ML20079Q300

Responds to Second Set of CP Interrogatories.Aerosol Plateout & Fallout Calculations Discussed.Affidavit Encl. Related Correspondence

ML20079Q300
Person / Time
Site:	Clinch River
Issue date:	05/09/1983
From:	ENERGY, DEPT. OF, PROJECT MANAGEMENT CORP., TENNESSEE VALLEY AUTHORITY
To:	National Resources Defense Council, Sierra Club
References
NUDOCS 8305110448
Download: ML20079Q300 (7)

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2 May 9, 1983 x 77 m, y UNITED STATES OF AMERICA v NUCLEAR REGULATORY COMMISSION 3\\

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD wwwwwwwwwwiwwwiLLwwiiiiwLuwiiwwLww wiwwww

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In the Matter of )

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UNITED STATES DEPARTMENT OF ENERGY )

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PROJECT MANAGEMENT CORPORATION ) Docket No. 50-537

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TENNESSEE VALLEY AUTHORITY )

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(Clinch River Breeder Reactor Plant) )

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APPLICANTS' RESPONSE TO NATURAL RESOURCES DEFENSE COUNCIL, INC., AND SIERRA CLUB'S SECONDLSETwCE CONSTBUCTIQUw2EBBITw2NTEBBOG&TOBJES Pursuant to 10 CFR 2.740b, and in accordance with the l Board's Construction Permit Scheduling Order of March 29, 1983, the United States Department of Energy, Project Management Corporation, and the Tennessee Valley Authority (the Applicants) hereby respond to the Natural Resources Defense Council, Inc.,

and the Sierra Club's Second set of Construction Permit Interrogatories and Request to Produce to Applicants, dated April 26, 1983.

DO O O O 37 PDR

s 2DLGEEDgDLDKWul How many reactor-years of operation have been accumulated during the operating history of all U.S. Naval reactors?

20teEEDeatDEgu2 How many ATWS events are known to have occurred among U.S. Naval reactors during their history of operation?

LDLCEEDGaLDEWL3 How many ATWS events are known to hate occurreo among l

AEC/ERDA/ DOE production reactors (the five at SRP and the nine at Hanford) during their history of operation? Give the breakdown l by reactor type.

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The CRBRP Project is not in possession of this information and the Applicants have not utilized or relied upon this information in support of its case in these proceedings.

The CRBRP Project has not undertaken such analysis and does not intend to conduct such a research effort.

l l 2DLBEEDgatDKyid Explain the significance of the Salem ATWS events to Applicants' position regarding the probability of an ATWS event l

at CRBR.

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BREPDDSEL4 The so-called Salem ATWS events are not significant to the Applicants' position regarding the probability of an ATWS event at CRBRP since (a) the CRBRP primary reactor shutdown system uses breakers different than those in use at Salem; the CRBRP breakers are sealed units that do not require periodic scheduled maintenance, and (b) CRBRP has two redundant, diverse, independent j fast-acting shutdown systems; the secondary reactor l

shutdown system does not use breakers to initiate l

reactor scram.

IDteEIDGatDIE45 Have Applicants calculated whole body and organ doses (see SER, p. A.5-10) for the parameters given in SER Table A.5-1 (p. A.5-9) except using 95% X/Qs instead of 50% X/Qs? If so, l

report all dose results for purposes of comparison with the results reported in Table A.5-2.

BRE90D5e No.

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l 3DLCEEDeatDEEu6 If dose calculations were performed with some, but not l

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all, parameters in Table A.5-1 (SER, p. A.5-9) changed, e.g., if any sensitivity results are available, report all dose'results and the changes in input assumptions.

Ec5pDD5e Sensitivity studies have not been perf ormed to determine the effect of changing the parameters in Table A.5-1 (SER, p.

A.5-9). The Applicants' sensitivity studies involving dose calculations are reported in CRBRP-3, Volume 2, Section 4.2 and Appendix G.4. Applicants have also assessed the effect on doses of simultaneously changing several parameters as explained in Applicants' Exhibit 46, Question / Answer 37 (TR:5409-11). The effect of those changes on the doses can be seen by comparing the table on TR:5410 to Table 5-1 in Applicants' Exhibit 1 (TR:2060).

JDteEEDEatDEyw2 Identify all assumptions regarding plateout and fallout associated with the Applicants' dose calculations reported in SER Table A.5-2.

Besponse The Applicants' dose calculations reported in SER Table A.5-2 are tak5n from CRBRP-3, Volume 2 (Rev. 5), Table 4-3, Case 2. The aerosol calculations of plateout and fallout are discussed in Section 4.2.1 of that report. Further discussion of I

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the aerosol modelling and assumptions is provided in Appendix D of that report. i l

The aerosol plateout and fallout is calculated using the '

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HAA-3B computer code. The pertinent input parameters f or the case reported in the SER are as follows:

Initial Particle Number Concentration XIN(1) = 2.09 x 108 of Aerosol (particles /cm3)

Aerosol Volume Variance SIGAIR = 8.0 Aerosol Mass Mean Volume (m3) VAIR = 2.7 x 10-2 Source Volume Variance SIGSOR = 8.0 Source Mass Mean Volume (m3) VSOR = 2.7 x 10-2 Density of Aerosol Material (g/cm3) RHO = 2.21 Viscosity of Air (dyne sec/cm2) VISC = 3.60 x 10-4 Temperature (OK) TEMP = 7.65 x 102 Diffusion Boundary Layer Thickness DELTA = 4.0 x 10-5 C2; ALPHA = 1.0 x 10-1 EL Err = 1.0 The initial particle number concentration of the aerosol, the aerosol volume variance, and the aerosol mass mean volume were based on the aerosols resulting f rom burning the 1000 lbs. of sodium assumed to be initially released through the heaa.

In addition, the analysis has a time varying aerosol source term, representing the flow of sodium and associated fission products from the reactor cavity into the reactor containment building,

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. 1 based on CACECO calculations. The aerosol density is based on l the mixture of sodium hydroxide and sodium monoxide, which are the primary components of the aerosol.

l The air viscosity is based on the peak containment l

atmosphere temperature occurring during the sequence as calculated by the CACECO code. The value of dC E, was calculated by a conservative linear extrapolation method which was based on the experimental data reported in Ref erence D-1 on page D-6 of CRBRP-3, Volume 2. Appendix D of CRBRP-3, Volume 2, provides additional descriptions and references for these input i parameters.

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

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In the Matter of -

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UNITED STATES DEPARTMENT OF ENERGY )

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PROJECT MANAGEMENT CORPORATION ) Docket No. 50-537

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TENNESSEE VALLEY AUTHORITY )

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(Clinch River Breeder Reactor Plant) )

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AFFIDAVIT OF PETER J. GROSS Peter J. Gross, being duly sworn, deposes and says as follows: .

1. That he is employed as Assistant Director for Public Safety, CRBRP Project, and that he is duly authorized to answer Interrogatories 1-7 in the Second Set of Construction Permit Interrogatories.

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2. That the above-mentioned and attached answers are .

true and correct to the best of his knowledge and belief.

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Signature) l SUBSCRIBED and SWORN to before me this _ 'l dd> day of May, 19 83.

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/ Notary Public)

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