IE Circular No. 79-04, Loose Locking Nut on Limitorque Valve Operators
CR79004 March 13, 1979 MEMORANDUM FOR: B. H. Grier, Director, Region I J. P. O'Reilly, Director, Region II J. G. Keppler, Director, Region III K. V. Seyfrit, Director, Region IV R. H. Engelken, Director, Region V FROM: Norman C. Moseley, Director, ROI, IE SUBJECT: IE CIRCULAR CO. 79-04, LOOSE LOCKING NUT ON LIMITORQUE VALVE OPERATORS The subject document is transmitted for issuance on March , 1979. The Circular should be issued to all holders of Reactor Operating Licenses and Construction Permits. Also enclosed is a draft copy of the transmittal letter. Norman C. Moseley, Director Division of Reactor Operations Inspection Office of Inspection and Enforcement Enclosures: 1. IE Circular No. 79-04 2. Draft Transmittal Letter CONTACT: H. A. Wilber, IE 49-28180 . (Transmittal letter for IE Circular No. 79-04 to each holder of an NRC Operating License or a Construction Permit) Addressee: The enclosed IE Circular 79-04 is forwarded to you for information. If there are any questions related to your understanding of the suggested actions, please contact this office. Signature (Regional Director) Enclosure: IE Circular No. 79-04 . UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 March 16, 1979 IE Circular No. 79-04 LOOSE LOCKING NUT ON LIMITORQUE VALVE OPERATORS Description of Circumstances: On December 8, 1978, Fort Calhoun Station Unit No. 1 reported that 30 out of 65 Limitorque Type SMB valve operators did not have the locking nut fastened securely in accordance with the manufacturer's recommendation. If this locking nut is not secure it can loosen and allow the stem nut to move axially to the point that the splines are disengaged; resulting in a loss of drive to the valve stem. The licensee reported that several locking nuts were slightly loose but in no instance had the stem nut backed out enough to affect the operation of the valve. This licensee was made aware of the potential problem by a letter of July 28, 1978, from the NSSS supplier, Combustion Engineering, inc. Other plants have reported similar findings. On April 27, 1977, Davis-Besse Nuclear Power Station Unit No. 1, reported that two valve operability failures had been caused by locking nuts loosening and falling off. During the ensuing inspection program a total of 65 out of 144 safety related valve operators required staking. Arkansas Nuclear One (ANO), Unit 2, reported on June 29, 1978, that several valve operators required staking. A subsequent inspection at ANO Unit 2 was made by an IE inspector who identified records that 15 out of 17 SMB operators provided by the NSSS supplier (Combustion Engineering Inc.) required staking. Valve operability failures, resulting from loosened locking nuts, have also been reported by Cooper Nuclear Station (Unusual Event Report 75-5), Browns Ferry Unit 2 report of March 6, 1974 and Three Mile Island Nuclear Station Unit 1 reports of March 13, 1976 and October 20, 1976. The corrective action by the licensee in each case was to stake the locking nut. In June 1978, the Limitorque Corporation issued a supplement to the October 1977 issue of the Type SMB Instruction and Maintenance Manual SMBI-170 that called for the crimping or staking of the locking nuts. The 1971 issue of the manual had statements for crimping and staking of the lock nuts incorporated into the manual. The stem nut specification drawing provided by Limitorque for Unit Types SMB-000, SMB-00, SMB-0, SMB-1, SMB-2, SMB-3, and SMB-4 directs the customer to a Limitorque 1 of 2 . IE Circular No. 79-04 March 16, 1979 Drawing No. 21-497-0009-3 for instructions on staking the locking nut; the specification drawing for the SMB-5 unit has a reference to Limitorque Drawing No. 21-497-0010-3 for staking instructions. Pennsylvania Power and Light Company (PP&L) informed the NRC that the generic problem of failure to stake locking nuts exists with Limitorque Type SMC valve operators and Type SMB operators. PP&L Co. was advised of the problem by Bechtel Corporation. The information was submitted to the NRC on March 2, 1979 as a deficiency at the Susquehanna Steam Electric Station. The Type SMC Instruction and Maintenance Manual SMCI-04-78 and Drawing No. 21-497-0013-3 provide directions for securing the locking nut. All holders of construction permits and operating licenses should be aware that the potential for valve operator failure exists if the locking nut is not adequately secured. The recommended action is to survey all installed Limitorque Operator Types SMB-000 through SMB-5 and Type SMC to determine that the locking nut is secure and to verify that assembly and maintenance instructions contain directions for securing the locking nut either by staking, per the vendor's recommendation, or another acceptable manner. No written response to this Circular is required. If you require additional information regarding this subject, contact the Director of the appropriate NRC Regional Office. Enclosure: List of IE Circulars Issued in the Last Twelve Months 2 of 2
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021