ML20236A643
| ML20236A643 | |
| Person / Time | |
|---|---|
| Issue date: | 07/22/1987 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-42 NUDOCS 8707280168 | |
| Download: ML20236A643 (5) | |
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1 FCM lt-MEMORANDUM FOR: Leland C. Rouse, Chief File:
Fuel Cycle Safety Branch
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Division of Fuel Cycle, Medical, I
Academic, and Commercial Use Safety i NO t # - p l'-
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FROM:
John P. Roberts, Section Leader Irradiated Fuel Section DN _ _ _.
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Fuel Cycle Safety Branch l,,E I
Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety 'g pgg l
SUBJECT:
MEETINGWITHTRANSNUCLEAR,INC.,(TN)
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SS 396 DATE AND TIME:
JULY 17, 1987; 9:00 a.m.
LOCATION:
Lawrence Livermore National Laboratory f
Livermore, California l
t ATTENDEES:
See Attendance List (Enclosure 1)
FUPPOSE:
To discuss submittal of a revised topic report (TR).
DISCUSSION-In order to facilitate the discussion of NRC staff comments on the initial TR submitted, TN proposed an agenda (see Enclosure 2). This was accepted. TN had not prepared a set of responses to staff comments. The discussions centered on understanding of the comments, and TN's development of responses to resolve them in a revised TR.
A major issue remained unresolved at the end of the meeting.
Criticality design for the fuel basket relies on insertion of a "moison spider assembly" of rods into a fuel assembly. It is questionable whetler this approach can satisfy design criteria of 10 CFP, Part 72 for at-reactor site storage, at least in the non-site-specific context of a topical report.
Original Signed by l
John P. Roberts, Section Leader l
Irradiated Fuel Section Fuel Cycle Safety Branch j
Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety l
DISTRIBUTION l
cProject.M4427 NMSS R/F JRoberts FSturz Beveridge/ Cornell 1-23 PDR FCIF R/F FBrown JSchneider 1
0FC: FCI i
8707280168 870722
foerth/as:
NAME:J PDR PROJ
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Md 2 PDR DATE:79.2/87 i
0FFICIAL RECORD COPY
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2 2 1987 ATTENDANCE LIST JULY 17, 1987 TRANSNUCLEAR, INC., MEETING John P. Roberts NRC/NMSS Alan S. Hanson Transnuclear Alfred G. Eggers Transnuclear Michael Mason Transnuclear Don Nocan Transnuclear William R. Lloyd LLNL j
Monika Witte LLNL Larry Fischer LLNL Martin W. Schwartz LLNL Mark Pount LLNL j
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ENCLOSURE 1
AGENDA FOR DISCUSSION OF NRC COMMENTS ON Tf1-24 TOPICAL REPORT l
INTRODUCTION KEY ITEMS FOR DISCUSSION (SEE TABLE 1)
DESIGN DRAWINGS MISSILES SEISMIC LOADIflG CASK DROPS Atl0 TIPPING BASKET LOADING CRITERIA CONTAINMENT BOUNDARY DEFINITION POIS0N SPIDER ASSEMBLY BASKET MATERIAL CHARACTERIZATION Co60 SOURCE CHARACTERIZATION OTHER IMPORTANT ITEMS FOR DISCUSSI0ll (SEE TABLE 2) 9712E 1
TABLE 1 - KEY ITEMS FOR DISCUSSI0tl 1
KEY ITEMS REFERENCE COMMEilT NUMBER i
DESIGN DRAWINGS 1.1.2 AND 1.?.5(A)
MISSILES 3.2.1.(A)
SEISMIC LOADING 3.2.3. 1 CASK DROPS AND TIPPING 3.1.11 AND 2.1.12 i
BASKET LOADING CRITERIA 3.2.13.2(C) l CONTAINMENT BOUNDARY DEFINITION 3.3.1 AND 3.3.2.1 POISON SPIDER ASSEMBLY 3.3.7.1 (C))
BASKET MATERIAL CHARACTERIZATION 4A.6.4.4 CHARACTERIZATION OF Co60 SOURCES 7.2.1(B) 6 (C)
Af10 7.3.2.2 (C)(D)(E) l I
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n TABLE 2 - OTHER IMPORTANT ITEMS FOR DISCUSSION i
KEY ITEM REFERENCE COMMEllT NUMBER' PRINCIPAL DESIGN CRITERIA 1.2.2 (A) C (B)
STRUCTURAL FEATURES 1.2.5 (B) THROUGH (F)
GEf1ERAL SYSTEMS DESCRIPTION 1.3 GEOGRAPHY AND DEMOGRAPHY OF 2.1 q
SITE SELECTED MATERIALS TO BE STORED 3.1.1 (A) THROUGH (F)
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STRUCTURAL AND MECHANICAL 3.2.1 (B) & (C), 3.2.1.2 (A)
SAFETY CRITERIA AND B, 3.2.2 (B), 3.2.6 (A), 3.2.10 l
SAFETY PROTECTION SYSTEMS 3.3.4.1, 3.3.5.2, 3.3.7.1A I
SHIPPING CASK REPAIR AND 4.5 MAINTENANCE CATHODIC PROTECTION 4.6 STRUCTURAL ANALYSIS OF 4A.5.1.5, 4A.S.5.2, 4A.S.2.3, CONTAINMENT VESSEL 4A.5.2.4, 4A.5.6, 4A.5.6.6.2 OPERATIONS SYSTEMS 5.1.2, 5.1.3.6, 5.2, 5.3, 5.4 RADIATION PROTECTION 7.3.1, 7.3.2.1, 7.3.2.2 ACCIDENTS 8.2.5.2(B), 8.2.7.2 OPERATING CONTROLS AND LIMITS 10.1.2.1 l
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