ML20148K729
| ML20148K729 | |
| Person / Time | |
|---|---|
| Issue date: | 11/07/1978 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 7811170276 | |
| Download: ML20148K729 (1) | |
Text
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NUCLEAR REGULATO3Y COMMISSION
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REGION IV
-A 011 HYAN PLAZA DRIVE. SUITE 1000
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AH LINGTOR TEXAS 70011
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flovember 7,1978 E.R.D.A.
ATTH:
H. Ness 15 fl. 23rd Street Grand Forks, North Dakota Gentlemen:
The enclosed Nuclear Regulatory Commission (NRC) IE Bulletin No. 78-13 requires action by you with respect to certain gauging devices in your possession.
Records show that you have received one or more of these gauges which are manufactured by Kay-Ray, Incorporated.
These gauges contain radioactive material regulated by the NRC.
The possession and use of the radioactive material contained in the gauges is governed by either a specific NRC license issued to you or under the general license provisions of NRC regulation 10 CFR Part 31, Section 31.5.
A copy of 10 CFR 31.5 is provided for your information.
If you possess gauges under a general license, you should have received a copy of this regula-tion from the gauge vendor when you received the gauges.
Should you have any questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely,,
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i.
Karl V. Seyfrit.!
Director
Enclosures:
1.
IE Bulletin fio. 78-13 2.
List of IE Bulletins Issued in 1978 e
7811170 2 76
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.
C., 20555 IE Bulletin No. 78-13 October 27, 1978 Page 1 of 2 FAILURE IN SOURCE HEADS OF KAY-RAY, INC., GAUGES MODELS 7050, 70508, 7051, 70518, 7060, 70608, 7061, AND 70518 Description of Circumstances:
The U. S. Nuclear Regulatory Commission (NRC) has received information that en three occasions in the past year fractures have occurred at the weld between the dome and the box of source heads used in the subject gauges manufactured by Kay-Ray, Inc.
These gauges contain radioactive material regulated by the NRC.
The possession and use of the radio-active material in the gauges is governed by either a specific NRC license or under the general license provisions of NRC regulation 10 CFR 31, Section 31.5.
A copy of 10 CFR 31.5 is enclosed.
These incidents of weld fractures in the gauges have caused the dome to separate from the box, exposing the 500 millicurie cesium-137 sealed I
source.
In one case, the radioactive source itself fell loose from the dome and was completely exposed.
The separation of the dome from the box could result in a radiation overexposure if an individual actually handled the radioactive source or worked in close proximity to a gauge where the lead dome had separated from the box.
In order to correct this potential radiation hazard, Kay-Ray has developed a support bracket which they will supply free of charge to prevent the dome separation if a fracture does occur.
In a June 30, 1978 letter (copy enclosed) Kay-Ray advised you of the availability of the support bracket and requested you to return a card confirming the specific source heads in your possession.
A number of companies have not returned a card to Kay-Ray, Inc.
l In order to assure correction of this potential hazard, you should complete the following actions.
Actions to be taken by you as a licensee of the NRC:
1.
On the enclosed form, enter your company's name, address and telephone number, complete the other actions according to the instructions, and sign the preaddressed form and return it to the NRC after completing all the required actions.
IE Bulletin No. 78-13 October 27, 1978 Page 2 of 2 If you have transferred or otherwise disposed of any Kay-Ray gauges, take the action in item number 2, following:
2.
Complete item 1 of the enclosed form, and (a) if you possessed the gauge under a general license of 10 CFR 31.5 include with the form a statement of how you have complied, or information which does comply, with the requirements of 10 CFR 31.5(c)(8) or (9) and pro-vide the name and address of the persons or organizations to whom the gauge was transferred, or (b) if you possessed the gauge under a specific license include with the form a statement of how you complied with the requirements of 10 CFR 30.41 and provide the name and address of the persons or organizations to whom the gauge was transferred.
If you have any of the specified Kay-Ray gauges in your possession, take the actions in item numbers 3 through 5, following:
3.
Within two (2) days of receipt of this Bulletin, visually inspect the source head on models 7050, 7050B, 7051, 7051B, 7050, 7060B, 7061, and 7061B of Kay-Ray gauges in your possession for evidence of weld cracks between the dome and box.
If cracks are found, take the following actions:
(a) contact Kay-Ray immediately at (312) 259-9244 and inform them, and (b) file a report with this office as required by 10 CFR 31.5(a)(5).
(A copy of 10 CFR 31.5 is enclosed.)
4.
Within ten (10) days after receiving the support bracket (s) from Kay-Ray, install a support bracket on each Kay-Ray gauge model (identified in item 3 above) in your possession.
5.
Within twelve (12) days after receiving the support bracket (s) from Kay-Ray, report the completion of the above actions to this office.
The report should be submitted by completing and returning the enclosed preprinted, preaddressed form to the NRC.
In addition to the above specific actions, we recommend that you read and become thoroughly familiar with the conditions of either the specific NRC license or the general license of 10 CFR 31.5 whichever authorizes your use and possession of the gauge devices.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80. Approval was given under a blanket clearance specifically for identified generic problems.
Enclosures:
1.
Report Form 2.
10 CFR 31 (extract) 3.
Kay-Ray Letter dated 6/30/78 4.
Kay-Ray Card
IE Bulletin No. 78-13 0.tober 23, 19/8 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
78-01 Flammable Contact 1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with an CR120A Relays Operating License (OL) or Construc-tion Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an Operating License (OL) or Construc-tion Permit (CP) 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an Operating BWR Offgas System License (0L) or Operations Construction Permi't (CP) 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit Operating License Switches Inside (0L) or Construc-Reactor Containment tion Permit (CP) 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechanism - General (0L) or Construc-Electric Model tion Permit (CP)
CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils Operating License (OL) or Construc-tion Permit (CP)
~,
IE Bulletin fio. 78-13 October 23, 1978 Page 2 of 3 78-07 Protection Afforded 6/12/78 All Power Reactor by Air-Line Facilities with an Respirators and Operating License (OL) and Supplied-Air all class E and F Hoods Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees 78-08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element Trans-fer Tube and an Operating License (OL) 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an Operating Closures License (0L) or Construction Per-mit (CP) 1 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an Operating Spring Coils License (OL) or l
Construction Per-mit(CP) 78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Welds action: Peach Bottom 2 and 3 Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee
IE Bulletin 78-13 October 23, 1978 Page 3 of 3 78-12 A Typical Weld 9/29/78 All Power Reactor 11aterial in Reactor Facilities with an Pressure Vessel Operating License Wel ds (OL) or Construction Permit (CP)
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