ML20128P331

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Requests Addl Info Re Applications Which Respond to Requirements Listed in Safety License Condition S-2
ML20128P331
Person / Time
Site: Westinghouse
Issue date: 10/15/1996
From: Gaskin C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Robert Williams
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
TAC-L30812, TAC-L30862, TAC-L30877, NUDOCS 9610170223
Download: ML20128P331 (4)


Text

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October 15, 1996 Mr. Robert A. Williams, Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION:

,~

1.

CSE AND FAULT TREE INFORMATION FOR THE URRS DISS0LVER SYSTEM, CSA

SUMMARY

INFORMATION FOR THE URRS SCRAP PROCESSING SYSTEM, AND CSE

SUMMARY

AND FAULT TREE INFORMATION FOR THE UN BULK STORAGE TANK SYSTEM (TAC N0.

L30812) 2.

CSE AND FAULT TREE INFORMATION FOR THE POWDER BLENDING SYSTEM (TAC N0. L30862) 3.

CSE AND FAULT TREE INFORMATION FOR THE ADV CONVERSION PROCESS (TAC NO. L30877)

Dear Mr. Williams:

This refers to your applications dated September 29, 1995, February 15 and 4

April 30, 1996, which respond to requirements listed in Safety License Condition S-2 of Materials License SNM-1107.

Our review of the applications has identified additional information that is needed before further action can be taken on your submittals. The additional information, specified in the enclosure to this letter, should be provided in the form of responses to the individual comments, as appropriate, or as revised pages to the application.

Please provide this information within 30 days of the date of this letter and reference the above TAC Nos. in future correspondence related to this request.

If you have any questions regarding this matter, please contact Mr. Craig Hrabal at (301)415-5424 or me at (301)415-8116.

Sincerely, Original signed by:

Charles Gaskin, Acting Section Leader Licensing Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS f

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Docket-70-1151 License SNM-1107

Enclosure:

As stated Distribution w/encls.

(Control Nos. 490S, 530S, 550S)

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October 15, 1996 Mr. Robert A. Williams, Project Manager Westinghause Electric Corporation Commercial Nuclear Fuel Division Drawer R 4

Columbia, South Carolina 29250 i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION:

1.

CSE AND FAULT TREE INFORMATION FOR THE URRS DISSOLVER SYSTEM, CSA

SUMMARY

INFORMATION FOR THE URRS SCRAP PROCESSING SYSTEM, AND CSE

SUMMARY

AND FAULT TREE INFORMATION FOR THE UN BULK STORAGE TANK SYSTEM (TAC NO.

L30812) 2.

CSE AND FAULT TREE INFORMATION FOR THE POWDER BLENDING SYSTEM (TAC N0. L30862) 3.

CSE AND FAULT TREE INFORMATION FOR THE ADU CONVERSION PROCESS (TAC N0. L30877) 4

Dear Mr. Williams:

4 This refers to your applications dated September 29, 1995, February 15 and April 30, 1996, which respond to requirements listed in Safety License Condition S-2 of Materials License SNM-1107, 3

4 Our review of the applications has identified additional information that is needed before further action can be taken on your submittals.

The additional information, specified in the enclosure to this letter, should be provided in the form of responses to the in'icidual comments, as appropriate, or as revised pages to the application.

Please provide this information within 30 days of the date of this letter and reference the above TAC Nos. in future correspondence related to this request.

3 If you have any questions regarding this matter, please contact Mr. Craig Hrabal at (301)415-5411 or me at (301)415-8116.

1 Sincerely, Char es Gaskin, Acting Section % Leader Licensing Section 1 4

Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-1151 License SNM-1107 4

Enclosure:

As stated 4

1 l

1 REQUEST FOR ADDITIONAL INFORMATION APPLICATIONS DATED 9/29/95, 2/15/96, AND 4/30/96 WESTINGHOUSE ELECTRIC CORPORATION DOCKET 70-1151 Please provide the following information:

1.

In the Powder Blending System, samples are taken from the polypaks to determine the moisture content before the polypaks are dumped into an unfavorable geometry container. The safety analysis stated that a composite sample is taken (consisting of a small amount from each polypak), and a few polypaks are individually sampled as the second moisture measurement.

Provide justification that supports the adequacy of these two sampling methods to assure that moisture limits are not exceeded in the unfavorable geometry device.

2.

For the large lot blender in the Powder Blending System, the saf 2ty analysis report indicates that to ensure that a potential critical quantity of moderator does not enter the blender, the mass of material is restricted.

However, the safety analysis report indicated that the mass measurement is performed after the material is in the blender.

After the powder is in the blender, how does ihe mass measurement effectively prevent a critical quantity of moderator from entering the blender?

3.

The safety analysis reports for the Powder Blending and UN Bulk Storage Tank Systems contained remarks that indicate that there was the potential for common mode failure.

In addition, there are several remarks that some initiating events might have an indetermira+e safety question.

How have these been resolved?

4.

Provide an analysis to demonstrate that monitor f the '

i Storage Tanks is adequate to preclude a critical.s.

Spet a. ally, how does your analysis show that monitoring is frequent enough to avet t a potential criticality should precipitation or settling occur?

5.

There are several discrepancies between Table 6.2.3 in your license and the CSEs.

For example, the vaporizer CSE requires mass and j

configuration defenses to fail for double contingency protection, i

however, the Table 6.2.3 only addresses " geometry (level control)" as j

the criticality safety basis.

" Level control" is also not defined in the license.

Likewise, the hydrolysis column CSE requires favorable geometry and limits on the concentration of uranyl fluoride for double contingency protection, but Table 6.2.3 only requires geometry as a criticality safety basis. There are a number of other examples of these differences between the license and the CSEs.

Provide an explanation or correction of these differences.

l l

ENCLOSURE

2 6.

Provide a justification for ensuring that tank ruptures will occur before exceeding geometry limits.

Specifically, have analyses been performed to show that less than rupture stresses can not expand tanks to their geometry limit?

1 7.

The CSEs provide numerous parametric / sensitivity calculations to show normal quantiti.,, from changes in parameter limits from normal to off-the effect on K es.

However, there are no analyses that demonstrate that the physical margin of safety is sufficient to show the likelihood of changing parameters to these off-normal quantities.

Provide analyses to show the margin of safety is sufficient.

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