ML19224C375
| ML19224C375 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 06/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7907020242 | |
| Download: ML19224C375 (1) | |
Text
'
TIC pa nicg UNITED STATES g
NUCLEAR REGULATO3Y COMMISSION
'P
^,
y 73 REGloN IH E
ctEN EttvN. stusois sois7 g
3 JUN 11 1979 Decket No. 50-358 Cincinnati Gas and Electric Company ATTN:
Mr. Earl A. Borgmann Vice President Engineering Services and Electric Production 139 East 4th Street Cincinnati, OH 45201 Gentlemen:
This Information Notice is being issued to call to your attention an aspect of the Commissions's regulations which IE inspectors base found is not always being fully implemented. No written response is required.
If you have questions regarding this matter, please contact me.
Sincerely, James G. Kepp er Director
Enclosure:
IE Information Notice No. 79-14 cc w/ encl:
Mr. J. R. Schott, Plant Harold W. Kohn, Power Superintendent Siting Commission Central Files Citizens Against a Radioactive Director, NRR/DPM Environment Director, NRR/ DOR Helen W. Evans, State of PDR Ohio Local PDR NSIC TIC
' - ~
~269 134 7907020fyg
e U.S. NUCLEAR REGULATORY COW.ISSION OFFICE OF INSPECTION AND ENFORCEMENT
/
REGION III June 11, 1979 IE Information Notice No. 70-11.
SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS Su=ary :
The NRC inspection staff has found that in several cases, facilities under construction have not aaplied 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 re=ind them of the Comission's regulations on this subject.
Description of Circumstances:
1.
In the Comission'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 perfore their safety functions...."
2.
The C - 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.1.
The following strtetures, systems and components of a nuclear power plant, including their founda;; ions 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, syste=s and components."
"C1.q.
The Class IE electric systems, inclucing the auxiliary cystems for the on-site electric power supplies, that provide the emergency electric power..."
~~ ~ ' ~ ~ ~ '
L vritten response to this information
~~
--=- -
restions regarding the matter, pleaca DUPLICATE DOCUMENT e
Regional Office.
<q Entiredocumentprevokilyehered
.e eochsent: List of *;E Information into system under:
Notices Issued in 1979 h
d ANO No. of pages:_
Q V.
e e
e