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                  .,k             &                              NUCLEAR REGULATORY COMMISSION y '!D 5[,jPlj ov y/ -f-:[
.,k NUCLEAR REGULATORY COMMISSION 5[,jPlj y '!D REGICN 1 y/ - : [
                                    $                                                                  REGICN 1 631 P ARK AVENUE xtNo oF PRUSSI A, PENN5YL,V ANI A 19406
631 P ARK AVENUE f-xtNo oF PRUSSI A, PENN5YL,V ANI A 19406
                  %;-Qg/                                                                                                     October 27, 1978
%;-Qg/
                      *..s City of Lancaster Martin Electrical Services, Inc.
ov October 27, 1978
c/o Water Filtration Plant ATTN:                 John Weaver                                                                                   .
*..s City of Lancaster Martin Electrical Services, Inc.
Columbia, Pennsylvania 17512 Gentlemen:
c/o Water Filtration Plant ATTN:
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 Xay-Ray, Incorporated. There gauges contain radioactive material regulated by the NRC. The possession and use of the radiccctive material contained in the gauges -is governed by either a specific NRC license issued to you or under the gereral 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 regu-lation from the gauge vendor when you received the gauges.
John Weaver Columbia, Pennsylvania 17512 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 Xay-Ray, Incorporated.
There gauges contain radioactive material regulated by the NRC.
The possession and use of the radiccctive material contained in the gauges -is governed by either a specific NRC license issued to you or under the gereral 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 regu-lation 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.
Should you have any questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, oyce f 'thw
Sincerely, f
                                                                                                                      . Grier
'thw oyce
                                                                                                          -    Director
. Grier Director


==Enclosures:==
==Enclosures:==
: 1.                 IE Bulletin No. 78-13
1.
: 2.               List of IE Bulletins Issued in 1978 CONTACT:               Robert 0. McClintock (215)337-5206                                                                             ,
IE Bulletin No. 78-13 2.
f/     fhf [
List of IE Bulletins Issued in 1978 CONTACT:
Robert 0. McClintock (215)337-5206 f/
fhf [
l l
l l


U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 IE Bulletin No. 78-13 Date: October 27, 1978 Page 1 of 2                 <
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
FAILURE IN SOURCE HEADS OF KAY-RAY, INC., GAUGES MODELS 7050, 7050B, 7051, 7051B, 7060, 70608, 7061, AND 7061B Description of Ci. cumstances:
20555 IE Bulletin No. 78-13 Date: October 27, 1978 Page 1 of 2 FAILURE IN SOURCE HEADS OF KAY-RAY, INC., GAUGES MODELS 7050, 7050B, 7051, 7051B, 7060, 70608, 7061, AND 7061B Description of Ci. cumstances:
The U.S. Nuclear Regulatory Commission (NRC) has received information that on 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 radioactive material in tne yuges is 9,0verned 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.
The U.S. Nuclear Regulatory Commission (NRC) has received information that on 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 incidents of weld fractures in the gauges have caused the dome to separate from the box, exposing the 500 millicurie Cesium-137 sealed 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.                                           ,
These gauges contain radioactive material regulated by the NRC. The possession and use of the radioactive material in tne yuges is 9,0verned by either a specific NRC license or under the general license provisions of NRC regulation 10 CFR 31, Section 31.5.
In order to correct this potential radiation hazard, Kay-Ray has de-veloped a support bracket which they will supply free ofIncharge        to a June 30, prevent the dome separation if a fracture does occur.
A copy of 10 CFR 31.5 is enclosed.
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.
These incidents of weld fractures in the gauges have caused the dome to separate from the box, exposing the 500 millicurie Cesium-137 sealed In one case, the radioactive source itself fell loose from the source.
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 de-veloped a support bracket which they will supply free of charge to prevent the dome separation if a fracture does occur.
In a {{letter dated|date=June 30, 1978|text=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.
In order to assure correction of this potential hazard, you should complete the following actions.
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:
Actions to be taken by you as a licensee of the NRC:
: 1. On the enclosed form, enter your company's name, address and tele-phone number, complete the other actions according to the instruc-tions, and sign the preaddressed form and return it to the NRC after completing all the required actions.
