ML20197H750
| ML20197H750 | |
| Person / Time | |
|---|---|
| Issue date: | 06/01/1984 |
| From: | Congel F Office of Nuclear Reactor Regulation |
| To: | Prichard C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20197F859 | List: |
| References | |
| FOIA-86-78 NUDOCS 8406200289 | |
| Download: ML20197H750 (8) | |
Text
- _ _ _ - .. .. .
g' #*%, UNITED STATES y- /'t NUCL. EAR REGULATORY COMMISSION r
,t M i, j WASHINGTON, D. C. 205$5
.....' JUN 011984 F- v we F ~" : Dr. Clark Prichard v
'esta ma;e snt tranc, b90 F' : F re n!. si . Conpl , rief edielo :icci ts sessmt t renc'., DSI p v ci. :; oty313 .ic ;- or :T OF 000"u Tl "mL r myune.s Fi.s <
t vTr.q, t.: . ;",i T*: ce iolo;ical ssass> < nt ': ranch has assosser' tna i- a ct or, occoactional ,
en u"re es a r- sult of extete.' int, fuel hurnu.. f ro.,.- 3?,00 ST to EC,1"" ,
?cr ar.al3 sis it. cit,ded occupatinntl exposurc f rv buil.i-vi, of inventory of len;-liv' ' fission proc'octs; frv chan;es in the refueling cycle; an<1 f ro -
+ ra r,s portatior of fuel.
"ur fir 'in3s are that the irpact vill riat rec,uire pre;arstion of en EIS for j occe,ationel ex,nsure since occupationsl exposure would 55 reluce ?s a result y
of tY action
'.t te c' ai is t ni ceteiled ant.,1ysis for our conclusions. The analysis was prr- -
f o r e
- by S . e l e ct. nrs/aro. ,
e / .
t Frank J. Congel, Chief ,
Fadiological tssasst.ent Brt.nch.
91 vision of Systems Integration cc: r. t.attson C. "uller P. Lynch P. Cote S. Block 5
y 84# 24916'pAeff K
/ 4
occooational ry;insura occupational axposura has dean considerad for extended burnup from 33,000
';DT to 55,110u DT in three uays: (1) exposure due to huild-up of the inven-tory of lon9-lived fission products; (2) exposure f rnn change in the refnal-ing cycle; (3) exposure inpact f rom transportation of fuel. Pl ant workers are considered part of the exposad population.
(1) prn1nction of rac4ioisotopes f rrri fission is proportional to the PT burnup and th. rate of grouth of rattionuclides. ' lost fission products will nave reach-ed saturation garra decay energy before reaching 33,00') MOT so that extending the cycl <' to 55,030 "oT would have little ef fect on occipational exposure f rn, .
tSese resinnuclides. Tne effect on occupational exposure of huild-up of the s inventory of long-lived fission products would also he negli9 ible. This is because long lived fission products entering the prinary coolant fron f ailed fuel, and leaking into Ptnt containnent, would constitute only a snall f rac-85 Kr tinnal incraase to the existing inventory in the prinary coolant. tisin9 85 Kr i nv ento ry -
as an exanple,one can coupute an increase of about 50? to the The exposure existing at 33,000 ' int, if the '10T was increased to 55,000 pathway for occupational exposure f ro? primary conlant leakage'is through airborne radioactivity. Attachments (1) and (2) show the saturation acti-Attach-vity, as a function of time, for all fission products decay act.ivity.
It rent 3 shows the result I.ig airborne radioactivity f rno a 1150 'Ule- reactor.
can he' noted that increasing the 85 Kr activity by 50% would have little ef-fect on the otherwise n+9 1191 ble inppct of airborne radioactivity to occupa-tional workers. Since no siun ificant additional inpact on occupational ex-S e
N l
V
% , as a result of prisi.ro f rom airbarne rer'iacactivity shoulct he f orthcomi -
extended nurnup, & do not 5elieve an r.lS naed be pre;>ared for this pathway.
As a consequence of extendef burnup, c'eclina in occupational exposure (2) is in he expectad. This is because of possible increase in refuelint, cycle iiiterv al s .
