ML20198A942
| ML20198A942 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000054 |
| Issue date: | 12/21/1983 |
| From: | Mcgovern J CHERNE CONTRACTING CORP. |
| To: | Kelber C NRC |
| Shared Package | |
| ML20155J110 | List: |
| References | |
| FRN-49FR27769, RULE-PR-50 AB60-2-074, AB60-2-74, AB61-2-74, NUDOCS 8605210361 | |
| Download: ML20198A942 (9) | |
Text
.-
-"~
/986 /- A fp/L iT M
' '.. ~
50-5 4 jlN UNION CARBIDE CORPORATION p.o sox 324.TuxEco.NEW YoAK 1o987 MEcMCAL FHODUCTS DVSON TELEPHONE NUMBEA (914) 351 e131 December 21, 1993 Attn: Dr. C. Kelber Nuclear Regulatory Commission Dffice of Research Hall Stop 1130 SS Washington, D.L.
20555
Dear Dr. Kelber:
I have enclosed another copy of the transparencies that i used in my presentation to the Commissioners on 12/19/63.
I have incluoed on them the comments that i added during the presentation.
Perhaps this will be more useful than the original outline you received at the briefing.
Thank you kindly for giving us the opportunity to present our ioeas on the LEU conversion issue directly to the Commissioners.
Please call me if you have questions on these transparencics or any other questions about the UCNR in the LEU conversion issue.
The promulgation of any rule mandating conversion to LEU is vitally important to us.
Very truly yours, Y
Jaws J. McGovern Business Manager Radiochemicals JJMcG:Js Enclosures (8 Transparencies) 8605210361 860514 PDR PR SO 49FR27769 PDR
UNION CARBIDE NUCLEAR REACTOR Tuxedo, N.Y.
RESEARCH REACTOR 5 Mw power LIGHT WATER MODERATED &
COOLED
- 95% DUTY CYCLE URANIUM-ALUMINUM FUEL (93% U-235)
NOT LABORATORY
)
5 MAJOR HOT CELLS 50,000 CI ELEMENTS 2, 3-83
- 60% DUTY CYCLE FUNCTION PRODUCE RAD 10 CHEMICALS PRODUCE RAD 10 PHARMACEUTICALS hEUTRON SERVICE IRRADIATIONS PRODUCTS MO-99, XE-133 1-131, 1-125, ETC.
MO-99/TC-99M GENERATORS, Tc DI AGNOSTIC REAGENT KITS NTD SI, ETC.
UNION CARBIDE, NUCLEAR PRODIETS IMPACT ON PUBLIC HEALTH NUCLEAR IEDICINE (Ill VIVO TESTS)
TYPE OF IOTAL 1980 TEST IEST PROCEDURES UCC CONTRIBUTES LUNG INHALATION 320,000 30%
LIVER 1,425,000 50%
BONE HMDP 1,615,000 50%
i BLOOD POOL 100,000 50%
KIDNEY 456,000 50%
LUNG EERFUSION 775,000 50%
BRAIN /INYROID 500,000 50%
TOTAL 5,181,000 2,500,000 RAD 10lMMUN0 ASSAY (IN VITRO TESTS)
THYROID HORMONES 48,000,000 50%
DIG 0XIN 14,000,000 50%
HUMAN CHORIONIC GONADOTROPIN 11,000,000 50%
B-12/ FOLATE 6,000,000 50%
I GE IMMUNE IEST 6,000,000 50%
CORTISOL 4,000,000 50%
ESIR10t 4,000,000 50%
ANG10TENSIN 1,500,000 50%
DIGIT 0xlN 1,400,000 50%
METH0TREXATE 120,000 50%
OTHERS 25,000,000 50%
TOTAL
~ 120,000,000 60,000,000
REACTOR BASED RADI0 CHEMICAL PRODUCERS WORLD MARKET j
THE STERLING FOREST LABORATORY IN TUXEDO IS A COMMERCIAL VENTURE WHICH OPERATES FOR PROFIT.
RELIABLE SUPPLY OF SHORTLIVED RADI0 ISOTOPES IS THE ESSENCE OF THE INDUSTRY.
