ML16224A056

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Proposed Draft Regulatory Guides, DG-1023, Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less than 50 Ft-Lb, and DG-1025, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
ML16224A056
Person / Time
Issue date: 07/15/1993
From: Wilkins J
Advisory Committee on Reactor Safeguards
To: Taylor J
NRC/EDO
References
D930715
Download: ML16224A056 (1)


Text

D930715 Mr. James M. Taylor Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Taylor:

SUBJECT:

PROPOSED DRAFT REGULATORY GUIDES, DG-1023, "EVALUATION OF REACTOR PRESSURE VESSELS WITH CHARPY UPPER-SHELF ENERGY LESS THAN 50 FT-LB," AND DG-1025, "CALCULATIONAL AND DOSIMETRY METHODS FOR DETERMINING PRESSURE VESSEL NEUTRON FLUENCE" During the 399th meeting of the Advisory Committee on Reactor Safeguards, July 8-9, 1993, we discussed the subject draft regulatory guides. Our Subcommittee on Materials and Metallurgy examined these guides in detail at a meeting on June 29, 1993.

During these meetings, we had the benefit of discussions with representatives of the NRC staff. We also had the benefit of the document referenced.

The need for these proposed guides was highlighted during the evaluation of the integrity of the Yankee Rowe reactor pressure vessel. We believe that these guides should prove useful to the licensees and regulatory authorities, and recommend that they be issued for public comment. We would like an opportunity to review the proposed final version of these guides after the public comments have been reconciled and before they are published in final form.

Sincerely, J. Ernest Wilkins, Jr.

Chairman

Reference:

Memorandum dated June 10, 1993, from Lawrence C. Shao, Office of Nuclear Regulatory Research, for John T. Larkins, ACRS,

Subject:

Request for ACRS Review of Proposed Draft Regulatory Guides, with enclosures:

DG-1023, "Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less than 50 ft-lb," and DG-1025, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence"