ML20041D069

Notifies of Correction to Numbering Sys in Amend 11 to License CX-10

ML20041D069
Person / Time
Site:	Lynchburg Research Center
Issue date:	02/16/1982
From:	John Miller Office of Nuclear Reactor Regulation
To:	Olsen A BABCOCK & WILCOX CO.
References
NUDOCS 8203040216
Download: ML20041D069 (3)

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FEB 161982 Docket No. 50-13

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9 Mr. A. F. 01sen REcggygg License Administrator

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Subject:

Correction to Amendment No. 11 On May 30,1980, NRC issued Amendment No.11 to Facility Operating License Co. CX-10. Upon reviewing the file we noted a discrepancy in the numbering system used in the license. This has now been corrected as fo! lows:

1 (1) the section indicated in Amendment No.11 Part A is changed to Part 4.g and each subsection numbered accordingly (4.g.1, 4.g.2, 4.g.3);and (2) the section indicated as Part B is changed to 4.h.

Sincerely, 31913&L SIGauRD BD James R. Miller, Chief Standardization and Special Projects Branch Division of Licensing

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Docket No. 50-13 FEB-161982 t

Mr. A. F. Ol sen License Administrator Babcock & Wilcox Company Lynchburg Research Center P. O. Box 1260 Lynchburg, Virginia 24505 f

Subject:

Correction to Amendment No,11 On May 30,1980, NRC issued Amendment No.11 to Facility Operating License.

c Co. CX-10. Upon reviewing the file we noted a discrepancy in the numbering system used in the license.

This has now been corrected as follows:

(1 ) the section indicated in Amendment No.11 Part A is changed to Part 4.g and each subsection numbered accordingly (4.g.1, 4.g.2, 4.g.3); and (2) the section indicated as Part B is changed to 4.h.

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Dear Mr. 01sen:

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The Commission has issued the enclosed Amendment No. 11 to Facilitf License.

No. CX-10 in response to your requests dated October 18,,1979, December 3,%....., -

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1979, and April 11, 1980..

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This amendment widens the allowed range of non moderator to moderator (M/W)~.

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volume ratios from the previous range b'etween 0.7. and 1.2 to a new range 7: :.

between 0.7 and 9.7.

This chan'ge will allow the performance 'of benchmarkVM6i5..g.d;fi critical experiments in support of the Department:of-Energy's program?i.n~ Light". 3 -

Water Reactor spent fuel pin storage.' This amendment becomes effective as of ~-

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r A copy of the related Safety Evaluation is also enclosed.'-_

Sincerely, or :..n sIcleEU

,JAES R. MILLIE /.i James R. Mi.ller, Chief Standardization and Special Projects-Branch Division of Licensing Office of Nuclear Reactor Regulation-

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Amendment No. 11 l..

Safety ' Evaluation

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THE BABCOCK & WILCOX COMPANY DOCKET NO. 50-13 I

_ CRITICAL EXPERIMENT TACILITY' AMENDMENT TO FACILITY tICENSE

• t Amendment No. 11 license No. CX-10.

1.

The Nuclear Regulatory Commission (the Commission) has founif A.

The application' for amendment by the Babcock & Wilcox C licensee) dated October 18, 1979, mation dated December 3,1979 and Aprilas supplemented by additional info 11, 1980, complies'with the standards and requirements of the Atomic Energy Act of 1954, amended (the Act), and the Commission's rules and regulations s forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application provisions of the Act, and the rules and regulations of th

, the C.

There is reasonable assurance (i) that the activities auth this amendment can be conducted without endangering the he safety of the public, and (ii)' that such. activities will be conduc in compliance with the Commission's re'gulations; 0.

defense and security or to the health and s E.

The issuance of this amendment is in accordance of the Commission's regulations and all applicable requiremen been satisfied; and F.

Publication of notice of.this amendment is not required since it of a license of the type ' described in 10 CF 2.

Accordingly, Facility L'icen addir.g the following items:se No. CX-10 is herebyJfurther' amended by-I' A.

by License No. CX-' 10, as amended, the licens 1979, as; supplemented by. additional information

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1979 and April 11, 1980 (h'ereinafter referred to as'the application),

to conduct certain experimerits using light and heavy water mixtures as moderator. at power levels up to one kilowatt thermal in its Spectral Shif t Control Reactor Critic'al Experiment Facility ("the f acility") situated in Bay No. 2 in its Critical Experiment Laboratory,

located near Lynchburg, Virginia.