1.
On the enclosed form, enter your company's name, address and tele-phone number, complete the other actions according to the instruc-tions, and sign the preaddressed form and return it to the NRC after completing all the required actions.


TE Bulletin No. 78-13 Date:   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:
TE Bulletin No. 78-13 Date:
: 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 provide 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.
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 provide 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:
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, 70508, 7051, 7051B, 7060, 70608, 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.)
3.
: 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.
Within two (2) days of receipt of this Bulletin, visually inspect the source head on models 7050, 70508, 7051, 7051B, 7060, 70608, 7061, and 7061B of Kay-Ray gauges in your possession for evidence of weld cracks between the dome and box.
: 5. Within twelve (12) days after receiving the support bracket (s) from Kay-Ray, report the completion of the above actions to this office.
If cracks are found, take the following actions:
The report should be submitted by completing and returning the enclosed preprinted, preaddressed form to the NRC.                         l In addition to the above specific actions, we recommend that you read             i l
(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.
l In addition to the above specific actions, we recommend that you read i
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.
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.
i Approved by GAO, B180225 (R0072); clearance expires 7-31-80. Approval         '
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
was given under a blanket clearance specifically for identified generic           l problems.                                                                         )
Approval was given under a blanket clearance specifically for identified generic problems.
                                                                                          )
)
Enclosures-                                                                       '
Enclosures-1.
: 1. Report Form l
Report Form 2.
: 2. 10 CFR 31 (extract)
10 CFR 31 (extract) 3.
: 3. Kay-Ray Letter dated 6/30/78                                               l
Kay-Ray Letter dated 6/30/78 4.
: 4. Kay-Ray Card 1
Kay-Ray Card
l


l IE Bulletin No. 78-13                                   !
l IE Bulletin No. 78-13 October 27,.1978 Page 1 of 2 LISTING OF IE BULLETINS t
October 27,.1978                                       '
ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
Page 1 of 2 LISTING OF IE BULLETINS                                                                                                   t ISSUED IN 1978 Bulletin                 Subject                                                   Date Issued           Issued To No.                                                                                                                                                            .
78-01 Flammable Contact -
78-01                   Flammable Contact -                                       1/16/78               All Power Reactor                                   i Arm Retainers in G.E.                                                             Facilities with an CR120A Relays                                                                     Operating License (OL) or                           ,
1/16/78 All Power Reactor i
                                                                                                                                                                                                  ~
Arm Retainers in G.E.
Construction Permit (CP) 78-02                   Terminal Block                                             1/30/78               All Power Reactor Qualification                                                                     Facilities with an OL or CP 78-03                 ~ Potential Explosive                                       2/8/78               All BWR Power                                       l Reactor Facilities
Facilities with an CR120A Relays Operating License (OL) or
                                                                                                                                                                                                  ~
~,
Gas Mixture Accumula-tions Associated with                                                             with an OL or CP BWR Offgas System Operations 78-04                   Environmental Quali-                                       2/21/78               All Power Reactor fication of Certain                                                               Facilities with an                                   :
Construction Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an OL or CP 78-03
Stem Mounted Limit                                                               OL or CP Switches Inside                                                                                                                         .
~ Potential Explosive 2/8/78 All BWR Power l
Reactor Containment 78-05                   Malfunctioning of                                           4/14/78               All Power Reactor Circuit Breaker                                                                   Facilities with an Auxiliary Contact                                                                 OL or CP Mechanism-General                                                                                                                       :
Gas Mixture Accumula-Reactor Facilities
Model CR105X                                                                                                                           i 78-06                 Defective Cutler-                                           5/31/78               All Power Reactor Hammer, Type M Relays                                                             Facilities with an With DC Coils                                                                     OL or CP 78-07                 Protection afforded                                         6/12/78'             All Power' Reactor l                                                         by Air-Line Respirators                                                           Facilities with an and Supplied-Air Hoods                                                           OL, all Class E and F                               j Research Reactors with aa OL, all Fuel Cycle
~
'                                                                                                                                            Facilities with an OL,
tions Associated with with an OL or CP BWR Offgas System Operations 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X i
;                                                                                                                                            and all Priority 1                                   .