At present, about 57 of the annual occupational expnsure is from Pccupational Radiation Exposura at runnercial nucler refnalin3 (Fateranca:
peer Peactr.rs, lu">, nimm-u?)3 Voi, a Table 9.) ossaning linear huruup, toe normal 1" nne'.' (1.5 yrs) rafueliin, cycle based on 33,P::0 "nT* , would he in.
1 creasm! hy the ratio of 5$,nnti/33,unt, = 1.7 to (IMx1.7) = 3n nonths (2 1/2 ati/1.5 = 27 ref uelini,)s f or 33,00:. "0T yrs.). Au .p.ar reactor lif etim, we have 100 "9T. This provides a savings of ra-cna perce to ct'/2t=1C refuelings for $5,:
ceintion ex;.nsure for 11 refuelings. Thus, assuraint, an annual occupational ex-pnsure of a5 nut 700 person-rces fron all reactor operations, we got 11 (rafuel-5 nut 10-in3s) x (it.05) x 7u0=385 person-rees/ reactor saved over 10 years or 7 Consequently, an EIS person-rens/ri-actor year severi over the lif e of the plant..
neot not he prepared f or this ef fect on occupational exposure, eP L' art 51 contains a Sumary Table 5 ;4 which lists the environnental
( ~4) In Cru inpact tn the exposeit population and individuals in the exposed population of tre would consider raattor plant unrkers as shirrent of spent fuel f ron O'Rs.
part of the ex;.cser i.npulatin'n that receive the rattiatinn exposure shown in tho
- Although 33,00 'iDT is based on 3 years of core irradiation with annual re-fueling of 1/3 core, the present direction of PWR. licensees is to refuel 1/3 core every 18 months. This could increase the MDT of core irradiation to a-bout 38,000 MDT depending upon the, number of effective full power days during
- this interval. Our analysis of occupational exposure however dose not consider this effect becasuse of the uncertainties involved in the estimates.
- O e
4
' - - - _ . ~ _ _ _ _ _ _ _ _ _ _ _
in the table will he
- tahl". Tl+ i"' pact of extended Nirnup on tno values su r :
33,009 insi,nificant sinco the total inventory of neu fission ;irnducts beyond enT is not sisnificant. (see f.ttachments (1) ans' (2)). Henco an El% is not varrantect for this environnantal iripact to the exposed ;.npul at ion.
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tion and shutdown (Parker and Healy,195G).
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TABLE 12.2-12 .
AIRBORNE RADIOACTIVITY CONCENTRATIONS (pCi/cc)
Fuel Building Fuel Building Containment containment (power) (refueling)
(power) (refueling)
Nuclide 3.10E-6 1.66E-5 H-3 2.34E-7 4.7E-6 negligible negligible 1.25E-12 negligible negligible Cr-51 negligible negligible Mn-54 2.07E-13 negligible negligible 1.07E-12 negligible negligible Fe-55 negligible negligible Fe-59 6.63E-13 negligible negligible 1.06E-11 negligible negligible co-58 negligible negligible Co-60 1.33E-12 negligible negligible Br-83 1.76E-11 negligible negligible negligible Br-84 2.61E-12 negligible negligible ,
Kr-83m 6.60E-8 negligible negligible negligible Kr-85m 6.02E-7 negligible negligible negligible negligible negligible Kr-85 1.18E-7 negligible negligible 1.39E-7 negligible negligible Kr-87 negligible negligible Kr-88 8.34E-7 negligible negligible 5.83E-10 negligible negligible Kr-89 negligible negligible Rb-88 8.01E-7 negligible negligible 5.63E-10 negligible negligible .
