ML19225C759
| ML19225C759 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/18/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 7908020402 | |
| Download: ML19225C759 (1) | |
Text
,
f!)F A RIGg.
Y*
UNITED STATES 8 "[3 7'W' [g (f j NUCLEAR REGULATORY COMMISSION
- 7. J '
. C REGION IV S
k, r# [
611 RYAN PLAZA DRIVE, SUITE 1000
%, ' ' '. d' AR LINGToN, TE XAS 70012
+...
July 18, 1979 In Reply Refer To:
RIV Docket Nos.
50-445/IE Bulletin No. 79-14 50-446/IE Bulletin No. 79-14 Revision 1 Texas Utilities Generating Company ATTN:
Mr. R. J. Gary, Executive Vice President and General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlenen:
IE Bulletin 79-14 is revised to limit the scope of work required. The changes are indicated on the enclosed replacement page for the bulletin.
If yoit desire additional in or=ation regarding this matter, please contact this office.
Sincerely, 7
L a4 te c </s" s u]
d
,IgsarlV.Seyfrit Director
Enclosure:
IE Bulletin No. 79-14 Revision 1
'l 435 001 7908020402
IE Bulletin No. 79-14 Revision 1 Cate: July IS, 1979 Page 2 of 3 Action to be taken by Licensees and Permit Holders:
All power reactor facility licensees and construction permit holders are requested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis.pplies ta the actual configura-tion of safety-related piping syste=s.
ihe 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 FSAR. The action items that follow aoply to all safetv-related pioing 2-1/2-inches in diameter and greater and to seismic Cateecry I piping, regardless of sine which was dynamically analyned by cceputer.
For older plants, where Seismic Category I requirements did not exist at the time of licensing, it must be shown that the actual configuration of ff.df/ safety-related systems, utilining uiping 2-1/2 inches in diameter and greater, meets design require-cents.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying that the seismic analysis Input information conforms to the actual configuration of safety-related systeas. For each safety-related systea, submit a list of design documents, including title, identification number, revision, and date, which were sources of input information for the seismic analyses.
Also submit a description of the seismic analysis input information which is contained in each document.
Identify syctecs er portions of systems which are planned to be inspected during each seq"ential inspection identified in Items 2 and 3.
Subait all of this information within 30 days of the date of this bulletin.
2.
For portions of systems which are cc.nally accessibic*, inspect one system in each set of redundant systems and all nonredundant systeas for cen-for=ance to the seismic analysis input information set forth in design documents.
Include in the inspection: pipe run ge:cetry; support and restraint design, locations, function and clearance (including floor and wall penetration); embedments (excluding those ccvered 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 description of the results of this inspection.
Where nonconformances are found which affect operability of any system, the licensee will expedite completion of the inspection described in Item 3.
- Nor= ally accessible refers to those areas of the plant which can be entered during reactor operation.
435 002 7907250430