The experiments shall be conducted in accordance with the procedures and subject to the limitations in License No. CX-10, as amended, in the application for license amendment and the following additional conditions:

The licensee shall con' duct critic'ai experiments consisting of 1) tightly packed fuel rod clusters.in'various arrays using' 2.46%

enriched U0 in aluminum clad rods.

2 Non-moderator to moderator volume ratios [MN) shall vary fro'm 2)

,0.7 to 9.7 fo.r the ' respective arrays.as indicated in the appli-cation.

The fuel assembly for each. experiment shall consist of 25 full

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3) clusters in a'5 x 5 array,as described in the ap' plication.

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The licensee shall submit a written report to the Commission following B.

completion of the program that describes and compares the measured results of various criticality experiments with the calculated and extrapolated values described in the application.

3.

This amendment becomes effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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, James R. Miller,' Chief Standardization and Special Project's~

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Branch Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance:

May 30,1980 1

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l Safety Evaluatiori by the Office of h'uclear Reactor Egulation Supporting Mencnent lio. Il to f acility License fio. CX-10 Babcock and Wilcox Company Docket tio. 50-13 Introduction Durjng the past few years, the Babcock and Wilcox Company (B&W) has conducted critical experiments for the Department of Energy's (DOE) program'to provide benchmark experiments for criticality calculations of stored Light Water Reactor (LWR) fuel assemblies.

DDE has extended the scope of th'is program at B&W in order to provide benchmark experiments.for tightly packed fuel pin storage.

E because with the decrease in like-These experiments are' of importance to p]icked array of pins represents an lihood of fuel reprocessing, a tightly pi attractive method of increasing.utilizat' ion of present storage space.

Although critical experiments representing higher arid lower non-moderator to moderator (M/W) volume ratios exist, thy lack of' suitable benchmarks in the range of the proposed B&W experiments requires conservatism in the -present calculational methods.

Since the M/W ratio of this high density fuel condition is outside the previous range of ratios allowed by the B&W license, B&W requested by letters of October 18, 1979, De'cember 3,1979, /,pril 11,19S0 and Apri.130,

'1980, a wideni,ng of the allowed range from 0.7-1.2 to "between 0.7 and 9.7.

This chartge would constitute Amendment flo,11 to license CX-10.

Discussion and Evaluation s

The proposed experiments will be conducted in the CX-10 facility in the Critical Experiment Laboratory. Building located at the B&W Research Center on the James River near Lynchburg, Virginia.

The proposed exp'eriments 'would utilize previously approved fuel pins of fuel pellets clad in aluminum.

These pins would be 2.46% enriched UO2 arranged in three differerit pitches in about 7" square assemblies.

The

.three pitches, representing in order the driest to wettest configurations, triangular pitch equal to the fuel pin diameter, square pitch equal to are:

the fuel pin diameter, and square pitch equal to 1.158 times the fuel pin Twenty-five assemblies in a 5x5 array will be assembled in the diameter.

core tank and brought cr.itical.

Moderator spaces of various sizes will be left between boice's to ' achieve criticality and to allow passage of boral The moderator and reflector used will be light water, with safety blades.

or without boric acid addition as necgssary to ac.hieve criticality at accept-f 0-06-1%1-0 0l/

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able moderator' height with all four safety blades fully withdrawn.

Reactivity control during operation will be provided by adjustment of noderator. height; in the range of normal operating heights, a change of one centimeter is worth a few cents i.n reactivity.

Moderator boron content adjustment can be made between runs.

The CX-10 facility is licensed to operate no higher than 1000 watts.

The mechanical assembly of the core's will be of the type used in previous experiments to assure integrity in the core, although individual hardware items will be specially fabricated. Top and bottom and fitti.1gs will be used in all three cluster types; intermediate restraint will be provided by, aluminum straps in the close packed clu' ters or by grids in the loose s

packed cluster.

A base. plate will position the clusters at the bottom and the tops will be fastened together by tie-plates attached to contiguous clusters. The core will be braced a5ai st the vall of the 9' diameter tank.

