ML19261E339
| ML19261E339 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/11/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 7907050565 | |
| Download: ML19261E339 (1) | |
Text
hd
. J.e
","'?%g t$
o UNITED STATES Ej j
NUCLEAR REGULATORY COMMISSION L J[
j REGION IV
^
0,,,
8 611 dYAN PLAZA oRIVE, SUITE 1000 k, ' d #
,o#
AR LINGTON, TEXAS 76012 June 11, 1979 In Reply Refer To:
RIV Docket No.
50-382/IE Information Notice No. 79-14 Louisiana Power and Light Co.
ATIN:
Mr. D. L. Aswell Vice President of Power Production 142 Delaronde Street New Orleans, Louisiana 70174 Gentlemen:
This IE Infor=ation Notice is being issled to call to your attention an aspect of the Cocsission's regulations which IE inspectors have found is not always being fully implemented. No written respense is required.
If you have questions regarding this matter, plesse contact me.
Sincerely, 7
)
Karl V. Seyfr Director Ecclosures:
1.
IE Information Notice No. 79-14 2.
List of IE Information hotices Issued in 1979
- j. D
?90 ?O50sw
UNITED STATES NUCLEAR REGULATORY COMMISSION _
0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTC', D.C.
20555 IE Information Notice No. 79-14 Date: June 11, 1979 Page 1 of 1 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS Summary:
The NRC inspection staff has found that in several cases, facilities under construction have not applied the pertinent quality assurance requirements of 10 CFR 50, Appendix B to the design, procurement, and installation of cable trays and their support systems for Class IE electrical cables. This notice is being issued to all applicants for, and holders of construction permits, to remind them of the Commission's regulations on this subject.
Description of Circumstances:
1.
In the Commission's Regulations for Licensing of Production and Utilization Facilities - 10 CFR Part 50, Criterion 2 of Appendix A, states in part that " Structures, systems and components important to safety shall be designed to withstand the effects of.... earthquakes....without loss of capability to perform their safety functions...."
2.
The Commission's Regulations on Reactor Si'.e Criteria, Part 100, Appendix A, d2 fine a " safe shutdown earthquake," (SSE) and generally identify the atructures, systems and components which are required to remain functional during such an earthquake.
3.
Regulatory Guide 1.29 " Seismic Design Classification" states in pertinent part:
"C.1.
The following structures, systems and components of a nuclear power plant, including their foundations and supports (emphasis added) are designated as Seismic Category 1 and should be designed to withsta _3 the effects of the SSE and remain functional. The pertinent quality assurance recuirements of Appendix B to 10 CFR 50 should ba applied to all activitie s affecting the safety-related function: of - ase structures, systems and components."
"C.I.q.
The Class IE electric systems, including the auxiliary systems for the on-site electric power supplies, that provide the emergency electric power..."
No written responae to this information notice is requiret.
If you have cuestions regardi:rg the matter, please coatact the Director of the appropriate NRC Regional Offi:e.
T906890y34 y c,3
- a,,z c
s~r
' June 11, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Date Issued To Notice No.
Issued 79-01 Bergen-Paterson Hydraulic 2/2/79 All power reactar Shock and Sway Arrestor facilities with an Operating License (OL) or a Construc-tion Permit (CP) 79-02 Attempted Extortion -
2/2/79 All Fuel Facilities Low Enriched Uranium 79-03 Iimitorque Valve Geared 2/9/79 All power reactor Limit Switch Lubricant facilities with an Operating License (OL) or a Construc-tion Permit (CC' 79 04 Degradation of Engineered 2/16/79 All power reactor Safety Features facilities with an Operating License (0L) or a Construc-tion Permit (CP) 79-05 Use of Improper Materials 3/21/79 All power reactor In Safety-Related Components facilities with an Operating License (OL) or a Construc-tion Permit (CP) 79-06 Stress Analysis of 3/23/79 All Holders of an Safety-Related Piping Reacter Operating License (OL) or a Construction Pe rmit (CP) 79-07 Rupture of Radwaste 3/26/79 All power reactor Tanks facilities with an Operating License (OL) or a Co-tion Permit Enclosure Page 1 of 2 N.'>b[
IE Inicrmation Notice No. 79-14 June 11, 1979 r
79-08 Interconnection of 3/28/79 All powem reactor Contaminated Systems with acilities with an Service Air Systems Used Operating License As the Source of Breathing (OL) and Pu Proces-Air sing fuel facilities 79-09 Spill of Radioactively 3/30/79 All power reactor Contaminated Resia f acilities with an Operating License (OL) 79-10 Nonconforming Pipe 4/16/79 I. power reactor Support Struts racilities with a Construction Permit (C")
79-11 Lower Reactor Vessel Head 5/7/79 All Holders of an Insulation Support Problem Operating License (CL; or a Construction Permit 'lP) 79-12 Attempted Damage to New 5/11/79 All fuel facilities, Fuel Assemblies research reactors, and PF power reactors with an Operating Licensee (OL) or a Construction Permit (CP) 79-13 Indication of Low Water 5/29/79 All Holders of an Operating Level in the Oyster Creek License (OL) or a Reactor Construction Permit (CP) 79-14 Safety Classification of 6/11/79 All Power Reactor Electrical Cable Support facilities with a Systems Construction Pecmit (CP) and applicants 79-15 Deficient Procedures 6/07/79 All power reactor facilities with an Operating Licenst (OL) or a Construction Pe rmit (CP)
Enclosure 2 age 2 of 2 292 l't3