ML19276G607
| ML19276G607 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 06/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Coughlin J PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA |
| References | |
| NUDOCS 7907240233 | |
| Download: ML19276G607 (1) | |
Text
TIC gan asGg UNITEo STATES
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NUCLEAR REGULATORY COMMISSION f
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cLEN ELLYN, ILUNOIS 60137 M
Docket No. 50-546 Docket No. 50-547 Public Service of Indiana ATTN:
Dr. James Coughlin Vice President, Nuclear 1000 East Main Street Plainfield, IN 46168 Gentlemen:
This Information Notice ir being issued to call to your a"ention an aspect of the Commissions's regulations which IE inspectors have found is not always being fully implemented.
No written response is required.
If you have questions regarding this matter, please contact me.
Sincerely, Qk Y
// James G. &
w Keppfer Director
Enclosure:
IE Information Notice No. 79-14 cc w/ encl:
Mr. R. M. Brown, Construction Project Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC LeBoeuf, Lamb, Leiby & MacRae m
7907240933'
. e U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENTORCEMENT REGION III June 11, 1979 IE Information Notice No. 79-14 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS
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S m ry:
The NRC inspection staff has found that in several cases, facilities under construction have not applied the pertiner.t 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 c11 applicants for, and holders of construction permits, to re=ind them of the Com=ission'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 ef fects of.... earthquakes....without loss of capability to perform their safety functions...."
2.
The Cc==ission's Regulations on Reactor Site Criteria, Part 100, Appendix A, define a " safe shutdown earthquake," (SSE) and generally identify the structures, syste=s and components which are required to re=ain functional during such an earthquake.
3.
Regulatory Guide 1.29 " Seismic Design Classification" states in pertinent part:
"C.I.
The following structures, systems and components of a nuclear power plant, including their foundations and supports (emphasis added) are designated as Seis=ic Cater cy 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 the safety related functions of these structures, systems and components."
"C1.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 regardint the matter, please contact the Director of the appropriate NkC Regional Office.
Attachment:
List of IE Information Notices Issued in 1979 7906290214
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IE Information Notice No. 79-14 Enclosure June 11, 1979 Page 1 of 1 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Date Issued To Notke No.
Issued 79-01 Bergen-Paterson Hydraulic 2/2/79 All power reactor Shock and Sway Arrestor facilities with an OL or a CP 79-02 Attempted Extortion -
2/2/79 All Fuel Facilities Low Enriched Uraniu:
79-03 Limitorque Valve Geared 2/9/79 All power reactor Limit Switch Lubricant facilities with an OL or a CP 79-04 Degradation of 2/16/79 All power reactor Engineered facilities with an Safety Features OL or a CP 79-05 Use of Improper Materials 3/21/79 All power reactor in Safety-Related Componenti.
facilities with an OL or CP 79-06 Stress Analysis of 3/23/79 All Holders of Safety-Related Piping Reactor OL or CP 79-07 Rupture of Radwaste Tanks 3/26/79 All power reactor facilities with an OL or CP 79-08 Interconnection of 3/28/79 All power reactor Contaminated Systems with facilities with an Service Air Systems Used OL and Pu Processing As the Source of Breathing fuel facilities Air 79-09 Spill of Radioactively 3/30/79 All power reactor Contaminated Resin facilities with an OL 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a CP O