Rb-89 negligible negligible Sr-89 3e54E-12 negligible negligible 2.49E-13 negligible negligible Sr-91 negligible negligible Mo-99 5.06E-11 negligible negligible 1.86E-13 negligible negligible Te-127m negligible negligible Te-127 4.01E-13 negligible negligible 9.26E-13 negligible negligible Te-129m negligible negligible Te-129 6.58E-13 negligible negligible 1.34E-12 negligible negligible Te-131m negligible negligible Te-131 2.69E-13 - negligible negligible 1.65E-11 negligible negligible Te-132 negligible negligible I-130 1.95E-11 negligible 7.6E-10 I-131 3.82E-9 2.14E-10 negligible negligible negligible 1-132 3.66E-10 negligible 5.5E-11 1.55E-II I-133 4.14E-9 negligible negligible 7.41E-11 negligible negligible I-134 negligible negligible I-135 1.34E-9 negligible negligible 2.75E-7 negligible negligible Xe-131m negligible negligible Xe-133m 1.35E-6 negligible negligible 7.24E-5 negligible negligible I Xe-133 negligible negligible Xe-135m 7.64E-9 negligible negligible 2.55E-6 negligible negligible Xe-135 negligible negligible Xe-137 1.26E-9 negligible negligible f 2.22E-8 negligible Xe-138 s
1 m _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ _ . - _ _ _ _ ___..,.___ _ _ _, .. . _ _ _ . _ , _ _ _ , _ - _ _ _ _ . , _ _ _ . . _ _
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- TABLE 12.2-12 (Sheet 2)
Fuel Building Fuel Building Containment Containment (power) (refueling) (power) (refueling)
Nuclide negligible negligible negligible Cs-134 1.67E-11 negligible negligible Cs-136 8.48E-12 negligible negligible negligible negligible Cs-137 1.20E-11 negligible negligible Cs-138 2.07E-8 negligible negligible negligible negligible Ba-137m 1.14E-11 negligible negligible Bn-140 1.43E-13 1.07E-13 negligible negligible negligible negligible ll Ln-140 ;-
1 NOTES:
- 1. Iodine airborne concentrations during refueling are calculated very conservatively, assuming no purification by fuel pool cleanup system ,
and no decay in the pool and a partition factor of 1 at the water-air
- interface at pool surface.
- 2. Continuous pool cleanup, decay in the pool, lower evaporation rates, ,
i and higher exhaust rates are expected to reduce iodine air con- j centrations to negligible levels during power operation in the i fuel building.
d
- 3. Xe-133 and 1-131 air concentrations in the - containment 1.6 x 10 s ventilation exhaust duct are expected to be $2 x 10 2 and However, the pCi/cc, containment 3 respectively during reactor head venting.
airborne concentrations for these isotopes are expected to be ;
significantly less during head venting since the radioactivity is directly piped **to the exhaust duct. The maximum value for Xe-133 i
i is based on operating plant measurements normalized for a reactor system which has continuous stripping of the noble gases in the volume control tank. The maximum value for ,I-131 is based on operating
, plant measurements.
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. PDE-04 l.S.E.A. ILLINOIS SAFE ENERGY ALLIANCE _.
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e2 ESP l 53 West Jackson Boulevard, Room 343
- Chicago, Illinois 60604 * (312) 663-1667 February 6, 1986 Director FREEDOM OF INFORMATKR<
Division of Rules and Records [d M UESTACTREQ[f,-N United States Huclear Regulatory Commission Washington, D.C. 20555 FREEDCM OF IIT?ORMATICH ACT R20UEST: High Burnup Fuel Experimentation in Commercial Lightwater Reactors To the Director:
This is a request under the Freedom of Information Act, y U.S.C. 5552, as amended, and the regulations of the Nuclear Regulatory Commission implementing the Act, 10CFR Part 9, Subpart A. This request is made on behalf of the Illinois Safe Energy Alliance.
This request seeks all records, as defined in 10CFR, Part 9, subpart A, Section 9 3 a (b), which refer to or are related to the performance of high burnup fuel and high burnup spent fuel in commercial nuclear power reactors and spent fuel p.ools in the United States and other countries. High burnup experimentation is also known as " uranium utilization" and " extended burnup."
The records sought are all of those dated or which refer to the period from 1975 to and including the present date. The enclosed list details some, (but, by no means all), of the records sought.
Because none of the statutory exemptions from the Act's mandatory disclosure provisions acclies, access to the requested records should
^~
be granted within ten (10) working days. In the unlikely event, however, that access is denied to any part of the requested records, please describe the deleted material in detail and specify the statutory basis for the denial as well as your reasons for believing that the alleged statutory justification applies in this instance. Please separately state ycur reasons for not invoking your discretionary pover; to r31r13e the requested documents in the public interest.
