absolute values corrected for instru.                       3. Acceptance crit, u        (See also Type  g:
determined from the tests and overall inte*           ment error,                                                   tes ts.) (a) The combDod .akage rate nf a'l grated leakage determined from the localleak              4. Preoperational leskope .of t tests. (a)               penetrations and valves sutus to Type 3 and Type A testa shall be included in the                                                                           aM C Wu sM h % Man M La. wit',
Test pressureH1) Jtsduced presskre tests.
report submitt.ed to the Comnusalon e.s spe.           (l) An initial test shall be performed at a                  the e sception of the valves apet Sed u n ees Wn W Pa W masure                                                2nessurements (b) C1      e of containtnent isolation valves                                                                        b) leakage                           obtained for the Type A test shall be accompitsbed by             (11) A escend test aball be performed at                 through component bestage survet!!ance sys.
normal operation and without any prelimi.                                                                          tems (e.g., continuous pressurization of in.
pre         Pa to measure a leakage rate Lam, cary esercising or adjustments (e g . Do                                                                          dividual containment components) that tightentng of valve af ter closure by vaJve              ( 111) The leakage characteristics yleided               maintatus a pressure not less than Pa at in.
motor) Repairs of maloperating or testing by measurements Ltm and Larn shall re*abe                    dividust test chambers of contatnment ene.
                                                                .tsh the mastmum allowable test lea sage                     trations d uring normal reactor o rat valves shall be made as necessary. Informa.                                                                                                                          n.
tion on any valve ennsure malfunction or             rate L5 af not more than La (Lttn/ Lam). In                  are sgm m M M % B                             -
the event Ltm/ lam is greater than 0.7. Lt valve leakage that requirea corrective action        shall be spect$ed as equal to M A par                                    P before the test, shall be incluced in the re.
(2) Peak presure rests. A test tha!! be per.                  g. ,. c,t method. Type C tests shall be per.
port submitted to the Comrniaston as spect.                                                                       gormed by local pressurization. The pressure ned in V B*                                           formeat at pressure Pa to measure the lentage               shall be applied in the same direction as re g, gam.
in       (c) The containment test conditions shajg                                                                     tnat when the value would be te alred
      $ stabilize for a period of suout e hours prior               (b) Acceptance        (*rt f eno-( t ) Jted uced         perform its safety function, unJean it 1r to the Clart of a leakage rate test.                    pressure tests. The lestage rate Ltm shall be               be determined that the results from the test C        (d) Those portions of the f1uld systema           less than 0 75 Lt.                                          for a preuure applied in a dtMerent direction
      ' that are part of the reactor coolant pressure               (2) Peak pressure tests. The leakage rate                will provide equntaient or more conservative
      $ boundary and are cpen directly so the con.              Lam shall be less than 0 75 La and not greater               results. The test methods in MLB.1 may be g than Ld.                                                     SuMtituted where appropriate. Each valve to tainment atmosp here under post. accident :o renditions and become an extension of the Q sare.        5. Penodic leakage rate tests-la) Test pres
* g be tested shall be closed by normal opera.
bour:dary of the containment shall be opened g                (1) Red uced pressure testa shall be             u. tion and without any preltminary esercismg                   -
or vented to the containtnent atmosphere u conducted at Pt.;                                                   to or adjustments le g . to tightening of vnit e prior to and during the test. Portions of cc             (2) Peak preuure tests shall be conducted e' arter closure by valve motor).
caomed systema inalde containment that pene. " at Pa.                                                                  2. Test pressure. (a) Valves, unless Pres. --UUE trate containment and rupture as a result of             ID) Acce pta nce crtfrria- t t )          Ard ucctf -                            u      g. a     n tr e a loss of coolant accident shall be vented to       pressure tests. The leakage rale LLm shall be                     g                g, the containment strnosphere. Alt vented sys.       ,less than 0 75 Lt. If locat leakage measure.
rnents are taken to effect repatra tu order to anr r nWu at a masure M Pa.
tems shall be drained of water or other fluncts.                                                                       (b) Valves. Which are scaled with Suid to the estent necessary to assure esposure of       meet the acceptance criteria, these measure.
fr m a seal system shall be pressurtt.ed with the system esatstnment 1 solation ealves to         ments     aballpresure be taken  atThe a test pressure,Pt.             that fluid to a pressure Dot less than 1.10 Pa.
containment mL1 test preuure and to assure              (2) Pese           tests.      leaksse    rate lam shall be less than 0.75 La. If local lesa.                    3 A cceptonn enin n The combined they witt be subjected to the post. accident                                                                       le he rate for all penetrations and valves d tf!erential pressure. Systems that are re.        age rnessurements are taken to effect repairs
                                                                                                                              " Cert to Type B and C tests shall be teu quired to maintain the plant in a safe con.!        in order to meet the acceptance criterna.
than 0 60 La. Leakage from containme nt dition during the test shall be operable in         these measurements shall be taken at a test pressurf Pa.                                                   inlation estves that are scaled with fluid their normal mode, and need act De vented,                                                                        Irem a seal system may be escluded ahen Systems that are normally f!!!ed with water             6. Additional Requirements. (a) If any periodic Type A test f alls to meet the appl 1                h t ermining the combined leakage rate:
and opera ting under post.secident cond1                                                                                 rided. Tha t; tions. such as the containment heat removal         cable seceptance criteria in IU.A.5 (bl. the test schedule applicable to subsequ'ent Type                       ist Such enJves have been demonstrated system need not be vented. However. the                                                                           m ha*e nuld leakare rates that do not es.
