ML19305B072

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Forwards IE Circular 79-25,Suppl a, Shock Arrestor Strut Assembly Interference. No Written Response Required
ML19305B072
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 01/31/1980
From: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Hancock J
FLORIDA POWER CORP.
References
NUDOCS 8003190102
Download: ML19305B072 (1)


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UNITED STATES y

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ATLANTA, GEORGIA 30303 In Reply Refer To:

JAN 31 19E0

JEQ 50-302 j Florida Power Corporation Attn:

J. A. Hancock, Director Nuclear Operations P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 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, J

a g/ James P. O Rei11y Director i

Enclosures:

1.

IE Circular No. 79-25 Supplement A 2.

List of IE Circulars Recently Issued h

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8003190\\0 1 u

JAN 311250 Florida Power Corporation 5 cc w/eacl:

D. C. Poole Nuclear Plant Manager Post Office Box 1240 Crystal River, Florida 32629 e

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UNITED STATES-7912190658 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 January 31, 1980 IE Circular No. 79-25 Supplement A 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 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 problem:

Shoreham #1 Three Mile Island #2 Shearon Harris #1, 2, 3, & 4 Watts Bar #1 Virgil Summer #1 Waterford #3 Limmer.-t #1 & 2

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During tbs course of this investigation Bergen-Paterson identified an ad11tional problem with the 2540-120 Shock Arrestor Strut Assembly. The assembly nay 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 Arrester 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 Assc=blies for applications in excess of 112,000 lbs should be replaced by larger units or other acceptable resolution should be made.

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IE Circular No. 79-25 Supplement A Enclosure January 31, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date of Issued to No.

Issue 80-02 Nuclear Power Plant 2/1/80 All holders of Reactor Staff Work Hours OLs including research and test reactors, and cps 80-01 Service Advice for GE 1/17/80 All licensees of Induction Disc Relays nuclear power reactor operating facilities and holders of nuclear power reactor cps 79-25 Shock Arrestor Strut 12/20/79 All licensees and holders Assembly Interference of power reactor cps 79-24 Proper Installation and 11/26/79 All Holders of a Power Calibration of Core Spray Power Reactor OL or CP Pipe Break Detection Equipment on BWRs.

79-23 Motor Starters and 11/26/79 All Power Reactor and Contactors Failed Operating Facilities to Operate and Holders of Reactor cps 79-22 Stroke Times for Power 11/16/79 All Power Reactor Operated Relief Valves Operating Facilities and all Utilities having a CP 79-21 Prevention of Unplanned 10/19/79 All holders of Power Releases of Radioactivity Reactor OLs and cps 79-20 Failure of GTE Sylvania 9/24/79 All holders of Power Relay, Type PM Bulletin Reactor OLs and cps 7305, Catalog SU12-11-AC with a 12V AC Coil 79-19 Loose Locking Devices 9/13/79 All Holders of Power on Ingersoll-Rand Pumps Reactor OLs and cps 79-18 Proper Installation of 9/10/79 All Holders of Power Target Rock Safety-Relief Reactor OLs and cps 1

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