ML19263E470
| ML19263E470 | |
| Person / Time | |
|---|---|
| Site: | 05000363 |
| Issue date: | 04/16/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 7906180389 | |
| Download: ML19263E470 (1) | |
Text
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- 88009 UNITED STATES g
NUCLEAR REGULATORY COMMISSION E
REGION I Is f
$31 PARK AVENUE KING OF PRUS$1 A. PENNSYLVANI A 19406 April 16, 1979 Docket No. 50-363 Jersey Central Power & Light Company ATTN:
Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Gcntlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular, Bulletin or NRR Generic Letter will be issued to recommend or request specific licensee actions.
If you have questions reatrding the matter, please contact this office.
Sincerely,
./W.
Boyce H. Grier
' Director
Enclosures:
1.
IE Information Notice No. 79-10 2.
List of Information Notices Issued in 1979 cc w/encls:
M. K. Pastor, Project Manager 2355 001 7906180389
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-10 Date: April 16, 1979 Page 1 of 2 NONCONFORMING PIPE SUPPORT STRUTS Description of Circumstances:
Bergen-Paterson Pipesupport Corporation informed the NRC that a limited quantity of its Part 2000 Rigid Rod Struts do not meet the published design criteria.
Subsequent plant inspection by the NRC indicated that no nonconforming Part 2000 Rigid Rod Struts are installed in operating units.
However, the following construction sites were identified as receiving nonconforming struts:
Summer No. 1 Unit Shoreham Grand Gulf No. 1 and 2 Units Wolf Creek No. 1 Unit Callaway No. 1 Unit Waterford No. 3 Unit St. Lucie No. 2 Unit Washington Nuclear No. 2 Unit Zininer No.1 Unit The actual load rating of Part 2000 Rigid Rod Struts varies with the material used for rods in the assembly.
At various times this rod was made from SA-36, SA-306, grade 60 and A-108 grade 1018 materials. Re-analysis indicates that the use of A-108 grade 1018 produces a product meeting all published criteria for all sizes; however, the use of either SA-36 or SA-306, grade 60 materials produces an acceptable material only for sizes 1.5 and 3 but not for sizes 10 and 20.
All construction permit holders should consider conducting a review to determine if Bergen-Paterson Pipesupport Corporation Part 2000 Rigid Rod Struts of the sizes 10 and 20 are being used at their construction sites.
If so, detennine if those in stock and installed meet the required design criteria.
2355 002 7906060153 hk
IE Information Notice No. 79-10 Date: April 16, 1979 Page 2 of 2 This information is provided as a notification of a possibly significant matter.
It is expected that recipients will review the information for possi.ble applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Enclosure:
List of IE Information Notices Issued in 1979 2355 003
IE Information Notice No. 79-10 Date: April 16, 1979 Page 1 of 1 LIST OF IE INFORMATION NOTICES ISSUED Ih 1979 Information Subject Date Issued To Notice No.
Issued 79-01 Bergen-Paterson Hydraulic 2/2/79 All power reactor Shock and Sway Arrestor facilities with an Operating License (0L) or a Construction Permit (CP) 79-02 Attempted 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 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 Components facilities with an OL or CP 79-06 Stress Analysis of 3/23/79 All power reactor Safety-Related Piping facilities with an 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 facilties Air 79-09 Spill of Radioactively 3/30/79 All power reactor Contaminated Resin facilities with an OL 2355 004