ML20023A523

Informs of Incorrect Info Contained in Third Paragraph of Encl 2 to 750331 Memo Re Facility Steam Generator Tube Rupture Incident.Corrected Paragraph Submitted

ML20023A523
Person / Time
Site:	05000000, Point Beach
Issue date:	04/09/1975
From:	Goller K Office of Nuclear Reactor Regulation
To:	Gallo J NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
Shared Package
ML19302F297	List: ML19302F296 ML20023A406 ML20023A413 ML20023A464 ML20023A465 ML20023A509 ML20023A510 ML20023A511 ML20023A512 ML20023A513 ML20023A514 ML20023A515 ML20023A516 ML20023A519 ML20023A521 ML20023A523 ML20023A525 ML20023A528 ML20023A529 ML20023A532 ML20071H278 ML20071H964 ML20071H968 ML20071H971 ML20071N278 ML20071N284 ML20071N287 ML20076B334 ML20076B338 ML20076B498 ML20076B501 ML20076B505 ML20076B509 ML20076B989 ML20077J897
References
FOIA-82-309 NUDOCS 8210070187
Download: ML20023A523 (2)

Text

______ __ ______

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w UNITED STATES NdCLEAR REGULATORY COMMISSION WASHINGTON, L.

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J. Gallo, Chief !! caring Counsel, OELD POINT BEACil UNIT 1 STEAh! GENERATOR TUBE RUPTURE INCIDENT Ffy note of F! arch 31, 1975 on the subject incident contained incorrect information in the third paragraph and in Enclosure 2.

Therefore, please delete Enclosure 2.

For the third paragraph, please substitute the following:

"The Point Beach Technical Specifications do not presently contain requirc-ments implementing Regulatory Guide 1.83, but the licensee has submitted a Technical Specification change request for inservice inspection of steam generator tubes which is now under review. The tube plugging limit of 30%

wastage which was used by the licensee, re;itive to the repair associated with the subject incident, is considered acceptable in view of the currently established limits of 35% for Prairie Island and 50% for Palisados.

The Point Beach Technical Specifications currently do not specifically limit primary to secondary Icakage, but they do limit overall primary system Icak-age to 10 GPl!.

F!oreover, if primary system Icakage exceeds 1 GPh!, the Technical Specifications require a follow-up evaluation of the safety impli-cations of the Icakage and a subsequent reactor shutdown if (1) the 1cakage is not evaluated to be safe, or (2) it-exceeds 10 GP.M.

This specification covers all primary system icakage cases including situations involving primary to secondary leakage. The acceptability and use of your suggested limit of 1 GPh! for primary to secondary leakage at Point Beach and other PliR's will be considered in discussions with Technical Review.

In this regard, R. >!accary et al have begun a review of Ph'R steam generator tube performance for all operating plants and will, with regard to Point Beach Unit 1, evaluate further the conditions and validity of its Technical Specifications.

At this time, our evaluation of actions taken by the licensee following f

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t' J. Gallo the subject incident and the appropriateness of current Technical Specifications leads us to conclude that no immediate licensing action is required."

/L/ l' Sd!L Karl R. Goller, Assistant Director for Operating Reactors Division of Reactor Licensing cc:

K. Kniel L. Kintner i

L. Frank S. Pawlicki J. Knight W llazelton G. Lear J. Wetmore 9

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