ML20138H703

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Intervenor Exhibit I-CCANP-84,consisting of Response to Quadrex Finding 4.8.2.1(g), Radiological Control Technical Adequacy Assessment. Finding Erroneous.Inappropriate Design Document for Structural Criteria Referenced
ML20138H703
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 07/16/1985
From:
BROWN & ROOT, INC. (SUBS. OF HALLIBURTON CO.)
To:
References
OL-I-CCANP-084, OL-I-CCANP-84, NUDOCS 8510290126
Download: ML20138H703 (1)


Text

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0L f' 00/}h-RADIOLOGICAL CONTROL QUADREX FINDING NO.

4.8.2.1/9)

TECHNICAL ADEQUACY ASSESSMEN T'

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~3sc The following findings may have a sarious impact on plant licensability or deserve licensing attention:

  • 85 0CT -4 All :17 "A design basis governing removable corg).e;..: yg ;

(g) walls was not evident (see Question R-11 33 @ g BROWN & RESPONSE Brown & Root disagrees with the above finding.

Given the placement of this finding in Section 4.8 of the Quadrex Report, it is assumed that Quadrex is stating that Brown L Root did not have a basis governing shielding requirements for removable concrete 4[ design walls.fThis statement is erroneous because the B rown L Root General Structural Design Criteria, which were in place at the time of the Quadrex review, include such a design basis and require consideration of shielding e

concrete walls are used./ Section 4.5.1 of ff0f reg _uirenients_wh_en removableThe General Structural'Disign Criteria 5A369SD00 requirements for materials to be used in removable walls.

The Brown L Root shielding personnel provided input to the Structural Discipline during development of these requirements. The masonry block density was considered in the shielding calculations to determine the required thicknes-of the removable walls.

Section 7.3 of the above referenced criteria document contains the requirements for seismic restraints of removable walls.

Quadrex seems to have based this finding on the Radiation Shielding TRD A509NQ00:.

However, that TRD is not the appropriate design basis document for structural criteria; the above referenced General Structural Design Criteria document is the one that controls design in this area.

Given these facts, it is evident that the above finding is erroneous and will have no impact on plant licensability.

NUCLEAR REGULATORY COMf484540M cocket No.

Official Enh. Me.

la the matter of G E S T:FlZ._ __l Shif 1;plicani RECEIVED l

fniervoer REJECTED CC9/J[ N 37 f

Ornt's Offt

,onarnter DATE 4 ther Witmen Ilocorter 2-202 8510290126 850716 PDR ADOCK 05000498 t

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