ONE IN EVERY FOUR PATIENTS IN U.S. HOSPI T ALS BENEFITS FROM A NUCLEAR DIAGNOSTIC PROCEDURE, 70 PERCENT OF ALL NUCLEAR DIAGNOSTIC PROCEDURES ARE PERFORMED WITH THE TC-99M ISOTOPE, THE DAUGHTER OF MO-99 j
PRODUCT Mix:
MO-99 (FISSION PROCESS) 80%
XE-133 5%
l-131 5%
I l-125 5%
OTHERS 5%
l THE ISOTOPES OF MO-99, XE-133 AND l-131 ARE SEDARATED FROM THE FISSION PRODUCTS OF U-235.
l PRODUCERS (F.P. MO-99):
l UNION CARBIDE CORPORATION (UCC) 45%
ATOMIC ENERGY OF CANADA LTD. (AECL) 45%
f l.R.E.
BELGIUM (IRE) 5%
AUSTRALIAN ATOMIC ENERGY COMMISS10' ( AAEC) 5%
l AECL, IRE, AND AAEC ARE GOVERNMENT SUBS 10lZED ENTERPRISES.
l
7 LEU CONVERSION TECHNICAL CONSIDERATIONS OPERATING SAFETY:
CLADDING INTEGRITY (A)
NORMAL SERVICE (B)
ACCIDENT CONDITIONS THE LOW DENSITY, HIGH ENRICHED FUELS HAVE BEEN PROVEN TO BE RELIABLE IN NORMAL SERVICE AND UNDER ACCIDENT CONDITIONS.
THEY HAVE PROVEN RELIABLE IN APPROXIMATELY 30 YEARS OF NORMAL OPERATION AND ALSO UNDER ACCIDENT CONDITIONS DEMONSTRATED IN THE SPERT AND BORAX TESTS.
PERFORMANCE OF THE HIGH DENSITY, LOW ENRICHE9 FUELS CAN RE MODELED FAIRLY WELL IN COMPUTER CODES HOWEVER BEHAVIOR UNDER ACCIDENT CONDITIONS MAY NOT BE AS PREDICTABLE WITHOUT SOME EMPIRICAL DATA.
THERMAL HYDRAULIC BEHAVIOR (A)
HEAT FLUX (B)
COOLANT CHANNEL DIMENSIONS IT IS IMPORTANT TO MAINTAIN THE SAME THERMAL HYDRAULIC BEHAVIOR TO AVOID MAJOR COOLING SYSTEM CHANGES.
OPERATING EFFICACY:
NEUTRON ENERGY SPECTRUM THERMAL NEUTRON FLUX LEVEL THE UCNR OPERATES PRIMARILY FOR PRODUCING RADI0 ISOTOPES AND PERFORMING SERVICE IRRADIATIONS COMMERCIALLY.
THE FORD REACTOR CONVERSION TO LEU j.
RESULTED IN A HARDENED NEUTRON FLUX SPECTRUM AND A REDilCTION IN THE L
l THERMAL NEUTRON FLUX.
THESE CHANGES WILL HAVE SERIOUS -CONSEQUENCES IN THE UCNR OPERATION.
c
=
.. = -.
~.. _
- c. w== w -
0 LICENSING i
I REVISE TECHNICAL SPECIFICATIONS:
l (AT LEAST 2 MAN YEARS UCC & NRC)
REVISE SAR:
(RENEWAL OF PRESENT LICENSE l
STARTED 1980 AND RENEWAL IS EXPECTED IN 1984.)
I MAJOR LICENSE CHANGE:
(PUBLIC HEARING AND EIA)
WE AGREE WITH THE CONCERNS OF THE UNIVERSITY REACTOR COMMUNITY ABOUT THE SUBSTANTIAL EXPEhSE INVOLVED IN THE REQUIRED LICENSE RENEWAL PROCESS THAT WILL BE REQUIRED IN LEO CONVERSION.
IMPLEMENTATION ROUTINE OPERATION MUST NOT BE INTERRUPTED.
WILL NEED U S 2 FUEL WITH HIGH LOADING 3
DENSITY (1986.
LICENSE 1988 INSTALL INCREMENTALLY 1989 - 1990.
i
~. -
LEU CONVERSION l
FINANCIAL CONSIDERATIONS COST OF REACTOR CONVERSION:
RELICENSING COST INITIAL FABRICATION COST (Uo, ALUMINIDE, SILICIDE)
CURRENTLY ESTIMATED TO INCREASE 15 PERCENT INSTALLATION COST FUEL LIFE (PERCENT BURN-UP)
REPROCESSING COST IF REQUIRED TO DO S O,' IT WILL BE DESIRABLE TO CHOOSE AN LEU THAT WILL MAINTAIN FLUX LEVELS AND ENERGY SPECTRUM AND ALSO YIELD OPERATING ECONOMICS THAT WILL COMPENSATE FOR THE CONVERSION EXPENSE.