containment isolation valves in the systems         A tests will be rev6ewed and approved by tue Comsruaalon.                                                  ctec those specined in the techntest spect.
de fined in L!!.A.1.t d ) aball be tested in ac.                                                                  f.rattens or assocasted bases. and cordance with III.C. The measured lesange               (b) If two consecutive periodle Type A rate from these tests shall be reported to the      tests f ati to tneet the applicable acceptance                    ibe The ina tstled tsala tion valve se al.
criteria in III.A 5(b), ne twithstanding the                  Fater srslem fluid tnventoey L3 gufheteng to Commission.                                                                                                       a'wre tne seating function for at least 30 L Conduct of tests. Preoperational leakage       periodic retest schedule of III.D.. a Type A dws at a pres ure of 1.10 Pa.
rate tests at ettber reduced or at peak pres.       test shall be performed at each plant shut.
sure, shall be conducted at the intervMs            down for refueling or approximate 4y every                        D. Periodic retts! scied ole-1.         Type A spec 16ed in III.D.                                 18 months. whichever occurs first uutti too                   test tal After the preoperational leakage
: 3. Test method.s. (a) All Type A tests shall     consecutive T@e A tests meet the acceptance                   rate tetts, a set of three Type A tests ar a!! be t         be conducted in accordance with the provt.          criteria in III.A S(b). mfter wh!ch tarr.e the                performed, at approstrnately equal intervals duritie each lo-year service period. The third L
an ns of the Arnerlean Nations! Standard            retest schedu'e spectfied in !!! D. may be test of eu.h set shall be conducted when the l         N4 5 61972. Lemange Rate Testing of Con.            resumed.
l La nment Structures for Nuclear Reactors.               B Type B tests.                                           plant is snutdown for the 10qent ptsnt in.
f                                                                1. Test methods. Acceptable means of pet,                  se r vice inspections $
bl rch 161972 8 Tbe method chonen for the forming . preoperational and periodic Type                        abi Permusihte r* rt ods f or testing. The r
B tests include:                                              perf armance of Type A tests shall be Itmtted j                                                                                                                             to periods t hen t*e plant f acility is non.
i ANSI N4' 4-J G72 Leakage Rate Testing of            fal Esamination by ballde leak-detection g
method (or by other equivaient tast methods                   operational and secured in the shut down
  ;       Containment 6tructures fer Nuclear Reactors                                                                         condttien under the admiriistrsttre control idated htar.16. int 2). Copies may be oe.            auch as mass spectrometers of a test cham, tatued from the American Nuclear Society,             ber, pressurized with str. tutrocen. cr pneu.                 and :n accordance with the ssfety procedures
  !                                                                                                                           dented m the license.
  .       244 East Ogden Avenue. Hinadale. IL 60'21.            ma tic f1uld specified in the tecnnical
  !       A ecpy is a s aniable for inspection at the           spec:fications or associated bases and con.                       2 TPpe 8 fests Type B testa escept testa ,.."
for air lock.s sh.til be perf ormed durrog esca t       Cornmanston a Public Dncument Roem 1717              structed as part of individual containment H Street N W., Washington, DC. The incer.             pe ne tra tions.                                                                                                   .;,,;.;,;,
T~
potation by reference was appresed by the                                                                                ' Such inservice it.spectiorks are requireo Director of the Federna 7tegnter on Octo.                                                                             ty i So f.Sm.
ber 30,1972.
* A menced D FR $ 00 7.
i September 1,1978                                                                 304o J

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FROM:
ACTION CONTROL               DATES Frasident's Commission on the Acciosat at                         COMPT. DEAOLINE            //10/78)    CONTROL     U Ng b 7 4              l Tara Atla Island                                             AC)(N OWLE DO M EN T                   DATE OF DOCUMENT                   l Af*tif f* 7 Landia                                                INTERIM REPLY G2[$                      l PREPARE FCR SIGNATURE               l Alchart Deig                                                      FINAL REPLY ,   .,,            f CHAIRMAN FILE LOCATION
                                                                                                                                       /               O EXECUTIVE DIRECTOR              I DESCRIPTION OTH E R r_ DE M O LETTER OMEMO O REPORT C OTHER SPECIAL INSTRUCTIONS OR REMARKS 4egmsts data os release of resteactive                                 If questions call Rohs for contact in materials for ==*ma*=g existles power                                  President's Commissica stattens                                                                                                                                    l
                                                                                                                                         .                                               1 CLASSIFIED DATA                                                    '
OOCUMENT/ COPY NO.
CL AS5lFICATIONl NUMBER OF PAGEs                                                     .#'                                        D CATEGORY                                            '/                                                  '
POSTAL REGISTRY NO.                       O NSI  O R D, . - CIR                                   "
ASSIGNED TO:               DATE       INFORMATION ROUTING                 LEGAL REVIEW                   D FINAL           U COPY Oft rica               7/6/73          60s&lCA                     Assew0 TO:                  DATE      N LE      L OBEMNS g)),p R                                                                    T
                                                        '                                     Schroeder-                                           O EoO AoMiN a CORREs BP (DrN4II gggg                                                                     E X T.
Mjqq                                                           COMME NTS. NOTIFY:
Haller r                                                                         '"-
3                                                             ., %
k                                                                         JCAE NOTIFICATION RECOMMENDED:                    O vEs       O NO NRC FORM 232 EXECUTIVE DIRECTOR FOR OPERATIONS
                                  -                                                                                                                DO NOT REMOVE THIS COPY PRINCIPAL CORRESPONDENCE CONTROL l
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