ML19261E336
| ML19261E336 | |
| Person / Time | |
|---|---|
| Site: | Allens Creek File:Houston Lighting and Power Company icon.png |
| Issue date: | 06/11/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Eric Turner HOUSTON LIGHTING & POWER CO. |
| References | |
| NUDOCS 7907050561 | |
| Download: ML19261E336 (1) | |
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UNITED STATES y, %g," W/,g }
NUCLEAR REGULATORY COMMISSION y
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s ARLINGTON, TEX AS 76012 June 11, 1979 In Reply Refer To:
RIV Docket No.
50-466/IE Information Notice No. 79-14 Ur, ton Lighting and Power Company AITN:
Mr. E. A. Turner, Vice President Power Plant Construction and Technical Services Post Office Box 1700 Houston, Texas 77001 Centlemen:
This IE Information Notice is being issued to call to your attention an aspect of the Coc=ission's regulations which IE inspectors have found is not always being fully implemented. No written response is required.
If y1u have questions regarding this matter, please e.ontact me.
Sincerel,
' r1 V. Se' f rit y
Director
Enclosures:
1.
IE Information Notice No. 79-14 2.
List of IE Information Notices Issued in 1979 29 b'
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-14 Date: June 11, 1979 Page 1 or 1 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS Summa ry:
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 ar.d their support systems for Class IE electrical cables. This notice is being issued to all applicants for, and holders of ccustruction 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 Site Criteria, Part 100, Appendix A, define a t' safe shutdown earthquake," (SSE) and generally identify the structures, 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.I.
The following structures, syste:-, 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 withstand the effects of the SSE and remain functional. The pertinent quality assurance requirements of Appendix B to 10 CFR 50 should be applied to all activities affecting th-safety-related functions of these structures, systems and components."
"C.1.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 response to this information notice is required.
If you have questions regarding the matter, please contact the Director of the appropriate NRC Regional Office.
7906290214 M9 amet
IE Information Notice 79-14 June 11, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Info rma tion Subject Date Issued To Notice No.
Issued 79-01 Bergen-Paterson Hydraulic 2/2/79 All power reector Shock and Sway Arrestor facilities with an Operating License (OL) or a Construc-tion Permit (CP)
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79-02 Attempted Extortion -
2/2/79 All Fuel Facilities Low Enriched Uranium 79-03 Limitorque Valve Geared 2/9/79 All power reactor Limit Switch Lubricant facilities with an Operating License (0L) or a Construc-tion Permit (CP) 79-04 Degradation of Engineered 2/16/79 All power reactor Safety Features facilities with an Operating License (OL) or a Construc-tion Permit (CP) 79-05 Use of Improper Materials 3/21/79 All power reactor In Safety-Related Components facilitiec with an Operating License (OL) or a Construc-tion Permit (CP) 79-06 Stress Analysis of 3/23/79 All Holders of an Safet:-Related Piping Reactor Operating License (OL) or a Construction Permit (CP:
79-07 Rupture of Radwaste 3/36/79 All power reactor Tanks facilities with an Operating License (OL) or a Construc-tion Permit (CP)
Enclosure Page 1 of 2 b5 )'b
IE Information Notice No. 79-14 June 11, 1979 79-08 Interconnection of 3/28/79 All power reactor Contaminated Systems with facilities 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 Resin facilities with an Operating License (OL) 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a Construction Permit (CP) 79-11 Lower Reactor Vessel Head 5/7/79 All Holders of an Insulation Support 'roblem Operating License (OL) or a Construction Permit (CP) 79-12 Attempted Damage to New 5/11/79 All fuel facilities, Fuel Assemblies research reactors, and power reactors with an Operating Licensee (OL) or a Construction Permit (CP) 79-13 Indicatica of Low Water 5/29/79 All Holders of an Operating Level in the Oyster Creek Licence (GL) 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 Permit (CP) and applicants 79-15 Deficient Procedures 6/07/79 All power reactor facilities with an Operiting License (OL)'
or a Construction Pe rmit (CP)
Enclosure Page 2 of 2
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