ML20148L663

Value/Impact Assessment for Reg Guide 1.136,Matl for Concrete Containments,Concludes That Guide Should Be Prepared

ML20148L663
Person / Time
Issue date:	11/09/1978
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
Shared Package
ML19220A221	List: ML20148L637 ML20148L663
References
REGGD-01.136, REGGD-1.136, NUDOCS 7811200322
Download: ML20148L663 (3)

Text

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i VALVE / IMPACT ASSESSMENT ON R.G. 1.136 b 0 70

" MATERIAL FOR CONCRETE 'NTAINMENTS" (ASME CODE SECTION III DIVISI6. 2, ARTICLE CC-2000)

1. The Procosed Action A. Description This guide provides information regarding the NRC's position on the acceptability for NRC licensing actions of Article .

l CC-2000 of the Code for Concrete Reactor Vessels and Contai ments published jointly by the American Society of Mechanical Engineers (ASME Boiler and Pressure Vessel Code,Section III, Division 2, 1977 edition) and the American Concrete Institute (ACI Standard 359-74) and addenda through the 1977 Winter Addenda to the Code.

In those areas in which the NRC finds provisions of the referenced Code inadequate for licensing purposes, supplementary guidelines are given in the regulatory position.

B. Need for the Proposed Action This guide will provide NRC reviewers and applicants a common basis of understanding of the NRC staff's minimum requirements ,

for materials for concrete containments, thus minimizing poten-tial materials.

for subjective interpretations on the degree of quality needed C. Value/ Impact of the Proposed Action 1.

NRC - Issuance and implementation of this guide will ensure that the quality of materials proposed for use in concrete containments will meet or exceed (at the appli-cant's discretion) the minimum requirements necessary to protect the public health and safety.

2. Other Government Agencies - None 3.

Industry - Most Code requirements have now been accepted by the industry and the NRC; therefore, the endorsement of these Code requirements would have no further impact as far as industry practices go. The industry will benefit from this guide because it will know what kinds of material are acceptable to the NRC staff. This win save time in the procurement of concrete containments. -

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D.

Public - No impact on the public can be foreseen Decision on the Proposed Action __

The proposed action should be undertaken II.

Procedural Approach A.

Alternatives

1. NRC Regulation

2. HUREG 3.

Branch Position

4. Regulatory Guide B.

Value/ Impact of Alternatives 1.

Vessels and Containments" c oris still in d and is experiencing rapid changes, it would not be suit to endorse the Code in a regulation ate.thisa time 2.

3.

NUREG - NUREGs are informational and contain n ositions.

a temporary measure untilo beaction is another alternative.

4. l

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Regulatory Guide - This proposed approach resolv es the t above comments in the most direct, manner. useful, e

and fle

C.

Decision on Procedural Approach ,

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theRegulatory action. Guide is the preferred method of acc .i omplishing I i

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1 III. Statutory Consideration A. NRC Authority This guide's authorization derives from the clarification. of General Design Criterion 1, " Quality Standards and Records," I of Appendix A, " General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, " Licensing of Production and Utilization Facilities," requiring, in part, that structures,  !

systems and components important to safety be designed, fabri-cated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed.

. B. Need for NEPA Assessment None IV. . Relationship to Other Existing or Proposed Regulations or Policies A. This will be the first guide in a series that will endorse ASME Code Section III Division 2.

B. No backfitting is required.

V. Summary and Lonclusion A. The Regulatory Guide should be prepared.

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