78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78' All Power' Reactor l
Material Licensees i
by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all Class E and F j
  . - _ _ _ _ _ . . _ . _ . - . , _ _ _ . . ~ _ . _ . .                   _ _ . . . . - . . _ _ . , _ _ . - _ . _ _ _ . . . _ - _ _ _                  . . . _ . . . _ . .  . - . . - . _ , -
Research Reactors with aa OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees i
. - _ _ _ _ _.. _. _. -., _ _ _.. ~ _. _..


m           -
m IE Bulletin No. 78-13 October 27, 1978 Page 2 of 2 LISTING 0F IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
IE Bulletin No. 78-13 October 27, 1978 Page 2 of 2                               .
78-08 Radiation Levels from 6/12/78 All Power, Test, and Fuel Element Transfer Research Reactor Tubes Facilities with an OL having Fuel Element Transfer Tubes.
LISTING 0F IE BULLETINS ISSUED IN 1978 Bulletin             Subject                     Date Issued                 Issued To No.
78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL (for action)
78-08               Radiation Levels from       6/12/78                     All Power, Test, and Fuel Element Transfer                                   Research Reactor Tubes                                                   Facilities with an OL having Fuel Element Transfer Tubes.
Closures or CP (for information).
78-09               BWR Drywell Leakage         6/14/78                     All BWR Power Paths Associated with                                   Reactor Facilities Inadequate Drywell                                       with an OL (for action)
78-10 Bergen-Paterson 6/27/78 All Power Reactor Hydraulic Shock Facilities with an Suppressor Accumulator OL or CP Spring Coils 78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action:
Closures                                                 or CP (for information).
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee.
78-10               Bergen-Paterson             6/27/78                     All Power Reactor Hydraulic Shock                                         Facilities with an Suppressor Accumulator                                   OL or CP Spring Coils                                                                           ,
All other BWR Power Reactor,
78-11               Examination of Mark I       7/21/78                     BWR Power Reactor Containment Torus                                         Facilities with an OL Welds                                                   for action: Peach             ,
Facilities with an OL for information.
Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee. All other BWR Power Reactor ,
78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP.
Facilities with an OL for information.             '
+4-
78-12               Atypical Weld Material       9/29/78                     All Power Reactor in Reactor Pressure                                       Facilities with an Vessel Welds                                             OL or CP.
+ -.. -- -.
              ,-- -- e                                       ,,,--1--- ... , , -          ,e ew - - - , , ---
a
,-- -- e
~w-.
,,.m
,,,--1---
,e ew - - -,


U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 4
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 4
Licensee Name:
Licensee Name:
Address:
Address:
                                                  --.. .J 2: 0 7.,;.
--...J 2: 0 7.,;.
y , -. .
y, -..
Telephone:                           _
Telephone:
If you possess the gauges under a specific NRC license, enter the license number:
If you possess the gauges under a specific NRC license, enter the license number:
: 1.       If you have transferred or otherwise disposed of any Kay-Ray                                     /
1.
gauges, place a check or mark in the box and provide the                                   /
If you have transferred or otherwise disposed of any Kay-Ray gauges, place a check or mark in the box and provide the
/
/
information required by action item 2 in the Bulletin instructions.
information required by action item 2 in the Bulletin instructions.
Complete the following for Kay-Ray gauges in your possession:
Complete the following for Kay-Ray gauges in your possession:
: 2.       Date the card was mailed to Kay-Ray, Inc. , confirming the specific source heads in your possession.                                                   (date)
2.
: 3.       Number of source heads visually inspected for evidence of weld cracks between the dome and box on models 7050, 70508,                               (number) 7051, 7051B, 7060, 70608, 7061, and 70618.
Date the card was mailed to Kay-Ray, Inc., confirming the (date) specific source heads in your possession.
: 4.       Number of source ..eads inspected in the items above which (number)
3.
Number of source heads visually inspected for evidence of weld cracks between the dome and box on models 7050, 70508, (number) 7051, 7051B, 7060, 70608, 7061, and 70618.
4.
Number of source..eads inspected in the items above which (number)
Ead weld cracks.
Ead weld cracks.
: 5.       Date support brackets were received from Kay-Ray.
5.
(date)
Date support brackets were received from Kay-Ray.
: 6.       Date installation of support brackets was completed.
(date) 6.
Date installation of support brackets was completed.
(date)
(date)
Signature and printed name of responsible individual or Radiation Safety Officer.
Signature and printed name of responsible individual or Radiation Safety Officer.
After completing the above actions and entering the required information,
After completing the above actions and entering the required information,
  . sign the form, fold it so that the NRC return address is showing, tape or staple closed and place in the mail. No postage is required.
. sign the form, fold it so that the NRC return address is showing, tape or staple closed and place in the mail.
No postage is required.


e .
e UNITED STATES f
UNITED STATES                                                                     f ]
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NUCLE AR REGULATORY COMMISSION                                       Postaos ano rass paso           )
NUCLE AR REGULATORY COMMISSION Postaos ano rass paso
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OP PICI AL SUSINESS                                               Comuassson PEN ALTY POR PRIV ATE USE, $300 L J l
OP PICI AL SUSINESS Comuassson PEN ALTY POR PRIV ATE USE, $300 L
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION & ENFORCEMENT                         ;
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REGION I 631 PARK AVENUE                                             l KING OF PRUSSIA, PA 19406                                   ,
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION & ENFORCEMENT REGION I 631 PARK AVENUE KING OF PRUSSIA, PA 19406 f
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UNITED STATES NUCLEAR RE@ULATORY COMMISSION RULES and REGULATIONS                                                                                     i TITI.E 10, CHAPTER 1. CODE OF PEDERAL REGULATIONS-ENERGY
UNITED STATES NUCLEAR RE@ULATORY COMMISSION RULES and REGULATIONS TITI.E 10, CHAPTER 1. CODE OF PEDERAL REGULATIONS-ENERGY PART GENERAL DOMESTIC LICENSES FOR BYPRODUCT MATERIAL i
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PART                 GENERAL DOMESTIC LICENSES FOR BYPRODUCT MATERIAL i
1
1
            . 31 l
. 31 I
I S* *-                                                        31.3 Certain devices and equipment.
manufactured for the purpose of '
manufactured for the purpose of '
31.1 Purpose and scope.                                                                                   detecting, measuring, gauging or A general license is hereby issued to 31.2 Terms and conditions.                                                                                controlling thickness, density, level, inter-31.3 Certain devices and equipment.                     transfer receive, acquire, own, possess and 31.s certain mensunas, sauses or contromas use byproduct material incorporated in             qualitative or quantitative chemical devices, the following devices or equipmcat which           composition, or for producing light or an 31.6 General license to install devtces sen-           have been manufactured, tested and erally 11 censed in 6 31.5.                                                                   iot'ized atmosphere.
S* *-
31.7 Lu           u safety devtcu for un in           labeled by the manufacturer in ac-                 -    N N p u n! &                 Mp       ph
31.3 Certain devices and equipment.
                      *-                                  ccrdance with the specifications con-             (a) f this secti n applies only to by-31.a Amancium 241 in the form of calibre-               tained in a specific ticense issued to him tion or reference sources.                                                                   product matenal Contained in devices 31.9 General license to own byproduct me.            . by the Commission.                           . which have been manufactured or tenal.                                 .       (a) Static climination device. Devices         nitially transferredt and labeled in ac-31.10 General licenu for strontium-90 in ic' 2 designed for use as static eliminators d* '''" " d"i*"*                        Ewhich contain, as a sealed source or                 mdang             M q spe&ah con-tained in a specific hcense issued pursuant 31.1 General 11cenu for um of byproduct u. sources, byproduct material consisting of materista for certain in vitro clinical g                                                    to @ 32.51 of this chapter or in ac-or taboratory testins.                    a total of not more than 500 microcunes           cordance with the specifications con-tained in a specific license issued by an b)       eted 34 FR 51.1                   Agreement State which authorizes (c) [ Deleted 35 FR 3982.)                         n       n f             cM t pe m ns (d) lon genentting tube. Devices de,                           "'"**                ***"
detecting, measuring, gauging or 31.1 Purpose and scope.
