ML20236S198
| ML20236S198 | |
| Person / Time | |
|---|---|
| Issue date: | 04/29/1996 |
| From: | Delligatti M, Kokajko L, Lee H NRC |
| To: | Leeds E, Sturz F NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20236S154 | List: |
| References | |
| NUDOCS 9807240193 | |
| Download: ML20236S198 (8) | |
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.' ATTACHMENTS (3) 4 g
, Y n o' % ,% UNITED STATES e S NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. SpeeHotn
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April 29, 1996 MEMORANDUM TO: Eric J. Leeds and Fritz C. Sturz, Section Leaders Spent Fuel Project Office, NMSS FROM: RAI Task Group:
Mark S. Delligatti Lawrence E. Kokajko Henry W. Lee Carl J. Withee
SUBJECT:
STYLE AND FORMAT FOR REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUPPLEMENTAL INFORMATION RECARDING PROPRIETARY INFORMATION IN AN RAI In accordance with your request that was stated in a meeting regarding our work on April 29, 1996, we are providing this supplemental information regarding proprietary information in an RAI. This memorandum should be .
considered an addendum to our memoranda dated April 16 and April 23, 1996.
We believe that the Project Manager should work with the applicant, licensee, (
vendor, or certificate holder to limit, to the extent practical, the amount of proprietary information that is withheld from public disclosure. As a result, l we believe that the RAI should, to the extent practicable, contain only information that can be released unimpeded to the public domain. RAI items should be carefully worded such that, even if the source of the RAI is -
proprietary, the RAI itself can be released to the public domain. We do not i endorse withholding information within an RAI, and such types of information '
should be infrequent.
An RAI item deemed to be proprietary would generally be derived from a predetermined proprietary source and contain exclusively proprietary information in and of itself. If information in an RAI is determined to be '
proprietary, the proprietary items should be grouped together and placed in an addendum to the transmittal letter and its RAI enclosure. Since we anticipate that only a few items may ever fall into that category, specific rationale !
should be delineated for each request.
We view the meeting on April 29, 1996, and this memorandum as the completion of our project. If you have any questions, we would be pleased to respond to ;
them.
/ m' ,Q /
, ) 0 Mark S. Delliga ti Lawrence E. Kokajko Hen W. Lee Carl J. Withee 9007240193 990714 0 PDR COMMS NRCC CORRESPONDENCE PDR g
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". ATTACHMENT B(4)
-February 20, 1997 NOTE T0: SFLS STAFF RAI FORMATS RAI formats for Parts 71 and 72 are available on the G Drive:
Part 71 - G:\RAI71' Part_72 - G:\RAI72 When using these documents, please COPY and RENAME. If revisions are needed, please notify me.
Thanks N'
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-Ginny Th'arpe cc: D. Damiano l
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3Ml.313t2ulatory Acolicability Statements 10 CFR Part 71 This document. titled Request for Additional Information (pal). contains a compilation of additional information requirements identified to date by the U.S. Nuclear Regulatory Commission staff. duiing its review of the applicant's application and Safety Analysis Report (SAR) for Packaging. This request for additional information is authorized pursuant to 10 CFR 71.39.
Each RAI describes .information needed to complete the review of the application and/or the SAR and to determine whether the applicant has demonstrated compliance with the regulatory requirements. Where an individual RAI relates to the applicant's apparent failure to meet one or more regulatory requirements or where an RAI specifically focuses on compliance issues associated with one or more specific regulatory requirements (e.g.. Specific design criteria or accident conditions). Such requirements are specified in the individual RAl.
Chapter 1 Introduction (General Information)
The following regulatory requirements are applicable in this chapter: 10 CFR 71.0(a). 71.7(a) 71.33, 71.35(a). 71.37, 71.39. and Subparts E. F. and G. It should be noted that other regulatory requirements may be applicable to this section.
Chapter 2 Structural 4 The following regulatory requirements are applicable in this chapter: 10 CFR 71.7(a). 71.35(a). 71.39. 71.71. 71.73, and Subpart E. It should be noted ;
that other regulatory requirements may be applicable to this section.
