ML20203D720

Forwards Jj Rivard Internal Memo Re Audit of Facility Train C Conduit Program at Impell Corp Walnut Creek,Ca Ofc

ML20203D720
Person / Time
Site:	Comanche Peak
Issue date:	07/02/1986
From:	Landers D TELEDYNE ENGINEERING SERVICES
To:	Jeng D NRC
References
6410-68, NUDOCS 8607210273
Download: ML20203D720 (2)

Text

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Mr. David Jeng @l / r/A> '

- 52 United States Nuclear Regulatory Commission Phillips Building Mail Stop 316 7920 Norfolk Avenue Bethesda, MD, 20814

Subject:

Audit of Comanche Peak Train C Conduit Program

Dear Mr. Jeng,

Attached is an internal TES memo concerning the subject audit.

If you have any questions do not hesitate to contact Mr. Rivard or the writer. .

Very truly yours, ,

TELEDYNE ENGINEERING SERVICES I

Donald F. Landers President l

DFL:mid attachment cc: V. Noonan (NRC)

.C. Tramell (NRC) / ,

A. Vietti-Cook (NRC) 1 G. Bagchi (NRC) 6410 File 1

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- WTA prVNE MEMORANDUM ENGINEERING SERVICES T0: D. F. Landers FROM: J. J. Rivard DATE: July 2, 1986 PROJECT: 6410C .

SUBJECT:

Audit of Comanene Peak Train C Concuit Program at Imoell Corporation's Walnut Creek, CA Office Attached is a copy of the Trip Report written by Giuliano DeGrassi of Brookhaven National Lacoratory. The Trip Report consists of an outline of the audit discussions. Specific areas included: A review of the program status, an outline of Impell's review of Ebasco, and Gibbs and Hill analyses and Impell's response to NRC, TERA and CYGNA technical issues raised. In addition is a list of Action Items defined to close out the methodology audit.

The following concerns the proposed resolution to some Action Items. ,

Action Item 2 This concern was raised by the NRC review team. The concern was whether 4% damping for OBE level loading and 7% for SSE are appropriate for conduit supports with Unistrut-type supports instead of the lower yalues used for piping systems. The basic question is whether the intent of Regulatory Guide 1.16 is met. Regulatory Guide 1.61 calls for 4% damping for OBE level loading and 7% for SSE for bolted structures. In Impell's presentation of their justification of these damping values, they list other plants which used 4% and 7% damping for conduit with similar Unistrut supports. If in f act these damping values are acceptable at other nuclear plants (I believe they are), the only justification required should be to verify this in addition to verifying that the conduit supports at these plants are similar to those at Comanche Peak.

Action Item 3 The NRC review team raised a concern for the TUGC0 and Impell proposal to use a Factor Safety of 3 for Hilti Bolts for the " Train C" conduit supports. Since the capacity of any expansion anchor is very

'dapendent upon its installation, it is the opinion of the author that before this can be considered, the two things which must be established are the following:

1. What procedure were these Hilti's installed to?

2. Were the Hilti installations subject to QC inspection?

JJR:jej