ML19249C141

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Forwards IE Bulletin 79-02,Revision 1,Suppl 1, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. No Action Required
ML19249C141
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 08/20/1979
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO.
References
NUDOCS 7909070486
Download: ML19249C141 (1)


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UNITED STATES Th E y)'y,( (j NUCLEAR REGULATORY COMMISSION

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631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-213 MS20 A Connecticut Yankee Atomic Power Company ATTN:

Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Gentlemen:

Enclosed is IE Bulletin No. 79-02, Revision 1, Supplement No. 1, which clarifies NRC positions on actions requested with regard to your power reactor facility (ies) with an operating license.

Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.

Sincerely,

&W, h4nu g Boyce H. Grier 01 rector

Enclosures:

1.

IE Bulletin No. 79-02, Revision No. 1 (Supplement No. 1) 2.

List of IE Bulletins Issued in Last Six Months cc w/encls:

R. Graves, Plant Superintendent D. G. Diedrick, Manager of Quality Assurance J. R. Himmelwright, Licensing Safeguards Engineer 92.7264 7909 070g -

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ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.

20555 IE Bulletin No. 79-02 Revision No. 1 (Supplement No. 1)

Date:

August 20, 1979 Page 1 of 2 PIPE SUPPORT BASE PLATE DESIGNS USING CONCRETE EXPANSION ANCHOR BOLTS Description of Circumstances:

The supplement to IE Bulletin No. 79-02 is intended to establish criteria for the evaluation of interim acceptability of plant operation with less than the design factors of safety for piping supports due to as-built problems, under design, base plate flexibility, or anchor bolt deficiencies.

In the reviews for system operability of the Duane Arnold and Crystal River facilities, criteria have been developed by the NRC staff that define pipe support operability.

The criteria have been applied in lieu of other analysis or evaluation.

Specifically, the licensees identifiei problems with pipe supports in which the original design factors of safe".y were not met but some lesser margin was available.

The design margins of four or five are intended to be final design and installation objectives but systas may be classed as operable on an interim basis with some lesser margin providing a program of

estoraticn to at least the Bulletin factors of safety has been developed.

Facilities which fall outside the operability criteria are considered to probably require a Technical Specification exception and will require review on a case by case basis.

Action to be Taken by Licensees:

For the following two cases, plant operation may continue or may begin:

a.

For the support as a unit, the factor of safety compared to ultimate strengths is less than the original design but equal to or greater than two.

b.

For the anchor bolts the factor of safety is equal to or greater than two and for the support steel the original design factor of safety compared to ultimate strengths is met.

The above criteria may be applied provided

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i graded to design margins of safety expedit DUPLICATE DOCUMENT OM b) supports and by the next refueling for non,'

is as defined in Bulletin No. 79-14 where those areas of the plant which can be ente Entire document previously entered into system under:

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J h/( O/& Y No. of pages:

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