ML19262C480
| ML19262C480 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/31/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 8002140064 | |
| Download: ML19262C480 (1) | |
Text
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CENTRAL FILES UNITED ST ATE 3 PCR:HQ
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NUCLEAR REGULATORY COMMISSION LPOR 3.% # '
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.'r./l January 31, 1980 STATE Docket No. 50-267 Public Service Company of Colorado ATTN:
Mr. C. K. Millen Senior Vice President P. O. Box 840 Denver, Colorado 80201 Gentle =en:
The enclosed IE Circular No. 79-25, Supplement A, is forwarded to you for information.
No written response to this Circular is required.
If you have any questions related to the subject, please contact this office.
Sincerely, O
, f k l ';
I Karl V. Seyfrit
/
Director
Enclosures:
1.
Draft IE Circular No. 79-25 Supplement A 2.
List of IE Circulars Recently Issued cc:
D. W. Warembourg, Nuclear Production Manager Fort St. Vrain Nuclear Station P. O. Box 368 Platteville, Colorado 80651 L. Brey, Manager, Quality Assurance.
8002140 0 61 Q
SSINS No.:
6830 Accession No.:
UNITED STATES 7912190653 NUCIIAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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< q, c, WASHINGTON, D.C.
20555 e9 "d e, L ba L-IE Circular No. 79-25 Supplement A Date: January 31, 1980 Page 1 of 1 SHOCK ARRESTOR STRUT ASSEMBLY INTERFEPINCE On December 20, 1979, licensees and holders of construction permits for nuclear power reactors were advised by IE Circular No. 79-25 of a potential problem with Bergen-Paterson part 2540 Strut Assembly used in combinatfan with Pacific Scientific Company mechanical shock arrestors sizes 15K, 50K and 120K.
Bergen-Paterson has conducted a detailed review of their records and identified the following nuclear power plants as being affected by the above problec:
Shoreham #1 Three Mile Island #2 Shearon Harris #1, 2, 3, & 4 Watts Bar #1 Virgil C. Summer #1 Waterford #3 Limmerick #1 & 2 During the course of this investigation Bergen-Paterson identified an additional problem with the 2540-120 Shock Arrestor Strut Astiembly.
The assembly may not be acceptable for applications up to the published load of 120,000 lbs.
Preliminary load testing has indicated that the maximum accept-able load may be only 112,00J lbs.
All, nuclear power reactor licensees and holders of construction permits are advised to review their systems for any Bergen Paterson part 2340-120 Shock Arrestor Strut Assembly.
Application of these assemblies should be analyzed, existing calculations reviewed, and if necessary, recalculated to determine whether loads exceed 112,000 lbs.
Strut Assemblies for applicstions in excess of 112,000 lbs should be replaced by larger units or other acceptable resolution should be made.
IE Circular No. 79-25 Supplement A January 31, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date Issued To No.
Issued 79-20 Failure Of GTE Sylvania 9/24/79 All Power Reactor Relay, Type PM Bulletin Licensees with a 7305, Catalog SU12-11-AC Construction Permit (CP)
With A 120V AC Coil and/or Operating Licensee (OL) 79-21 Prevention of Unplanned 10/16/79 All holders of Power Releases of Radioactivity Reactor Operating Licenses (OLs) or Construction Permits (cps) 79-22 Stroke Times for Power 11/16/79 All Power Reactor Oper-Operated Relief Valves ating Facilities and all Utilities having a Construction Permit (CP) 79-23 Motor Starters and 11/26/79 All Power Reactor Oper-Contactors Failed to ating Facilities and Holders Operate of Reactor Construction Permits (cps) 79-24 Proper Installation and 11/26/79 All Holders of a Calibration of Core Spray Power Reactor Operating Pipe Break Detection License (OL) or Equipment on BWRs.
Construction Permits (cps) 79-25 Shock Arrestor Strut 12/20/79 All licensees and Assembly Interference holders of power reactor construction Permit (CP) 80-01 Service Advice for GE 1/17/80 All licensees of nuclear Induction Disc Relays power reactor operating facilities and holders of nuclear power reactor Construction Permits (cps)
Enclosure