ML20196G048

Declaration of M Resnikoff in Support of State of Utah Amended Contention C.* Declaration of M Resnikoff Re Preparation of State of Utah Amended Contention C

ML20196G048
Person / Time
Site:	07200022
Issue date:	06/22/1999
From:	Resnikoff M RADIOACTIVE WASTE MANAGEMENT ASSOCIATES, UTAH, STATE OF
To:
Shared Package
ML20196G006	List: ML20196G002 ML20196G048
References
ISFSI, NUDOCS 9907010040
Download: ML20196G048 (11)

Text

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i UNITED STATES OF AMElllCA BEFORE THE U.S. NUCLEAR REGULATORY COMMISSION j

ATOMIC SAFETY AND LICENSING BOARD la the Matter of PRIVATE FUEL STORAGE. L.L.C.

(Independent Spen Fuel Docket No. 72 22 ISFSI Stsrage lastallation)

June 22.1999 DECLARATION OF DR. MARVIN RESNIMOFF IN SUPPORT OF STATE OF UTAH'S AMENDED CONTENTION C

1. Dr. Marvin Resnikoff. declare under penalty of perjury that:

1. I am the Senior Associate at Radioactin Waste Management Anacciates a private consulting firm based in New %rk City. On November 20.1997 and Janu.ry 18.1908. I prepared declarations which were anbmitted to the Lic.cnoing Board by the State of 1;tah in support of its contentions regarding Private Fuel Storace. L.L.C.'s proposed independent Fuel Storage Installation. A statement of my qualifications was attached to Nevernber 1997 declaration.

2. I am tamtliar with Private fuel Storage's ('PFS ") license application and Safety Ama!> sis Report in this proceeding, as well as the applications for the storage and transportation casks PFS plans to use. I am also farniliar with NRC regulations, guidance documents, and environmental studies relating to the transportation, storage. and disoneal of spent nuclear power plant fuel, and with NRC decommissioning requirernents.

3. I assisted in the preparation of the State of Utah's Amended Contention C. The technteal facts presented in Amended Contention C e.vu-uc and correct to the best of rny knowledge, and the concipione drawn from those facts are heaed on my best professional Jud nt.

/

Dr. Marvin'Resnilioff[

June 22.1999 I

l 9907010040 990623 i

PDR ADOCK 07200022 C

PDR Td WdSP:E0 665T CE unt BTSO OE9 ETE : 'ON BNCHd INEN30tNOW 31strl an!1* 31006 : WOdd E

06/23/99 14:35 HARMON.CURRfV4.5Pi + 18013660292-264 NO.362 D02 a

SPENT FUEL PROJECT OFFICE OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS I

William F. Kane, Director INTERIM STAFF GUIDANCE l

ATTACHMENT

06/23/99 14:35 H'e10N, g g g gp! -* 18013662292-264 NO.362 D03 INTERIM STAFF GUIDANCE (ISG)

ISG-1 Damaged Fuel 15G-2 Fuel Retrievablity i

ISG4 Post Accident Recovery and Compliance with 10 CFR 72.122(l)

ISG4 Cask Closure Wold Inspections ISG4 Normal, Off Normal, and Hypothetical Accident Dose Estimate Calculations for the Whole Body, Thyroid, and Skin ISG4 Establishing Minimum initial Enrichment for the Bounding Design Basis Fuel Assembly (s)

ISG.7 Potential Generic lasue Concerning Cask Heat Transfer in a Transportation Accident 9

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= N 13660292-264 no.asa Spent Fuel Project Omco Interim Staff Guidance 6 lasue:

Normal, off normal, and hypothetical socident dose estimate calculations for the whole body, thyreld, and skin.

While the sts# considem there will be no effluent from a storage oesk, the applicant must demonstrate compliance with 10 CFR 72.104(a),10 CPR 72.106(b), and 10 CFR 72.126(d). It is the staffs assumption that leakage of gases, volatiles, bei Anos, and crud is credible and should be addressed. The anstyeis should be based on a souros temi that includes all redonuclides that are greatsr than 0.1% of the total activity present in the fuel plus lodine (this would result in approximately g6% of the dose if the totalirwentory were included). The guldence given in Table 41 of NUREG 1817 (DRAFT) and Inchnical besos given in NUREG/CR 4467 -provide release fractions relative to gases (f ), volatiles (f,), bei fines (f,),

and crud (fe). NUREG/CR4487 also provides the basis for determining the quantities of radionuclides forinclusion in the source term. The use of a computer code such as 8A32H to generste this souros term or the shleiding souros term is acceptable to the staff.

An assumed minimum leakage duration for normal and o#-normal conditions of one year and a minimum leakage duration for hypothetical accioent conditions of 30 days are considered appropriate. The analyses should use the leak rate from tested conditions as adjusted to account for bounding conditions of storage fbr normal, o# normal, and accident conchtions (temperatures and pressures) as on assumed leakage rate for the normal, o# normal, and eccklent condthons.

