ML19282A957
| ML19282A957 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/08/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 7903080425 | |
| Download: ML19282A957 (1) | |
Text
. e "fo UNITED STATES j
ug'o NUCLEAR REGULATORY COMMISSION f
[
'o REGION IV 5
E 611 RYAN PLAZA DRIVE,SulTE 1000 AR LINGTON, TEXAS 7%11 o
/
- +***
February 8,1979 In Reply Refer To:
RIV Docket No.
50-382/IE Bulletin No. 79-01 Louisiana Power and Light Co.
ATTN: Mr. D. L. Aswell Vice President of Power Production 142 Delaronde Street New Orleans, Louisiana 70174 Gentlemen:
Enclosed is IE Bulletin 79-01.
It requires action by you with regard to power re.ctor facilities with an operating license except for the 11 SEP plants which are listed in Enclosure 3.
This Bulletin is also being sent for infonnation to the 11 SEP plants and all power reactor facilities with a construction permit.
No action or written response is required for construction permit facilities or the 11 SEP plants.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, gik Karl V. Seyfrit Director
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 3.
List of SEP Plants (11) 7903080
UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-01 Date: February 8,1979 Page 1 of 3 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Description of Circumstances:
The intent of IE Circular 78-08 was to highlight to all licensees important lessons learned from environmental qualification deficiencies reported by individual licensees.
In this regard, licensees were requested to examine installed safety-related electrical equipment and determine that proper documentation existed which provided assurance that this equipment would function under postulated accident conditions.
The scope of IE Circular 78-08 was much broader than other previously issued Bulletins and Circulars (such as IEB 78-04 and IEB 78-02) which addressed specific component failures.
The intent of this Bulletin is to raise the threshold of IE Circular 78-08 to the level of a Bulletin; i.e., action requiring a licensee response.
Inspections conducted to date by the NRC of licensees' activities in response to IE Circular 78-08 have identified one component which licensees have found to be unqualified for service within the LOCA environment.
Specificially, unqualified stem mounted limit switches (SMLS), other than those identified in previously issued IE Bulletin 78-04, were found to be installed on safety-related valves inside containment at both Duane Arnold and Quad Cities 1 and 2 Nuclear Generating Stations.
The unqualified switches are identified as NAMC0 Models SL2-C-11, S3CML, !.A1-31, sal-32, D1200j, EA-700 and EA-770 switches. According to the manufacturer, these switches are designed only for general purpose applications and are not considered suitable devices for service in tle LOCA environment.
Consequently, switches are being replaced at th3 above power plants with qualified components.
Also, NRC inspection of component qualification has identified equip-ment which does not have documentation indicating it is qualified for the LOCA environment.
The inspections have also identified that the licensees' re-review and resolution of problem areas are not receiving the level of attention from all licensees which the NRC believes is warranted.
Because of the protracted schedule for completion of the re-review, we are now requesting the power reactor facilities with operating licenses to expedite completion of their re-review program or.Minally requested by IF Circular 78-08 dated May 31, 1978.
M 7902120225-