ML19261E338
| ML19261E338 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/11/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7907050563 | |
| Download: ML19261E338 (1) | |
Text
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o UN;TED STATES
[y' ^7,(y 'n, NUCLEAR REGULATORY COMMISSION
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c E REGION IV 8
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611 RYAN PLAZA oRIVE, SUITE 10C0 E
,o ARLINGioN, TEXAS 76012 June 11, 1979 In Reply To:
RIV Docket No. STN 50-482/IE Information Notice No. 79-14 Kr.asas Gas & Electric Co.
Attn:
Mr. Glanc L. Koester Vice President-Operations Post Office Box 208 Wichita, Kansas 67201 Gentleaen:
This lE Infor=ation Nacice is being issued to call to your attention an aspect of the Cocaission'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, h
$U Karl V. Seyfrit Director
Enclosures:
1.
IE Information Notice No. 79-14 2.
List of IE Infor=ation Notices Issued in 1979 cc: Nicholas A. Petrick, SNUPPS D, T. McPhee, Kansas City Power and Liebt Cc-n r Gerald Chai.uoll,,;.
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' L :. ma, h tts a ltoworidge Z. W. Creel, Kansas Gas and Electric Company 291 53 7907050563
UNITED STATES NUCLEAR REGULATORY COMMISSION _
0FFICE OF INSPECTION AND ENFORCEMENT WA::'INGTON, D.C.
20555 IE Information Notice No. 79-14 Date: June 11,1979 Page 1 of 1 SAFETY CLASSIEICATION OF ELECTRICAL CABLE SUPPORT SYSTFl!S Summary:
The NRC inspection staff has found that in several cases, facilities under construction have not applied the pertinent quality assurance requirements cf 10 CFR 50, Appendix B to the design, procurement, and installation of cable trays and their support systems for Class IE electrical caoles.
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 Site Criteria, Part 100, Appendix A, define a " safe shutdavn 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.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 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."
"C.1.q.
The Class IE electric systems, including the auxiliary systems for the on-site electric power supplies, that provide the e=ergency 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 b J3
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IE Information Notit: 79-14
,,,_ June 11, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979
~
Information Subject Date Issued To Notice No.
Issued 79-01 Bergen-Patersoa Hydraulic 2/2/79 All power reactor Shock and Sway Arra. tar facilities with an Operating License (OL) or a Construc-tion Permit (CP) 79-02 Atte=pted 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 (OL) or a Construc-tion Permic (CP) 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 pcwer reactor In Safety-Related Components facilities with an Operating License (OL) or a Construc-tion Pccmit (CP) 79-06 Stress Analysis of 3/23/79 All Holders of an Safety-Related Piping Reactor Operating License (OL) or a Construction Permit (CP) 79-07 Rupture of Radwaste 3/26/79 All power reactor Tanks facilities with an Operating License (OL) or a Construc-c.t;n Pernit (CP)
Enclosure Page 1 of 2 Y
b0
IE Information Notice No. 79-14
,, J3ine 11, 1979 79-08 Interconnection of 3/28/79 All power -reactor Contaminated Systecs 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 f..cilities with a Construction Permit (CP) 79-11 Lower Reactor Vessel Head 5/7/79 All Holders of an Insulation Support Proble Operating License (OL) or a Construction Permit (CP) 79-12 Attempted Damage tc New 3/11/79 All fuel facilities, Fuel Assemblies research reactors, and 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).
19-14 Safety Classification of 6/11/79 All Power Reactor Electrical Cable Support facilities with a Systems Construction Permit (CP) and applicants
'9-15 Deficient Procedures 6/07/79 All power reactor facilities with an Operating License (OL) or a Construction Permit (CP)
Enclosure Page 2 of 2
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