ML20155E832
| ML20155E832 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 10/30/1998 |
| 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) |
| References | |
| CON-NRC-98-054, CON-NRC-98-54 TAC-L31068, NUDOCS 9811050193 | |
| Download: ML20155E832 (3) | |
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Westinghouse Commercial Nuclear Drawer R Electric Corporation Fuel Division fegasp9 carena 292so e
October 30,1998 i
Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l
Washington, DC 20555 l
Dear Sir:
SUBJECT:
CHANGED PAGES; LICENSE NUMBER SNM-1107; DOCKET 70-1151; l
REVISED TO INCORPORATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (TAC NO. L31068)
Westinghouse Electric Company hereby submits (six copies of) changes to a proposed f
l Revision 11.0 of Chapter 3.0, for the Application for Renewal of a Special Nuclear Materials l
License for the Commercial Nuclear Fuel Division at the Columbia, South Carolina Fuel Fabrication Facility. An enclosure to this letter describes the changes.
If you have any questions, please contact me at (803) 776-2610, Extension 3393.
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Sincerely, WESTINGHOUSE ELECTRIC COMPANY
/
. Robert A. Williams, Licensing Project Manager l-Westinghouse Columbia Plant l
l Docket 70-1151 i
License SNM-1107 V '2
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cc:
U. S. Nuclear Regulatory Commission
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ATTN: Mr. Charles Gaskin Licensing Section 1, Licensing Branch
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FCS&S Division, NMSS i
11545 Rockville Pike Mail Stop T8D14 i
Rockville, MD 20852-2738 9811050193 991030 ADOCK0700gylif (g
. Enclosures PDR-C
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4 NRC-98-054 October 30,,1998 DESCRIPTION OF CHANGES The enclosed changed pages of the License' Application reflect NRC Staff's expressed satisfaction with responses to their Request for Additional Information related to the original
' April 3,1998 submittal of the Amendment Request for Revision 110 of SNM-1107; including, in accordance with the October 28,1998 NRC/ Westinghouse Staff telecon, deletion of the proposed definition of "significant spreadable radioactive contamination." In addition, another " structured incident evaluation" (i.e., " Specific Cause Determination") has been added to Section 3.7.2 (page 3.18).
The pagination of this submittal still reflects (to a minor degree) the previously discussed anomaly resulting from Westinghouse confusion of " Revision Number" versus " Amendment Number." This has been manually corrected in all on-site copies of the License Application; and, in accordance with a prior commitment, will be electronically corrected (with a complete correct copy of the License Application submitted to NRC Staff) when Revisions 10 and 11 have been approved.
7
o (a.2)
Any incident involving Quality Level A systems, for which accident controls l cannot be initiated, whether or not regulatory limits are exceeded.
(b) 4-Hour Notifiutions (NRC Operations Center) l (b.1) Any incident involving Quality Level B systems, for which accident controls cannot be initiated, whether or not regulatory limits are exceeded.
J (b.2). Any nuclear criticality safety incident, in an analyzed system, for which less than F
previously documented double contingency protection remains (multi-parameter control or single-parameter control) and:
(b.2a) Greater than a safe mass is involved and double contingency protection is not restored within four (4) hours; or, (b.2b) Greater than a safe mass is involved and controls are restored within four (4) l hours, but:
- i. Only single contingency protection is restored; or, l
ii. Double contingency protection is restored but multiple original controls under both contingencies were modified or replaced.
(b.3) Any determination that a criticality safety analysis or evaluation was deficient, or that a particular system was not previously analyzed; and, that less than two unlikely, independe t, and concurrent changes in process conditions would be-required before a criticality accident would be possible.
(b.4)' Any unanticipated /unanalyzed nuclear criticality safety incident, or incident involving a previously unanalyzed system, for which the severity and remedy are not readily determined.
(c) 24-Hour Formal Notifications (NRC Operations Center) l (c.1) Any incident for which the work area is unavailable for normal use for 24-hours, following a loss of radioactivity contamination control, where the unavailability is due to the contamination.
(c.2)
Any incident for which Quality Level A or B system safety equipment is not performing its intended fmiction.
l (c.3) Any unplanned medical treatment at a medical facility when an individual has spreadable centamination on clothing or person.
Docket No.
70-1151 Initial Submittal Date:
30APR90 Page No.
3.19 l
License No. SNM-1107 Revision Submittal Date: 03APR98 Revision No. 11.0 l
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