ML20134K403

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Staff Requirements Memo Re 970122 Briefing by NRC Staff & Representatives from ASME & IEEE in Rockville,Md on Codes & Standards
ML20134K403
Person / Time
Issue date: 02/12/1997
From: Hoyle J
NRC OFFICE OF THE SECRETARY (SECY)
To: Thompson H
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
References
REF-10CFR9.7 M970122A, NUDOCS 9702130288
Download: ML20134K403 (2)


Text

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UNITED STATES o

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 z

,o Fabruary 12, 1997 IN RESPONSE, PLEASE REFER TO:

M970122A OFFICE OF THE SECRETARY

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MEMORANDUM TO:

Hu h L. Thompson, Jr A

i g Ex cutive Director for Operations M

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FROM:

J hn C.

o le, Secretary

SUBJECT:

TAFF REQUIREMENTS - BRIEFING ON CODES AND i

STANDARDS, 10:00 A.M.,

WEDNESDAY, JANUARY 22, 1997, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN g'

TO PUBLIC ATTENDANCE)

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The Commission was briefed by the NRC staff and representatives from the American Society of Mechanical Engineers (ASME) and the Institute of Electrical and Electronics Engineers (IEEE) on the use of consensus codes and standards.

The Commission requested that the staff identify those plants which have reactor vessels or safety-related piping syrcems that do not fall under the design rules of ASME Code Section III and identify the design rules or Codes that do apply, characterize the significant differences between ASME Code Section III and ANSI /ASME Codes B.31.1 and B.31.7, and describe any inspection inconsistencies that could arise from the use of these differing standards.

(EDO)

(SECY Suspense:

4/25/97)

The staff should discuss the applicability of ASME Code Section III or other design / construction Codea of Record to operations, in particular, to those attributes that may not be addressed by the relevant Code requirements referenced in paragraphs (f) and (g) of 10 CFR 50.55a, and address the nature of design / construction Code requirements in the context of operations and the current licensing basis of operating plants.

The ASME Code is a product of a consensus process.

The staff should discuss its rationale for applying backfit considerations when endorsing later editions of the ASME Code that would allow licensees to selectively determine which requirements are applicable to their facilities, since the bases of many relaxations in one portion of the Code may be a result of consensus agreement for increased requirements in other portions m

of the Code.

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(OGC)

(SECY Suspense:

4/25/97) 130073 g

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9702130288 970212 PDR 10CFR PT9.7 PDR

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The Commission urged the staff to improve the nimaliness to complete NRC endorsement of new editions or rerisions to previously endorsed codes and standards, where appropriate.

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cc:

Chairman Jackson Commissioner Rogers Commissioner Dicus Commissioner Diaz Commissioner McGaffigan OGC OCA OIG Office Directors, Regions, AChS, ACNW, ASLBP (via E-Mail)

PDR - Advance DCS - P1-24

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