ML19294B309
| ML19294B309 | |
| Person / Time | |
|---|---|
| Site: | 07001113, 070113F |
| Issue date: | 04/18/1977 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19294B308 | List: |
| References | |
| 14389, NUDOCS 8002280164 | |
| Download: ML19294B309 (4) | |
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l April 18,1977 l
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Mr. L. C. Rouse, Chief l
Fuel Processing and Fabrication Branch Division of Fuel Cycle and Material Safety Office of Nuclear Materials Safety and Safeguards U. S. Nuclear Regulatory Comission Washington, D. C.
20555 R W rence: HRC License SNM-1097, Docket #70-1113 Ocar Mr. Rouse:
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SUBJECT:
Application Amendment 3. Training Programs With reference to activities authorized by SNM-1097 at its fuel fabrication plant in Uilmington, North Carolina, General Electric Company hereby requests a change in wording concerning training programs, as described in Section 5.1.8 on pages A-23 and A-24 of Appendix A to SNH-1097.
Specifically, the requested change refers to the second paragraph of Section In the first line of this paragraph, we wish to change 5.1.8 on page A-24.
the words, "A separate training program will be established for each type of..." to read, " Training programs will be established for each type of..." (see attachment).
The present wording referring to training programs in S e tion 5.1.C of Appendix A to SNM-1097 requires a separate training progt am for each However, our exper-working position in the fuel manufacturing operation.
ience with the training programs has demonstrated that, in some cases, parts '
of or all of the training program for one such position may be identical to that for another position. Also, the training programs are not fixed in i
scope or emphasis but are changing to meet the needs of our business.
Therefore, we are re. questing the aforementioned change in the relevant license condition to assure that the potential for a technical noncompliance to the license condition does not exist as far as our training programs are concerned.
General Electric believes that the granting of this amendment request is not contrary to the public interest.
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4 Mr. L. C. Rouse I
Page Two April 13, 1977 Your prompt consideration of this request would be appreciated. General i
Electric personnel would be pleased to discuss this matter further with you and members of your staff, as you deem necessary.
Very truly yours.
GENERAL ELECTRIC COMPANY i
Arthur L. Kaplan Consulting Engineer Licensing ALK:pir
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cc: Mr. N. C. Moseley, Regional Director U. S. Nuclear Regulatory Comission Office of Inspection and Enforcerent Region II - Suite 018 230 Peachtree Street, N'el Atlanta, Georgia 30303 bcc:
D. A. Domey Dr. R. Ehrlich J. A. Mohrbacher File 0.2 Lic. Chronol. File Working File 226 Letterbook 1
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t ATTACHMENT TO LETTER TO MR. L. C. ROUSE, DATED APRIL 18, 1977 PROPOSED CHANGE IN DESCRIPTION OF TRAINING PROGRAM Ifl i
SECTION 5.1.8 CF APPEflDIX A TO Sf;M-1097 i
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nuclear safety, plant operating and emergency procedures, prior to such I
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employees working with special nuclear material.
A criticality control training program, under the direction of the criticality safety function, shall be maintained to emphasize the need for following criticality control procedures, but not to teach personnel how to set criticality safety limits.
- Training programs
- will be established for each type of working i
position, such as foreman, supervisor, equipment operator, radiation protection technician, etc., commensurate with criticality safety respon-sibilities associated with each such position.
The effectiveness of the training programs in criticality safety shall be verified by the criticality safety function.
5.2 Technical Requirements J
5.2.1 g
Safety Limits (a)
Enrichment Limits The maximum nominal U-235 enrichment of any uranium compound handled, used or stored shall be 4.0% except for the following:
(1) Enrichments up to 6.0% may be used in safe batches, based on the highest enrichment involved, for UO2 powder blending, ar.d for preparation of laboratory standards for use in laboratory operations.
1 (2)
Enrichments up to 4.5% may be received in the form of loaded fuel rods for use in fabricating fuel assemblies.
(3) Up to 1 gram U-235 at any enrichment level ay be received as 4
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5.2.I(3)
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Appenuix A 3*
April 18, 1977
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