SOME BASIC LEU FUEL DESIGNS ARE PRESENTED IN THE FOLLOWING TABLE.
DESIGN NUMBER AND
- OF PLATES & MEAT WIDTH (MM)
UDENgITY l
2 3
4 TYPE GM/CM 16/.51 18/ 51 17/.76 16/1.0 F8 l
OR U3SI2 2.3 l 222 276 CURRENT COST i
U308 OR U3SI2 3.2 196 220 l 310 l
383
+
f387 U3SI2 4.0 244 275 479 U3SI2 4.8 293 330 l 464 575 CURRENT
- 580 COST V SI2 6.0 367 412 3
719 i
-METAL /H 0 METAL /H 0 2
2 THE FUEL DESIGNS APPEARING IN THE LOWER LEFT QUADRANT MAY BE SUITABLE TO PROVIDE THE NEUTRON SPECTRUM AND OPERATING ECONOMY THAT IS IN THE UCNR TO MAINTAIN OPERATING CONTINUITY.
COST OF IS0 TOPE PRODUCTION:
l REDUCED THERMAL FLUX WILL INCREASE VARI ABLE OPERATING COST PROP 0RTIONATELY.
(IF VARIABLE COST OF ISOTOPE PRODUCTION IS SEVERAL MILLION DOLLARS THEN A 10 PERCENT 9 EDUCTION IN, THERMAL NEUTRON FLUX WILL CAUSE INCREASED OPERATING EXPENSE 0F SEVERAL HUNDRED THOUSAND DOLLARS.
HARDENED FLUX WILL INCREASE TRANSURANIC PRODUCTION IN ISOTOPE TARGET WASTE.
(THIS WILL ADD A SUBSTANTIAL COST IN WASTE DISPOSAL.
IT MAY PRECLUDE OUR USING COMMERCIAL LLW BURIAL SITES.)
HARDENED FLUX WILL INCREASE FAST NEUTRON DAMAGE"IN NTD St.
IMPACT OF HEU/ LEU ISOTOPE TARGETS 1.
TECHNOLOGY DOES NOT EXIST-FOR CHEhlCAL SEPARATION PROCESS OF LEU TARGETS.
(SUBSTANTIAL DEVELOPMENT IS REQUIRED TO DEVELOP NEW CHEMICAL SEPARATION PROCESS.)
2.
C0FPARIS0N OF OPERATING CHARACTERISTICS IN UChh CORE.
HEU LEU ENRICHMENT 93 20 NOM. WGT./GMS. U-238 1
24 NOM. WGT./GMS. U-235 15 6
2 2
h0M. WGT./GMS. TOT. U 16 (50 MG/CM )
30 (100 MG/CM )
MO-99 YIELD 360 144 PU-239 (UCI) 10 TO 20 250 TO 500 3.
C0FPARIS0N OF OPERATING COST.
VARI ABLE COST OF PRODUCING h0-99 WOULD INCREASE BY APPROXIMATELY 2.4.
TOTAL COST WOULD INCREASE BY APPROXIMATELY 1.7.
SMALL REACTOR SUCH AS UCNR COULD NOT COMPETE hlTH HIGH POWER TEST REACTORS.
f i
....a :..
- =
i
SUMMARY
IF CONVERSION TO LEU FUEL BECOMES MANDATORY:
(A)
CONVERSION OF UCNR MUST BE WITH U SI2 3
(B)
CONVERSION MUST BE GRADUAL OR INCREMENTAL.
(C)
OPERATING COST WILL RISE IF THERE IS NO COST ADVANTAGE IN CONVERSION.
i f
IF THERMAL FLUX IS REDUCED IT WILL BE IMPOSSIBLE TO COMPENSATE FOR ADDED COST BY BETTER FUEL ECONOMY.
IF CONVERSION TO LEU TARGETS BECOMES hANDATORY:
UCNR COULD NOT COMPETE WITH OTHER PRODUCERS.
1 AT LEAST, THE SUPPLY OF F2 DICAL ISOTOPES WOULD BE LESS RELIABLE.
AT WORST, THERE WOULD BE A SHORTAGE OF MEDICAL ISOTOPES.
l l.
i l:t i
-