ML19224C381
| ML19224C381 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Hines E DETROIT EDISON CO. |
| References | |
| NUDOCS 7907020252 | |
| Download: ML19224C381 (1) | |
Text
e Tl0 ps adC UNI T E D STATES
(
[
g NUCLEAR REGULATORY COMMISSION
[
P( ; o REGION til 5
' f 799 ROOSEVELT ROAD m-E e
GLEN E LLYN. ILLINOIS 60137
/
JUN 111979 Docket No. 50-341 The Detroit Edison Company ATTN:
Mr. Edward Hines, Assistant Vice President and Manager Quality Assurance 2000 Second Avenue Detroit, MI 48226 Gentlemen:
This Information Notice is being issued to call to your attention 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,
- 5A James G. Kep br Director
Enclosure:
IE Information Notice No. 79-14 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Eugene B. Thomas, Jr.,
Attorney 269 153
'ID0702 0 Z b
i
U.S. ICCLEAR RECULATORY CO.9'.ISSION OFFICE OF INSPECTION AND EhTORCEMENT
/
REGION III June 11, 1979 IE Information Notice No. 79-11.
SATETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS 2
S m ry:
The NRC inspection staf f has found that in several cases, facilities under construction have not applied the pertinent quality assurance requirements of 30 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 teing issued to all applicants for, and holders of construction permits, to rc=ind them of the Co _ission's regulations on this subject.
Description of Circu= stances:
1.
In the Coc=ission'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 C - 4ssion's Pegulations 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 "Seis ic 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 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."
"C1.q.
The Class IE electric systems, including the auxiliary cyste=s for the on-site electric power supplies, that provide the emergency electric power..."
L vritten response to this luf i'
- estions regarding the matter, please DUPLICATE DOCUMENT C
h Fegional Office.
Entire document previously entered
,...oc hment: List of lE Information into system under:
1:atices Issued in 1979 l
No. of pages:
m