I*"
31.2 Terms and conditions.
signed for ionization of air which contam, ate.
A general license is hereby issued to controlling thickness, density, level, inter-31.3 Certain devices and equipment.
as a scaled source or sources, byproduct j                                             *"
transfer receive, acquire, own, possess and 31.s certain mensunas, sauses or contromas use byproduct material incorporated in qualitative or quantitative chemical
* material consisting of a total of not more *                       "*" #    #*"  *"  E   ""
: devices, the following devices or equipmcat which composition, or for producing light or an 31.6 General license to install devtces sen-erally 11 censed in 6 31.5.
  ~@ 31.1 Purpose and scope,                                 than 500 microcuries of polonium-210 f E **"*"'                     *                          *
have been manufactured, tested and iot'ized atmosphere.
,          This part establishes general licenses           per device or of a total of not more than         g  R *e*ne*d kenn 6 pawa$ W M h j for the possession and use of byproduct                   50 millicuries of hydrogen-3 (tritium) per
31.7 Lu u safety devtcu for un in labeled by the manufacturer in ac-N N p u n! &
:g material contained in certain items and a               ~
Mp ph ccrdance with the specifications con-(a) f this secti n applies only to by-31.a Amancium 241 in the form of calibre-tained in a specific ticense issued to him tion or reference sources.
device.
product matenal Contained in devices
' general license for ownership of by-                       @ 31.4 (Deleted 36 FR 16898-)                     to the device at the time of receipt and N product material. Part 30 of this chapter                             #            *" urin g, Sauging or     beanng a statement that removal of the also contains provisions applicable to the                       n  Iling devices s                       label is prohibited are maintained thereon subject matter of this part.                                 (a) A general heense is hereby issued         and shall comply with allinstructions and 31.2 Terms and conditions.                     ;; to commercial and industrial firms and             precautions provided by such labels; g         (a) The general licenses provided in W research, educational and medicalinstitu-                         (2) Shall assure that the device is R this part are subject to the provision of l tions, individuals in the conduct of their                       tested for leakage of radioactive matenal E @ @ 30.14(d), 30.34(a) to (e), *30.41, u business, and Federal, State or local and proper operation of the on-off 6 30.51 to 30.63 and Parts 19,20, and 21t E overnment        g             agencies to acquire, receive,      mechanism and indicator, if any, at no E of this chapter unless indicated other. possess, use or transfer, in accordance                               longer than six-month intervals or at such wise in the language of the general li. with the provisions of paragraphs (b),(c)                           other intervals as are specified in the and (d) of this section, byproduct ma-           label; however; Jense.                                                                                                           (i) devices containmg only krypton tenal contained in devices designed and
. by the Commission.
    '    At tention is directed particularly to the                                                           need not be tested for leakage of radio-provuions of the regulations in Part to of this             ' Persons possessms byproduct :naterial in active matenal, and chapter wnich relate to the labeling of con. Jevices under the senerat license in i 31.s iainers.
which have been manufactured or 31.9 General license to own byproduct me.
before Jan. I s.19-s may continue to possess,         (ii) devices containing only tntium or
(a) Static climination device. Devices nitially transferredt and labeled in ac-tenal.
* use or transfer that matenal in accordance with   not more than 100 microcuries of other Amended 38 FR 33968.
31.10 General licenu for strontium-90 in ic' 2 designed for use as static eliminators Ewhich contain, as a sealed source or mdang M q spe&ah con-d* '''" " d"i*"*
i Amended 43 FR 6915.
tained in a specific hcense issued pursuant for um of byproduct u. sources, byproduct material consisting of 31.1 General 11cenu to @ 32.51 of this chapter or in ac-materista for certain in vitro clinical g a total of not more than 500 microcunes cordance with the specifications con-or taboratory testins.
I 1.5 in e et n Jan.14       beta and/or gamma ermttmg matenal or
tained in a specific license issued by an b) eted 34 FR 51.1 Agreement State which authorizes (c) [ Deleted 35 FR 3982.)
