ML19212A219
| ML19212A219 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/09/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19207B153 | List: |
| References | |
| REGGD-01.038, REGGD-1.038, NUDOCS 7908230539 | |
| Download: ML19212A219 (5) | |
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R. cr i. 38, fac -3 Preliminary Value Impact Statement on Regulatory Guide 1.38, Rev 3,
" Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power Plants" 1.
The Proposed Action A.
Description Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," establishes overall quality assurance req sirements for the design, construction, and operation of safety-related structures, system and compor.ents of nuclear power plants.
T: e proposed regulatory guide describes a method acceptable to the NR( staff for complying with the Commission's regulations for the packaging, shipping,
- meiving, storage, and handling of it>_'.as for nuclear power plants.
B.
Need for the Proposed Action Existing guidance on quality assurance requirements for packag-ing, shipping, receiving, storage, and handling of items for
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nuclear power plants is contained in Regulatory Guide 1.38,-
Rev. 2 which endorses ANSI N45.2.2-1972, " Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and 1
Handling of Items for Nuclear Power Plar,ts During the Construc-4 tion Phase".
Revision 1 to ANS1 N45.2.2-1972 has been approved
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and designated ANSI /ASME N45.2.2-1978.
Current NRC guidance should be updated to establish an NRC por,i-tion on the revised approved national standard.
C.
Value/Imcact of the Prcoosed Action 1.
NRC The NRC staff has been involved in the development, review and approval of the revised national standard.
The proposed action will establish an NRC position by taking advantage of previous staff effort in conjunctici with approval of the revised national standard and, ther fore, will have minimal impact.
2.
Other Gcuernment Agencies Not applicable, unless the government agency is an applicant, such as TVA.
3.
Industry The proposed action establishes an NRC position to an exist-ing national standard and, therefore, reduces uncertain!y as to what the staff considers acceptable in the area of quality assurance requirmaents for packaging, shipping, receiving, 2
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storage and handling of items for nuclear power plants.
Most of the impact on industry has already been accccplished in conjunction with development, review and approval of the national standard.
Additional impact associated with endorse-ment of the standard sheild be minimal.
4.
Workers (relative to ALARA)
Not applicable.
5.
Public No impact on the public can be foreseen.
Regulatory Position 1 provides information to t!a user of the guide concerning applicability of referencet standards and has no impact.
Regulatory Position 2 clarifies the requirements of section 4,
" Shipping," of the standard noting that nothing in that sec-tion of the standard should be deemed to require com. mon or contract carriers transporting byproduct, source cr special nuclear material in the ordinary course of its basiners to comply with the provisions set forth in the standard.
This was a position in Revision 2 to Regulatory Guide 1.38, and including this position in Revision 3 to Regulatory Guide 1.38 should have no impact.
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Regulatory Position 3 clarifies the requirement for vapor barriar material to be of a contrasting color to the acuip-ment on which it is used.
This was a positicn in Revision 2 to Regulatory Guide 1.38, and including this position in Revision 3 to Regulatory Guide 1.38 should have no impact.
D.
Decision on the Procosed Action As previously stated, guidance should be issued on the revised quality assurance requirements for packaging, shipping, receiving, storage and handling of items for nuclear power plants.
II.
Technical Acoroach This section is not applicable to this statement since the proposed action is an endorsement of a recently approved and issued national standard.
The technical issues have been previously discussed.
III. Procedural Accroach Previously discussed.
IV.
Statutory Considerations A.
NRC Authority This guide would fall under the authority and safety require-ments of the Atomic Energy Act.
In particular, Criterion XIII 4
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of Aopendix 8 to 10 CFR Part 50 establishes quality assurance requi"ements for handling, storage and shipping of safety related structures, systems and components for nuclear pcwer plants.
8.
Need for NEPA Assessment The proposed action is not a major action, as defined by 10 CFR Part 51.5(a)(10), and does not require an environmental impact statement.
V.
Relationship to Other Existino or Prooosed Regulation or Policies No conflicts or overlaps with requirements promulgated by other agencies are foreseen.
Implementation of the proposed action in discuss in Section D of the proposed guide.
VI.
Summary and Conclusion Revision 3 to Regulatory Guide 1.38 on quality assurance require-m nts for packaging, shipping, receiving, storage, and handling of items for nuclear power plants should be issued.
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