ML19262C489
| ML19262C489 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8002140078 | |
| Download: ML19262C489 (1) | |
Text
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CENTRAL FILES PDR:HQ
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UNITED STATES NUCLEAR REGULATORY COMMISSION LPDR 3w REctoN iv AF 7
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January 31, 1980 Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
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,f duff & W Karl V. Seyfrit
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Director d
Enclosures:
1.
Draft IE Circular No. 79-25 Supplement A 2.
List of IE Circulars Recently Issued cc:
James P. O'Hanlon, Plant Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 80021'rd 7f
SSINS No.:
6830 Accession No.:
UNITED STATES 7912190658 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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' la IE Circular No. 79-25 Supplement A Date: January 31, 1980 Page 1 of 1 SHOCK ARRESTOR STRUT ASSEMBLY INTERFERENCE 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 combination with Pacific Scientific Company mechanical shock arrestors sizes ISK, 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 problem:
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 Assembly.
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 112,000 lbs.
All nuclear power reactor licensees and holders of construction permits are advised to review their systems for any Bergen Paterson part 2540-120 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 applications 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