I For determestion of X/Q values, absent site-specific data, use of Class D stability and wind veloclty of Ave m/s meteorological conditions may be used for long term conditions (normel, oN normal). For short. term conchtlons (a hypothetical accident), use of Class F stately and wind speed of one m/s meteorological condition is considered bounding.

The sta# accepts dose celeulshons using Dose Conversion Factors from EPA Federal Guidanos Reports 11 and 12 on en isotope specific basis. No weighting or normaliantion of the dose conversion factors is ecoeptable since tNs may not be conservative. The resultant dose for normal conditions of storage must be a smal fraction of the 25 mromtyr limit of 10 CFR 72.104(a) to accommodate an array of casks and extemal direct done. For off-normal condllions, only one cask need be consklered, but the resultant uose must be a fraction of the dose limit so that when added to the dose torn normal conclitions it stE meets 10 CFR 72.104(a).

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a n 3,gg 14:35 I' W R4sSPI ' 2 =23sse232

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to.362 ;

Recommendatiota:

Update NUREG-1536 Chapter 7, Sections 3 and 4, (pages 7 5 7-7); Chapter 10.Section V,3, (page 10 3): and Chapter 11, SocWon V. 3 ( page 11-3) to reflect tNs new poeWon. NUREG-1567 should eles be updated acconhngly.

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$(lfS Approved

_ William F. Mane Date e

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i DOE /RW-0184 R1 Volume 1 CHARACTERISTICS OF POTENTIAL REPOSITORY WA.STES JULY 1992

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I Prepared for the U.S. DEPARTMENT OF ENEF... '

OFFICE OF CIVILIAN RADIOACTIVE WASTE AANAGEMENT Washington, D.C. 20585 Prepared by the OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 managed by MARTIN MARIETTA ENERGY SYSTEMS, INC.

for the U.S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-840R21400 M

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1 1B-3 Table 1B.1.

Nuclide half-lives, decay modes, and recoverable heat (Q) from the ORIGEN2 decay library used to calculate radiological data a

Parent Half-life Decay mode

""E (W Ci)

H-3 3.897E+08 s Beta 3.367E-05 He-3 H-4 1.000E-03 s Beta 0.000E+00 He-4 He-6 0.808 s Beta 9.295E-03 Li-6 Li-8 0.842 s Beta 3.729E-02 Be-8 Be-8 2.000E-06 s Alpha 5.632E-04 He 4 Be-10 5.049E+13 s Beta 1.200E-03 B-10 Be-11 13.6 s Beta 6.823E-02 B-11 B-12 2.030E-02 s Beta 7.926E-02 C-12 C-14 1.808E+11 s Beta 2.933E-04 N-14 C-15 2.45 s Beta 1.702E-02 N 15 N 13 598. s POS or EC 8.957E-03 C-13 N-16 7.12 s Beta 4.334E-02 0-16 0-19 29.0 s Beta 2.857E-02 F-19 F-20 11.4 s Beta 4.167E-02 Ne-20 Ne-23 37.2 s Beta 1.226E-02 Na-23 Na-22 8.211E+07 s POS or EC 1.415E-02 Ne-22 Na-24 5.400E+04 s Beta 2.771E-02 Mg-24 Na 24m 1.990E-02 s IT 2.798E-03 Na-24 Na-25 59.6 s Beta 1.148E-02 Mg-25 Mg-27 560. c Beta 9.443E-03 Al-27 Mg-28 7.52BE+04 s Beta 9.088E-03 Al-28 Al-28 134. s Beta 1.794E-02 SI-28 Al-29 391. s Beta 1.394E-02 Si-29 Al-30 3.68 s

. Beta 3.393E-02 Si-30 Si-31 9.438E+03 s Beta 3.536E-03 P-31 Si-32 650. y Beta 1.245E-03 P-32 P 32 14.3 d Beta 1.014E-02 S-32 P-33 25.0 d Beta 1.470E-03 S-33 P-34 12.4 s Beta 3.023E-02 S-34 S-35 88.0 d Beta 9.924E-04 C1-35 S-37 5.06 min Beta 2.845E-02 Cl-37 Cl-36 9.499E+12 s POS or EC (1.90%)

1.475E-03 S-36 Beta (98.1%)

Ar-36 Cl-38 2.233E+03 s Beta 1.788E-02 Ar-38 C1-38m 0.716 s IT 3.980E-03 Cl-38 Ar-37 3.026E+06 s POS or EC 1.245E-05 Cl 37 Ar-39 269. y Beta 3.349E-03 K-39 Ar-41 6.577E+03 s Beta 1.036E-02 K-41 Ar-42 33.0 y Beta 3.557E-03 K-42 aPOS - positron; EC - electron capture; IT - internal transition;

• - excited state; n - neutron; and SF - spontaneous fission.

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