ML19225C749

From kanterella
Jump to navigation Jump to search
Forwards IE Bulletin 79-14,Revision 1, Seismic Analysis for As-Built Safety-Related Piping Sys
ML19225C749
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 07/18/1979
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Eric Turner
HOUSTON LIGHTING & POWER CO.
References
NUDOCS 7908020395
Download: ML19225C749 (1)


Text

._.

l h l-

.y n,4

\\

UNITED ST ATES f...

.y; i NUCLE AR REGUL ATORY COT.1T.11SSION

$, (, " E 5

REGIO *J IV

,'t_, A [ [

611 RY ATJ PL AZ A D A VE. 0UIT E 1C00 AR Ll?.GTC N, TE X A3 76012

/

+

.,uly 18, 1979 In Repl-f Ref er To:

RIV Docket Nos. 50-493/IE Eulletin No. 79-14 53-499/IE Eulletin No. 79-14 Revision 1 Houston Lighting & Power Company ATTN:

Mr. E. A. Turner, Vice President Power Plart Construction and Technical Services Post Of fice Box 1700 Houston, Texas 77001 Gentlemen:

IE Bulletin 79-14 is revised to lin.it the scope of work required. The changes are indicated.on the enclosed replace ent pag 2 for the bulleti.n.

If you desire additiona.1 information regarding this =atter, please contact this office.

Sincerely,

/

,7 1

w,,a n { c( 4L /acc ~-

U jKarl V.

Seyrrit

' Direc:or Encic;ure:

IE Eclie in No. 79-14 Re. sica 1 ZJ pc 790802ca95 "JJ 31 l

s II Eulletin No. 79-14 Revision 1 Date:

July 13, 1979 Page 2 of 3 Action to be taken by Licensees and Permit Holders:

All power reactor facility licensees and construction permit holders are regtested to verify, unless verified to an equivalent degrea within the last 12 months, that the seismic analysis applies to the actual configura-tion of sa fety-related piping systeas. The safety-related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic Design Classification,' Revision 1, dated August 1, 1973 or as defined in the applicable FSA2.

The action items that follow apply to all safetv-related piping 2-1/2-inches in diameter and greater and to scismic Cate?ory I pipint, re72rdless of size which was dynamically analyzed by ccaputer.

For older plants, unere Seisaic Category I requirecents did nce exist at the tice of licensing, it must be shown that the actual configuration nf iEdid safety-related systems, utilining piping 2-1/2 inches in diameter and greater, meets design require-cents.

Specifically, each licensee is requested to:

1.

Identify inspection elecents to be used in verifying that the seismic analysis input information conforms to the actaal configuratica of safety-related systems.

For each safety-related system, submit a list of desian documents, including title, identification number, revision, and date, ubich were scurces of input information for the seismic analyses. Also submit a description of the seismic analysis input information which is contained in each document.

Identify systems or porticas of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3.

Submit all of this infor=atien within 30 days of the date of this bulletin.

2.

For portions cf systems which are normall'y accessible *, inspect ene system in each set of redandant systems and all nearedundant systems for con-formance to the seismic analysis input infaraation set forth in design documents.

Include in the inspection: pipe run secretry-support and restraint design, locaticas, functisa and clearance (including floar and wall pen tratica); embed 2ents (excluding thsse covered in IE Eulletin 79-02); pipe attachments and valve and valve operator locations and weights (excluding those covered in IE Eulletin 79-04).

Within 60 days of the date of this bulletin, submit a descri; tion of tne results of this inspection.

Where nonconformances are !cund hich affect operability of any system, the licensee will expedite cacpletion of the inspection described in Item 3.

5ccmall, acccasible refers to thcce arcas of the plant which can be entered during reactor operation.

-j]

~ ' ?.

,r~

_im o0130 r

7907o