ML20236P712

Submits Proposed Rev 13.0 of Page IV of Application for Renewal of SNM-1107 for Commercial Nuclear Fuel Div at Columbia,Sc Fuel Fabrication Facility

ML20236P712
Person / Time
Site:	Westinghouse
Issue date:	07/13/1998
From:	Robert Williams WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20236P714	List: ML20236P712 ML20236P716
References
CON-NRC-98-027, CON-NRC-98-27 NUDOCS 9807170112
Download: ML20236P712 (2)

Text

_ _ _ _ -

n

)

'D Westinghouse Commercial Nuclear orawera Electric Corporation Fuel Division fjfgajpgpaea29250 NRC-98-027 July 13,1998 Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 l

Dear Sir:

{

SUBJECT:

REQUEST TO REPLACE SAFETY CONDITION: LICENSE NUMBER SNM-1107; l

DOCKET 70-1151 j

REFERENCES:

1)

SNM-1107 License Safety Condition S-2 2)

December 12, 1997 letter (RA-WLG-97-057); W. Goodwin (Westinghouse) to L. Ten Eyck (NRC) 3)

April 17,1998 letter (NRC-98-014); J. Allen (Westinghouse) to U.S. Nuclear Regulatory l

Cormnission Document Control Desk In accordance with the July 10, 1998 telecon between your Mr. C,wrles Gaskin, and Mr. Wilbur Goodwin (Westinghouse) and myself, Westinghouse Electric Compan).ereby submits (six copies of) a proposed Revision 13.0 of page iv, of the Application for Renewal of a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Columbia, South Carolina Fuel Fabrication Facility (CFFF).

If you have any questions, please contact me at (803) 776-2610, Extension 3393.

Sincerely, l

WESTINGHOUSE ELECTRIC COMPANY t' l >q '

Robert A. Williams, Licensing Project Manager Westinghouse Columbia Plant j

l cc:

U. S. Nuclear Regulatory Commission ATTN:

Mr. Charles Gaskin Licensing Section 1, Licensing Branch FCS&S Division, NMSS

,.;, O 11545 Rockville Pike Mail Stop T8D14 Rockville, MD 20852-2738 9807170112 980713 -

PDR ADOCK 07001151 C

PDR..

NRC-98-027 July 13,1998 DISCUSSn.$

This Request to Replace SNM-1107 Safety Condition S-2 incorporates the latest Columbia Plant Management-approved commitment to enhance the Interim CFFF Design Safety Basis, previously submitted in the Westinghouse letter to Ms. Liz Ten Eyck (NRC), from Regulatory Affairs manager -Wilbur Goodwin, on December 12, 1997, and, the detailed CSA/CSE upgrade schedule previously submitted in the Westinghouse letter to the U.S. NUCLEAR REGULATORY COMMISSION Document Control Desk (NRC-98-014), from Plant Manager Jack B. Allen, on April 17,1998.

Westinghouse requests that Safety Condition S-2 be replaced to read as follows:

S-2 Criticality Safety Evaluations (CSEs) and Criticality Safety Analyses (CSAs) will define the interim criticality safety bases utilized throughout the Plant. All CSA's and CSE's will be upgraded and/or completed in accordance with all applicable commitments in Chapter 6.0 of the License Application, 'and summaries (in the format of the License Annex) will be submitted to NRC. All completed CSA's and CSE's will be independently peer-reviewed in accordance with license requirements and related procedures. Configuration control data packages for ongoing changes to facility struco.r:s, systems and components will be filed with their respective CSA's and/or CSE's, to provide a substantially complete, "living" framework for system Integrated Safety Assessments (ISA's) that will ultimately become the Final CFFF Design Safety Basis described in Chapter 4.0 of the License Application. The submittal by the CFFF will be provided according to the following schedule:

TARGET COMPLETION DATB PROCESS SYSTEM 2Q98 UN Tanks

• 3Q98 ADU Conversion

• Rods (ADU & IFBA)

UF, Cylinder Washing 4Q9R ADU Pelleting URRS Dissolver*

Powder Blemiing (ADU)*

IQ99 IAw. level Waste Processing E

Hoods & Contamment 2Q99 URRS Scrap Processing Soleent Extraction l{

URRS Waste Treatment I

3Q99 Final Assembly Storage j.

IFBA (Excluding Rods) -

[.

Laboratories 1

('

• Will be done as ISAs (" Final Design Safety Basis")

i

< _ _ _. _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _. _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _. _ _ _ _ _ _ _