This tank was used from the earliest ex iments until the advent of the spectral shift (D 0) measurement's when.a

' diameter tank was installed 2

within it; the small tank and its assoc 4'ated hardware will be removed for-the proposed' measurements in order to.adlemmodate the' larger ' cores.

Potential accidents from operation at excessive power, mechanical ~ rearrange-ment of modules or pins or accidental ficoding of a dry. core can,be considered

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using the same rationale as was used in Referenc'e (1); the designs and procedures provide ample margin.

Due to license limits on the worth of an individual safety blade, the reactivity addition of the continuous rod withdrawal accident is limited to 0.05%/sec; this accident is highly unlikely and the addition rate is less than that for the addition of incorrect moderator discussed below.

Although also highly unlikely, addition of pure. vater to an asstmbly which requires boron for reactivity suppression is the maximum credible accideht.

KENO IV was used to calculate the expected raximum reactivity for the three types of clusters in the planned range of module separation distances:

the most reactive core was determined to be the loose-packed array 'with modules separated by 0.7 inch.. KENO has,been used by m' with the 123-group X50RN cr'oss section set to calculate more than 30 experimental configurations ranging from very wet assemblies to dry metal spheres.

Because none of the l

' justification for the program)ge'of the proposed experiments (he bench arks lies in the M/W ran l

, the largest difference between KENO and experiment, namely 1.9%, was added to the calculated excess o'f the loose ~-

packed core.

For the postulated accident-condition of addition of pure l

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The rate water to this assembly, the critical height is aMut 11 inches.

of reactivity addition for continued fill after criticality is gaiculated from an experimentally detemined relationship including a 10.n factor i

l data. The

'for the uncertainty ins and in the fitting of the exper menta peak-to-average (PTA) power ratio needed in the point kinetics calculation was calculated as a pin-to-pin times an assembly-to-assembly factor; about Also of significance 15% conservatism was added to the calculated value.

in the kinetics calculation is the fuel temperature coefficient of reactivity.

TUTAWL was used to perfom the resonance processing needed in this calculation.

B&W has determined that fUTAW.-calculated resonance integrals match experi-mentally detennined integrals of both He11 strand and pettus to about 1.5%;

hcwever a lot reduction in the calculated fuel te.perature coefficient was The effect of this last conservatism was evaluated assumed for conservatism.

not for the loose-packed core, but for the triancular pitch core sith However, by assuming separability and, assemblies separated by 1.5 inches.

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additivity, the effect was included in the calculation of peak clad temperature

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for the worst case condition in discussions with B&W.

i he maximum credible accident in The calculated peak clad temperature for the worst case core was'832 F, well below the approximately 120D*.F melti,ng l

temperature for the aluminum clad, and ~ano below the 1050 F calculated for I

the maximum credible accident.in a past critical experiment program.-

Environmental Considerations We have determined that this amtndment will not result in any significant environmental impact and that it does not constitute a major Commission action significantly affecting the qualify of the human environment. We;

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have also determined that this action is:not'one of those covered by 10 CFR 151.5(a) or (b).

Having made these determinations, we havr further concluded that, pursuant to 10 CFR 151.5(d)(4), an environmen'tal impact statement or environmental impact appraisal and negative declar ation need not be prepared in. connection with issuance of this amendment.

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Conclusion

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The staff has con'luded that B&W has used qualified methods and input data c

in their calculations and has included adequate conservatism in the results

. to allow for the lack of suitable, benchmark experiments.

The staff further concludes'that: (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously con-sidered and does not involve a significant decrease in safsty mirgin, the -

amendr.ent does not involve a significant safety consideration, (2) there is reasonable assurance that the health and safe 14 of the public will.not

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be endanger ~ed by operation in the proposed manner,.and'(3) such activities will be conducted in compliance with the Ccmission',s regulat. ions and the issuance of the amendment will not be inimical tor the comon defense and security or to the. health and safety of the public.

Reference 1.

BAW-1211

" Spectral Shif t Control Reactor Basic Physics Program, Criti' cal Experiment Hazard Evaluation ~," R. H. Clark, T. C. Englde'r, B&W Co.,

September _1960.

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