I anticipate that you will make the requested materials available within the statutorily pr33cribed period. I also request that you waive any applicable fees since disclosure meets the statutory standard for waiver of fees in that " furnishing the information can be considered as primarily benefiting the general public.", 5 U.S.C. A.
d552 (a)(4)(A), since the Illinois 3afe 2nergy Alliance 13 a public interest organization.
_ , , , ,-3,..,,
D WYW W i"
, Sincerely,
~,
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Catherine a uigg, P.eJearch Director (312/3El-669g
, w..
ay pHsOGRAM. Roas Unaar Condsons of tuonnal Overauun and Po.or Ramp., S R 2 Fnsion Gas Incaced Fues Swennog on I.M .
Path. H R Frecoum. L V Corsetti(C El e.,enced B mup F. o.nn,,sg, $,?$:$<g?
a.
MONDAY, APRIL 5,1982 Temperature Transients K Viniamun D 4 r,ss,= Gas Resease at H,9h Bumup M gp/,
4:30 a m. Welcome: M. F. Sankovich.
General Chawman (Babcock &
PO*I"d M Kauftnan. N Vm}nesount, R Atacen (CEA.Francet M Baron. J W Croucner. E. T. Laais (EG&G ndano) 3 Ouaancaon of USNRC Fues Rod
))g !
gg Behawur Codes to Entend Bumup ET i. ,, a Dudeker (FRAMA TOME)
A S. Tulenk . Technical Program Chairman tB&W)
S EPRI Support of F,ssson Gas Release Laats. D W Croucher. S L Seiltert. F.
M Hd9' jag (EG&G Idanot .y "=N g Measurements H Ocken. O Frankhn Opsning Remarks: P. M. Lang (USDOE). 4 NRC Assessment 0I Estended Bumw h y.%
(Electr.c Power Research insi.iuten Licens,ng L S Rubenstein (USNHC)
Ester.u.ed Burnup - Perspectnes & .D Espectatnons 6 Fsssson Froduct De havoor on Various PWR 5 r Laconsong Assessment.
DhR tirgh Ba nup -j*~s
- p y J 00 a m. SESSION t - EXTENDED Fuel Types kradestva at tsgn own p M bppens. 8 Van Ouuyve a vdewatie J E Wuud. R L Crossner. C E Dan. C a y p }&
BURNUP FUEL PERFORMANCE D. Sawyer (GE) e i (Dengonucteawe). J. Van de Veloo y, 3 4
Chairmen: Dr. H. Stehle (KWU'). Dr. E. (CEN SCK) 6 PWR bcensng Assessment D Frannhn -d* gNh8 Roberts (Westinghouse) (EPRI). A Strasser (Stoller) 1 Operating Encenence %th Combustion 2.00 p.m. SESSION 4 - EXTENDED 'rY
/ Eng.neenng s Fuet at High Bwnup. G P BURNUP PHENOMENA 7. The Status ofinfomationat Foot Portormance Programs-W 5N
- Chairmen
- P. Knudsen (Riso), Dr. D. Frank- 3 Smith. M G Anorews, S C. Hatheid E J N N.Y.
Ruzaunas (C-E) hn (EPRI) a. TR/BULAT/ON H Ba.not. D Haas. E. $
) 1. The inremational OVER RAMP Project at de Mueremmest(r. H Nacnaerts d
- r*)
a
! Fuel Performance Charactensucs at Entenaed Bumop R. S. Kaiser. H Stuasvun T E. Holloseth (Consumers). P.