Chapter 3 Thermal The following regulatory requirements are applicable in this chapter: 10 CFR I
71 7(a). 71.35(a). 71.39, 71.43(g). 71.71(a). 71.71(b). 71.71(c). 71.71(c)1.
71.73(a), and 71.73(c)(4). It should be noted that other regulatory requirements may be applicable to this section.
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Cwcainment Me rollowing regulatory requirements are applicable in this cnapter: 10 CFR 71.79 t. 71.35(a). 71.39. 71.43(c). 71.43(e). 71.43(f). 71.51. 71.61.
11 71(a), and 71.73(a). It should be noted that other regulatory requirements may be applicable to this section.
( [If failed fuel is under regulatory consideration. add 10 CFR 71.63 and AppendixA.] 1 Chapter 5 Shielding The following regulatory requirements are applicable in this chapter: 10 CFR
(
.71.7(a). 71.35(a). 71.39. 71.41. 71.43(f). 71.47, 71.51(a). 71.71(a).
71-73(a). and Subpart G. It should be noted that other regulatory requirements may be applicable to this section.
Chapter 6 Criticality The following regulatory requirements are applicable in this chapter: 10 CFR 71.7(a). 71.35(a). 71.35(b). 71.39. 71.55. 71.59, 71.71(a). and 71.73(a). It should be noted that other regulatory requirements may be applicable to this section.
' Chapter 7 Operating Procedures The following regulatory requirements are applicable in this chapter: 10 CFR 71.7. 71.35(a). 71.39. 71 71(a). 71.73(a). 71 111. and Subparts A and G.
including U.S. Department of Transportation regulations referenced in 10 CFR
'71.5 and.Subpart G. It should be noted that other regulatory requi.rements may be applicable to this section.
Chapter 8- Acceptance Tests and Maintenance Program The following regulatory requirements are applicable in this chapter: 10 CFR 71.7. 71.35(a). 71.39, 71.71(a). 71.73(a). and Subparts G and H. It should be noted that other regulatory requirements may be applicable to this section.
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General Reculatory Acolicability Statements 10 CFR Part 72 This document titled Request for Additional Information (RAl). contains a compilation of additional information requirements, identified to-date by the U.S. Nuclear Regulatory Comission staff during its review of the applicant's application and Safety Analysis Report.(SAR). This RAI follows the same format of the applicant's SAR.
Each individual RAI describes information needed by the staff for it to complete its review of the application and/or the SAR and to determine whether the applicant has demonstrated compliance with the regulatory requirements.
Where an individual RAI relates to the applicant's apparent failure to meet one or more regulatory requirements or where an RAI specifically focuses on compliance issues associated with one or more specific regulatory requirements (e.g. specific design criteria or accident conditions). such requirements will be specified in the individual RAI.
This.RAI is organized as follows:
Chapter-1 General Description Chapter 2 Principal Design Criteria Chapter 3 Structural Chapter 4 Thermal Chapter 5 Shielding Chapter 6 Criticality Chapter 7 Confinement Chapter 8 Operating Procedures Chapter 9 Acceptance Tests and Maintenance Program Chapter 10 - Radiation Protection Chapter 11 Accident Analyses Chapter 12 Conditions for Cask Use Chapter 13 Quality Anurance Chapter 14 Decommissioning Chapter 1 General Description The following regulatory requirements are applicable in this chapter: 10 CFR l
72.2(a)(1). 72.11. 72.24(b). 72.24(c)(3). 72.24(j). 72.28(a). 72.122(h)(1).
72.230(b), and 72.236(a). It should be noted that other regulatory requirements may be applicable to this section.
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P Ct. apter 2 Principal Design Criteria The following regulatory requirements are applicable in this chapter: 10 CFR 72.2(a)(1) 72.11. 72.24(c). 72 24(d). 72.24(e) 72.24(f). 72.24(g). 72.24(m).
72.24(1)(2). 72.30(a). 72.44(d). 72.102. 72.104. 72.106. 72.120(a) 72.122.
72.124. 72.126, 72.128. 72.130 and 72.236. It should be noted that other regulatory requirements may be applicable to this section.
