ML19059A155
| ML19059A155 | |
| Person / Time | |
|---|---|
| Site: | 07109360 |
| Issue date: | 02/28/2019 |
| From: | William Allen Spent Fuel Licensing Branch |
| To: | Industrial Nuclear Co |
| Allen W | |
| References | |
| Download: ML19059A155 (2) | |
Text
NRG FORM 699 (03-2013)
U.S. NUCLEAR REGULATORY COMMISSION CONVERSATION RECORD NAME OF PERSON(S) CONTACTED OR IN CONTACT WITH YOU See below.
E-MAIL ADDRESS ORGANIZATION Industrial Nuclear Company, Inc. (INC)
LICENSE NUMBER(S)
SUBJECT Request for Additional Information Teleconference
SUMMARY
DATE OF CONTACT 02/14/2019 TELEPHONE NUMBER (800) 857-9679 DOCKET NUMBER(S) 71-9360 CONTROL NUMBER(S)
DATE OF SIGNATURE 02/28/2019 TYPE OF CONVERSATION DE-MAIL 0 TELEPHONE D INCOMING 0 OUTGOING NRC participants: Chris Allen, Meraj Rahimi, Michel Call, Chris Bajwa, Tae Ahn, Yong Kim, Eli Goldfeiz and Jimmy Chang INC participants: Mike Rose, Ron Montefo11e Orano participants: Gary Clark A phone call between NRC staff and INC to discuss a request for additional information (RAJ) associated with a certificate of compliance request for the Model No. Ten Hole Source Changer package commenced at approximately 4:00 P.M. eastern standard time. After NRC staff provided some background information relative to the question, INC stated that the materials mentioned in the Materials RAI were either components purchased off-the-shelf, not important to safety or both. Following a short discussion, INC indicated they might identify the safety classification of each package component on the drawing in order to address the information request.
In discussing the Thermal and Shielding RA!, INC pointed to thermal tests performed for the IR-I 00 package (Docket No. 71-9157).
In these tests, the depleted uranium (DU) shield for the IR-I 00 did not oxidize even though the low density foam surrounding the DU shield was damaged. NRC staff responded that differences between the IR-100 and the Ten Hole Source Changer might make the Continue on Page 2 ACTION REQUIRED (IF ANY)
Continue on Page 3 NAME OF PERSON DOCUMENTING CONVERSATION Chris Allen SIGNATURE rt L.
NRC FORM 699 (03-2013)
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NRC FORM 699 (03-2013)
SUMMARY
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U.S. NUCLEAR REGULATORY COMMISSION CONVERSATION RECORD (continued) information not applicable; therefore, the information by itself was insufficient to address the RAJ. In addition, NRC staff pointed out that, if!NC could demonstrate that the DU shield temperature remained below the temperature required to ox idize DU, the DU shield would not oxidize even if air was able to reach it. When INC questioned why NRC staffs concern over thermal stresses, NRC staff responded that different thermal expansion coefficients for the package materials might cause structural issues. After discussing a date by which fNC could respond to the RA ls, the call concluded at approximately 5:00 P.M. eastern standard time.
NRG FORM 699 (03-201 3)
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