(Bokjonucleaire)
- b. Hogn Bumun Ettects Program M C f N
, Kunnsns. W J Leecn. E Roberts. H Knuosen (Reso). H Mogard (Studsok) Freshiey (DNWL)
N*l f
W.ison. J. 8 Velenan iWeshngnouse) 2. Hogh Bumup Ettects on Pettet Clacanng c SUPER RAMP. DEMO-RAMP I. R, Eeendea Rumcp Fuel Peormance T. O interacDon Phenomena. R Alaben. N DEMO RAMP tt. H Mogard (Studsvin) f
~ h, dig, t V.gnescut (CEA-F ance). J. Josepn d R so F,ss,an Gas Release P. Knudsen Precha. T A. Coleman. G M Ba.n. J S , ir (FRAMATOME)
! Tuenko (e&W). R G Snipes J D a PCs um,tauon at E,tenaed Bumup R (N'50) h^
Kortheuer (Duke Power Company)
G. Batt.nger. R A Christensen. R F.
THURSDAY, APRIL 8,1982 e69tt-Bumup Performance of Eason 9.00 a m. SESSION 7 - IMPACT OF Nuclear Company Fuelm the H B. Edber1 (Entropy. Inc ). S Oidberg. Jr.
EXTENDED BURNUP ON THE FUEL (EPRI). E Rumcle (sal). A. K MSet Rcc nson Pressunted Water Readcr. C- (Sianford University) CYCLE
- i. A Esarhos. D E. Bentley. T A B; air. L Chairmen. S. Sandklet ($V), Dr. P. M. Lang F Van Swam. F. P Wanaquisi(Ennon 4 Densaccon. Swe#,ng and Microstrue.
(USDOE)
I Nuclear l tures at LWR Fuets Through Entenced Bumups S R Patts, N Fuhrman (C-E) 1 Tentative Evasu arion of Consequences of 4 5 Entended Bumup Fuelinvestigabons on Estenced Bumup on Reprocessing of commercial Reactors. J A Baumgartne'- S. French Analytocal Espenence on High LWR Spent Fuet. A Chesne. X Ta(mont y 1 l W E Ba ty. R A Proeussie, J F. Schard' Bumup Performance of PWR Fuet ]
(CEA Centre)
{ IGeneral Esectt c) Elements Unaer Steady-State Conditions- A
- 2. Eutenced Bumup nmplementatson -
{ 6 KWU Espenence and Anatys,s of LWR M Bruet. 8 Houdadie. A Araben (CEA-France). M Baron, M. Dodeber Assessment and Espenence M L Smdh. h. C NM g Fuet With Respect to H,gh Bumop H C'B Frankan (VEPCo). A S MWer Siehle. H. Fuchs H Knaso. R Manzei (FRAMATOME)
(West.nghousel 1
'KhU) 6 Ocservarson and Analysos of the Corrosion
$ 3 Economics of Entende d Bumop from a 5 2.t.0 p.m. SESSION 2 - EXTENDED Behavior of PWR fuel F Garzarottu. P Suchy (KWU). P. G Smerd (C-E) ytsty po,nt of V>ew H Hottman U. Wottt, {5 e:
BURNUP FUEL PERFORMANCE F. Bauer (RWE)
- t
- Cr wmen: R. Tomonto (Flonda Power & WEDNESDAY, APRIL 7,1982 4 Bumable Po, sons for Estended Bumup
- i Light). H. Heckermann (RWE) g' Jhr,q 9.00 a m. SESSION S - ADVANCED t Appacahon of Estenced Bumup A ULtery Perspecove W J bppo6d (Baitimore Gas FUEL DESIGNS FOR ACHIEVING HIGH BURNUP 3w3,(( '#
[ f Thornton. J. L Harnson. A Badruzzaman, g i Elecir c) 1 Chairmen: L. Raven (BNFL). Dr. K. Woods T. A Coleman. W A Wittkopf (B&W1. J L 2 aOE GE NSP Entended Bumup Program (Esson Nuclear l D Kortn euter (Dune Power) 3 O Anaerson. D. E Nemnsi(Normern Tgg ~
Swes Poweq 1 Dessga and Development of KWU t8s t0 S Ut la on of Gaaohneum Bumable Pooson &h "
3 Tr,e tsgn Bumuu trrac.arron Programs at PWR and 9a9 BWR Fuet Assemtwes and Theur Relevance to Bumua Increase R on PWR Estenced Bumun Fuel Cycles M G,eene. A Hams. R Loreis. P. Rohr. P RQM
%gr.k 19e FAA4tA TO&tE t74 t1 Standard Fue, O Donneti C. Bagnat (C E)
C Dwon. J P. Stora (FRAMATOMED Noizer. G bil. F. W Ansch (KWU) %*W I 2 Deveiopment of an Es: ended Bumop Fuel gf A Estenced Bumup fuel Performance on Assemtdy L A Waston. J T Wsilse. J E mme R J mn mm. A G Conventoonal and Low leahage Fuot Management Schemes for Arnansas W.*
RWE Reactors H Hecnerrrlann. V Wolft (R hE)
'; be&
Md"S*' I APSU Nuclear One. Unit 2 U Docher. A m.