                                                                    *[umnents 31-1                                               September 1,1978
n n f cM t pe m ns (d) lon genentting tube. Devices de, signed for ionization of air which contam, I*"
ate.
as a scaled source or sources, byproduct j material consisting of a total of not more
* E
~@ 31.1 Purpose and scope, than 500 microcuries of polonium-210 f E **"*"'
This part establishes general licenses per device or of a total of not more than R *e*ne*d kenn 6 pawa$ W M h g
j for the possession and use of byproduct 50 millicuries of hydrogen-3 (tritium) per material contained in certain items and a device.
:g
~
' general license for ownership of by-
@ 31.4 (Deleted 36 FR 16898-)
to the device at the time of receipt and N product material. Part 30 of this chapter
*" urin g, Sauging or beanng a statement that removal of the also contains provisions applicable to the Iling devices s label is prohibited are maintained thereon n
subject matter of this part.
(a) A general heense is hereby issued and shall comply with allinstructions and 31.2 Terms and conditions.
;; to commercial and industrial firms and precautions provided by such labels; g
(a) The general licenses provided in W research, educational and medicalinstitu-(2) Shall assure that the device is R this part are subject to the provision of l tions, individuals in the conduct of their tested for leakage of radioactive matenal E @ @ 30.14(d), 30.34(a) to (e), *30.41, u business, and Federal, State or local and proper operation of the on-off E overnment agencies to acquire, receive, mechanism and indicator, if any, at no 6 30.51 to 30.63 and Parts 19,20, and 21t g
E of this chapter unless indicated other.
possess, use or transfer, in accordance longer than six-month intervals or at such wise in the language of the general li.
with the provisions of paragraphs (b),(c) other intervals as are specified in the and (d) of this section, byproduct ma-label; however; Jense.
tenal contained in devices designed and (i) devices containmg only krypton At tention is directed particularly to the need not be tested for leakage of radio-provuions of the regulations in Part to of this
' Persons possessms byproduct :naterial in chapter wnich relate to the labeling of con. Jevices under the senerat license in i 31.s active matenal, and before Jan. I s.19-s may continue to possess, (ii) devices containing only tntium or iainers.
use or transfer that matenal in accordance with not more than 100 microcuries of other Amended 38 FR 33968.
I 1.5 in e et n Jan.14
*[umnents beta and/or gamma ermttmg matenal or i Amended 43 FR 6915.
31-1 September 1,1978


PART 31 o GENERAL DOMESTIC LICENSES FOR BYPRODUCT MATERIAL                                                             J 10 microcunes of alpha emitting material;       within 30 days, furnish to the Director of         (d) The general license in paragraph and devices held in storage in the original     the appropriate Nuclear Regulatory Com-         (a) of this section does not authorize the shipping container prior to initialinstalla. mission Inspection and Enforcement               manufacture or import of devices tion need not be tested for any purpose;       Regional Office listed in Appendix D of         containing byproduct material.
PART 31 o GENERAL DOMESTIC LICENSES FOR BYPRODUCT MATERIAL J
                                                                                                      ~
10 microcunes of alpha emitting material; within 30 days, furnish to the Director of (d) The general license in paragraph and devices held in storage in the original the appropriate Nuclear Regulatory Com-(a) of this section does not authorize the shipping container prior to initialinstalla.
(3) Shall assure that the tests required   Part 20 of this chapter, a report contain-by paragraph (c)(2) of this section and         ing a brief description of the event and other testing, installation, servicing, and     the remedial action taken; removal from installation involving the             (6) Shall not abandon the device radioactive materials, its shielding or         containing byproduct matenal; containment, are performed:                         (7) Shall not export the device N         (i) in accordance with the instructions   containing byproduct material except in 6 provided by the labels;or                           accordance with Part 110 of this s         (ii) by a person holding a specific       chapter;t (8) Except as provided in paragraph
mission Inspection and Enforcement manufacture or import of devices tion need not be tested for any purpose; Regional Office listed in Appendix D of containing byproduct material.