Chapter 3 Structural The following regulatory requirements are applicable in this chapter: 10 CFR 72.11, 72.24, 72.26, 72.44(c). 72.102(f). 72.120. 72.122. 72.124, 72.182(b) .
72.182(c), and 72.236, it should be noted that other regulatory requirements may be applicable to this section.
Chapter 4 Thermal The following regulatory requirements are applicable in this chapter: 10 CFR 72.11. 72.24(c)(3) . 72.24(d) . 72.106. 72.122(h)(1) . 72.122(1) 72.128(a)(4) .
72.236(f). 72.236(g), and 72.236(h). It should be noted that other regulatory requirements may De applicable to this section.
Chapter 5 Shielding The following regulatory requirements are applicable in this chapter: 10 CFR 72.11, 72.24(c)(3). 72.24(d). 72.104(a). 72.106(b) 72.122(b). 72.122(c).
72.128(a)(2). 72.212. and 72.236(d). It should be noted that other regulatory requirements may be applicable to this section.
Chapter 6 Criticality The:following regulatory requirements are applicable in this chapter: 10 CFR 72.11 :72.24(c)(3). 72.24(d). 72.124(b). 72.236(c), and 72.236(g). It should be noted that other regulatory requirements may be applicable to this section.
Chapter 7 Confinement 1
The following regulatory requirements are applicable in this chapter: 10 CFR 72.11. 72.24(c)(3). 72.24(d). 72.24(1). 72.104(a). 72.106, 72.122(b).
72.122(h), 72.122(i). 72.128(a)(1). 72.236(e). and 72.236(1). It should be
- noted that other. regulatory requirements may be applicable to this section.
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Naoter 4 Operating Procedures Pe following regulatory requirements are applicable in this chapter: 10 CFR Parts 20 and 50 and 10 CFR 72.11. 72.24(e). 72.24(f). 72.24(1)(2).
72.40(a)(5). 72.104, 72.106. 72.122(f). 72.122(1) 72.128(a)(5). 72.150.
72.212(b)(9). 72.234(f). 72.236(h), and 72.236(1), it should be noted that other regulatory requirements'may be applicable to this section.
Chapter 9 Acceptance Tests and Maintenance Program The following regulatory requirements are applicable in this chapter: 10 CFR 72.11. 72.24(c). 72.24(1). 72.24(p). 72.82(e). 72.122(a). 72.122(f).
72.128(a)(1).72.162.72.212(b)(8).72.232(b).72236(g).72.236(j).
72.236(k). 72.236(1). and Subpart G. ' It should be noted that other-regulatory requirements may be applicable to this section.
Chapter 10 Radiation Protection The following regulatory requirements are applicable in this chapter: 10 CFR 20.1101. 20.1201, 20.1207. 20.1208. and Subpart F: and 10 CFR 72.11. 72.24(e).
72.102(b). 72.104. 72.106. and 72.126(a). It should be noted that other regulatory requirements may be applicable to this section.
Chapter-11 Accident Analyses
.The following regulatory requirements are applicable'in this chapter: 10 CFR 72.2(a)(1) 72.11, 72.24(b). 72.24(d). 72.24(m) 72.104(a). 72.106(b).
72.122(b). 72.122(d). 72.122(g). 72.122(h):. 72.122(i). 72.122(1). 72.124 72.126(a). 72.128. and 72.236. It should be noted that other regulatory requirements may be applicable to this section.
I Chapt'er 12 Conditions for Cask Use The following regulatory requirements are applicable in this chapter: 10 CFR 72.11. 72.24(g). 72.26. 72.44(c). 72.104. 72.106. 72.234(a). 72.236, and Subparts C. E. F. G. H. and 1. It should be noted that other regulatory requirements may be applicable to this section.
Chapter 13 Quality Assurance The following regulatory requirements are applicable in this chapter: 10 CFR i
72.11 and Subpart G. It should be noted that other regulatory requirements may be applicable to this section.
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!s coa x er 14 Decommissioning i The follow ng regulatory requirements are applicable in this chapter: 10 CFR :
61.55, 72.11, 72.24(q). 72.30. 72.54. 72.130. and 72.236(i). It should be noted that other regulatory requirements may be applicable to this section. J G:\RAl.72 l
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