N g'
1 MEA.A TGM fuet Rod Espenence Above 3 OW***f""' ""Id'ad %"'A Freem in (C E) m .w' N1 32.000 stWJ tcon U S Junnrans. O Esponence and Eatuarmn J 0 1. Pronected Natsonal Benetets to LWR Fuel etW vam.id I ASEA- ATOMS A.nscougn lUKAEAL D N Coucdt. D A Cycles From Estended Bumup P M , 'h ti nqn bamug Performance of DN Fuels un Hons i0t4FL). A Jensen i M sfeldt Lang. W E. Murpn.e (USDOE) C,T,=.*gh M '
inRs H Barriot. D Haas M bppens
!Dasysuaeasep 4 (p ,,,gn,,
l"dd'on Tests on Bamer fuelun 8 Impact ut Estenaed Burnup on the BA.R fuet Cycle P B Brown. J R Rashti p, -gy . h.4 ltg t j cp i 7
%taay of L WR Fuet Schavcur by Well Swpua I LargeSate Dornnnsuation (TVA). R L Crontruer. C G Hopk*ns. P x W.
- l Ch.uaaenzeJ Tests - Part / Inprie J" '" "$ **"*" # J 5 Annyo E Rusoy. E L Esch S 0 J Sawa a. O B Townsend. P Wei. O, 1Uu tGE) M.m I Afeasurement of CladJmg Drametral Cerarmar.on mm Bu r nup M Futu M y,,,, ,c g y 9 Estended San Bumuu Wm @uual
~-
D[ I k.h.kana K Yanagoaa a (JAPCL Part 2 y_, @.
S Some Cumments on Design,ng tcr Sh.tr Controt D G Churnh. A L
%t riraa,atmn Esamaation and Its Cmnitier. G C Hopnins. P J Savo.a. P SU"'e. Pac fuer Uenateur R W Straston y,, gggy q m'yh* c,4
., .p-c, Reisted Anarys,s ut Isuruga Fuel K (S*45 Fed"'dl '"$1 '"i*i y,,_ 9 y .
leasteilo Y Isuctan (JAERI) 6 The Cervertupinent ut Arusolar Petis;ts Win 2.00 p m SES$10N 8 - EK TENDED MM 4 TUESDAY, APRll 6' 1982 C'"""d" ""'"" C'""d'"9 and sonere- BURNUP: HOW FAR7 HOW FAST?
c3,,,,,, o,. R N Duncan (C E). H k, %p?) '
Pac fuel Designs far improved PCl 9 00 a m SESSION 3 - EKTENDED Res,>t. nce and Estunded BumW F W Mogaid (Studsvik)
.l,
- .p$ 'r '
- Q BURNUP PHENOMENA - FISSION MODUCT BEHAVIOR Bunman (Consumurs, C E Crouitmod g son Nocean M D Fresnicy J O Penet Discussion' p u ta,9 u S Deparimeni of Energy IrMM gg 7 Ct,.. mien: M D. Frestday (UNWL). Dr R A Meyer, u S M+ur Ho9uuto'f Uam.ir abNWLI n* * 'O iA Tracucci (FR AM A TOME) 2.00 p m. SESSION 6 - EXTENDED Commine N Y#
f,a.vaoon ut PutA3n ed tv,qrs Burnuu D Frankhn Eleonc Poae' Howd'C" l' 5'
/
smn Gas Re, case Data C E Uer e' DUHNUP FUEu IN TRANStENT AND OFF.NOHMAL OPERADON W J Lippusd Ballmue Gas & EfecthC M
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