ML19276E892
| ML19276E892 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/16/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W FLORIDA POWER CORP. |
| References | |
| NUDOCS 7903210587 | |
| Download: ML19276E892 (1) | |
Text
1 UNITED ST ATES
- # 8800g NUCLEAR REGULATORY COMMISSION f
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REGION il p
101 MARIETT A STREET,N.W.
e ibD8 ATLANT A, GEORGIA 30303 MAR 161979 In Reply Refer To:
RII:JP0 50-302 Florida Power Corporation Attn:
Mr. W. P. Stewart, Director Power Production P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Gentlemen:
The enclosed IE Circular 79-04 is forwarded to you for inforr.ation.
If there are any questions related to your understanding of the suggested actions, please contact this office.
w y
James P. O'Reilly b
Director
Enclosure:
IE Circular No. 79-04 cc w/ encl:
G. P. Eeatty, Jr.
Nuclear Plant Manager P. O. box 1228 Crystal River, Florida 32629 7003310 SI
IE Circular No. 79-04 March 16, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST '1VELVE M0hTHS Circular Subject Date of Issued To No.
Issue 78-16 Limitorque Valve 7/26/78 All Holders of Reactor OLs or Actuators cps 7-17 Inadequate Guard Training /
10/13/78 All Holders of Qualification and Falsified and applicants for Reactor OLs.
Training Records 7-18 UL Fire Test 11/6/78 All Holders of Reactor OLs or cps 78-19 Manual override (Bypass) 12/28/78 All Holders of of Safety Actuation Signalt, cps 79-01 Administration of 1/12/79 All Medical Unauthorized Byproduct Licensees except Material to Humans Teletherapy Medical Licensees and each Radiopharmaceutical Suppliers 79-02 Failure of 120 Volt Vital 2/16/79 All Holders of AC Power Supplies Reactor OLs and cps 79-03 Inadequate Guard Training-2/23/79 All Holders of Qualification and Falsified and applicants Training Records for Special Nuclear Material Licenses in Safeguards Group I Enclosure Page 3 of 3
IE Circular No. 79-04 March 16, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MohTHS Circular Subject Date of Issued To No.
Issue 78-09 Arcing of General Electric 6/5/78 All Holders of Company Size 2 Contactors cps 78-10 control of Sealed 6/14/78 All Medical Sources Used in Licensees in Radiation Therapy Categories G and G1 78-11 Recirculation M-G 6/15/78 All Holders of Set Overspeed Stops BWR OLs or cps 78-12 HPCI Turbine Control 6/30/78 All Holders of Valve Lift Rod Bending BWR OLs or cps for plants with HPCI Terry Turbine 78-13 Inoperability of Multiple 7/10/78 All Holders of Service Water Pumps Reactor OLs and cps except for plants located in: AL, AK, CA, FL, GA, LA, MS, SC 78-14 HPCI Turbine Reversing 7/12/78 All Holders of BWR Chamber Hold Down Bolting OLs or cps for plants with a HPCI Terry Turbine excepting Duane Arnold and Monticello 78-15 Checkvalves Fail to 7/20/78 All Holders of Close In Vertical Reactor OLs or cps Position Enclosure Page 2 of 3
IE Circular No. 79-oh March 16, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS Circular Subject Date Issued To No.
of Issue 76-01 Loss of Well Logging h/5/78 All Holders of Source Well Logging Source Licenses 78-02 Proper Lubricating 011 h/20/78 All Holders of for Terry Turbines Reactor OLs cr cps 78-03 Fackaging Greater Than 5/12/78 All Holders of lype A Quantities of Reactor OLs, cps, Low Specific Activity Fuel Cycle, Radioactive Material Priority I Material for Transport and Waste Disposal Licenses 78-Ch Installation Error That 5/15/78 All Holders of Cculd Prevent C1csing of Reactor OLs or Fire Doors cps 78-05 Inadvertent Safety Injecticn 5/23/78 All Holders of During Cooldown Reactor OLs or cps 78-C6 Potential Co==on Mode 5/23/78 All Holders of Flooding of ECCS Equipment Reactor OLs or Roors at LWP Facilities cps 78-07 Damaged Corponents of a 5/31/78 All Holders cf Bergen-Paterson Series Reactor OLs or 25000 Hydraulic Test cps Etand 78-08 Environnental Qualification 5/31/78 All Holders of of Safety Related Equipnent Reactor OLs or at Nuclear Power Plants CFs Enclosure Page 1 of 3
IE Circular No. 79-oh March 16, 1979 Drawing No. 21-h97-0009-3 for instructions on staking the locking nut ;
the specification drawing for the SMB-5 unit has a reference to Limitorque Drawing No. 21 h97-0010-3 for staking instructions.
Pennsylvania Power and Light Company (PF&L) informed the NRC that the generic problem of failure to stake locking nuts exists with Limitorque Type SMC valve operators and Type SMB operatcrs.
FF&L Co. vas advised of the problem by Bechtel Corporaticn. The information was submitted to the ImC on March 2,1979 as a deficiency at the Susquehanna Steam Electric Station. The Type SMC Instruction and Maintenarce l'enual SMCI-Oh-78 and Drawing No. 21 h97-0013-3 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 SYB-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 reconnendation, or another acceptable tanner.
No written recycnse to this Circular is required.
If you require additional information regarding this subject, contact the Director of the appropriate IGC Regional Office.
Enclosure:
List Of IL Cf reulars Issued in the Last Twelve Months 2 of 2
UNITED STATES NUCLEAR REGULATORY CCITISSION OFFICE OF INSPECTION AND E"FORCEMENT WASHINGTON, D.C.
20555 March 16, 1979 IE Circular No. 79-0h LOOSE LOCEING NUT ON LIMITORQUE VALVE OPERATORS Description of Circumstances:
On December 8,1978, Fort Calboun Station Unit No.1 reported that 30 out of 65 Limitorque Type SM3 valve operators did not have the locking nut fastened securely in accordance with the manufacturer's reco==endation.
If this locking nut is not secure it can loosen and allow the stem nut to cove axially to the point that the splines are disengaged; resulting in a loss of drive to the valve stet.
The licensee reported that several locking nuts were slightly loose but in no instance had the sten nut backed out enough to affect the operation of the valve.
This licensee was cade avere of the potential problem by a letter of July 28, 1978, from the USSS supplier, Combustion Engineering, Inc.
Other plants have reperted similar findinFs.
On April 27, 1977, Davis-Eesse Nuclear Fover 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 1hh safety related valve operators required staking. Arkansas Nuclear One (ANO), Unit 2, reported on June 29, 1978, that several valve operators required stakin6. A subsequent inspection at ANO Unit 2 was made by an IE inspector who identified records that 15 out of 17 S!5 operators provided by the NSSS supplier (Combustion Engineering Inc.) required staking.
islve 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 6,197h 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 1976, the Limiterque Corporat '
.1 issued a supplement to the October 1977 issue of the Type S:e Instruction and Maintenance Manual SMBI-170 that called for the crimping or staking of the locking nuts.
The 1971 issue of the canual had statetents for crimping r.nd staking of the lcck nuts incorporated into the manual. The stem nut specification drawing provided by Limitorque for Unit Types SMB-000, SMB-00, SMB-0, SMB-1, S).B-2, SME-3, and SMB L directs tae custorer to a Limitorque 1 of 2 h
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