{ license pursuant to Parts 30 and 32 of this chapter or from an Agreement State       (c)(9) of this section, shall transfer or to perform such activities;                   dispose of the device containing by-(4) Shall maintain records showing product material only by transfer to a compliance with the requirements of person holding a specific license pursuant paragraphs (c)(2) and (c)(3) of this sec-       to Parts 30 and 32 of this chapter or from tion. The records shall show the results of     an Agreement State, to receive the device tests. The records also shall show the and within 30 days after transfer of a dates of performance of, and the names device to a specific licensee shall furnish of persons performing, testing, installa- to the Director of Nuclear Material Safety tion, servicifts, and removal from installa-   and Safeguards, U.S. Nuclear Regulatory tion concerning the radioactive material,       Commission, Washington, D.C. 20555, a
~
_its shielding or containment.                     report containing identification of the
(3) Shall assure that the tests required Part 20 of this chapter, a report contain-by paragraph (c)(2) of this section and ing a brief description of the event and other testing, installation, servicing, and the remedial action taken; removal from installation involving the (6) Shall not abandon the device radioactive materials, its shielding or containing byproduct matenal; containment, are performed:
    -                                                  device by manufacturer's name and Records of tests for leakage of radio-active material required by paragraph.model number and the name and address                             "
(7) Shall not export the device N
k of the person receiving the device. No (c)(2) of this section shall be maintained, report is required if the device is trans-for one year after the next required leak f ferred to the specific licensee in order to test is performed or until the scaledR obtain a replacement device; source is transferred or disposed of.               (9) Shall transfer the device to g Records of tests of the on-off mechanism           another generallicensee only:
(i) in accordance with the instructions containing byproduct material except in 6 provided by the labels;or accordance with Part 110 of this s
  . and indicator, required by paragraph                   (i) Where the device remains in use at g (c)(2) of this section, shall be maintained a particular location. In such case the
(ii) by a person holding a specific chapter;t
  "" for one year after the next required test transferor shall give the transferee a copy
{ license pursuant to Parts 30 and 32 of (8) Except as provided in paragraph this chapter or from an Agreement State (c)(9) of this section, shall transfer or to perform such activities; dispose of the device containing by-(4) Shall maintain records showing product material only by transfer to a compliance with the requirements of person holding a specific license pursuant paragraphs (c)(2) and (c)(3) of this sec-to Parts 30 and 32 of this chapter or from tion. The records shall show the results of an Agreement State, to receive the device tests. The records also shall show the and within 30 days after transfer of a dates of performance of, and the names device to a specific licensee shall furnish of persons performing, testing, installa-to the Director of Nuclear Material Safety tion, servicifts, and removal from installa-and Safeguards, U.S. Nuclear Regulatory tion concerning the radioactive material, Commission, Washington, D.C. 20555, a
* of the on-off mechanism and indicator is of this section and any safety documents performed or until the sealed source is dentified in the label of the device and transferred or disposed of. Records which within 30 days of the transfer, report to are required by paragraph (c)(3) of this the Director of Nuclear Material Safety section shall be maintained for a period and Safeguards, U.S. Nuclear R'egulatory of two years from the date of the Commission, Washington, D.C. 20555, recorded event or until the device is           the manufacturer's name and model
_its shielding or containment.
_ transferred or disposed of.                     number of device transferred, the name
report containing identification of the device by manufacturer's name and Records of tests for leakage of radio-active material required by paragraph.model number and the name and address k of the person receiving the device. No (c)(2) of this section shall be maintained, report is required if the device is trans-for one year after the next required leak f ferred to the specific licensee in order to test is performed or until the scaledR obtain a replacement device; source is transferred or disposed of.
      ~
(9) Shall transfer the device to g Records of tests of the on-off mechanism another generallicensee only:
and address of the transferee, and the (5) bpon the occurrence of a failure of or damage to, or any indication of a name and/or position of an individual possible failure of or damage to, the wno may constitute a point of contact shielding of the radioactive material or between the Commission and the trans-I"f"; 0f the on off mechanism or indicator, or (ii) Where the device is held in storage
. and indicator, required by paragraph (i) Where the device remains in use at g (c)(2) of this section, shall be maintained a particular location. In such case the
  . upon the detection of 0.005 microcune the original shipping container at its k or more removable radioactive material,                 ended location of use prior to initial
"" for one year after the next required test transferor shall give the transferee a copy
' shall immediately suspend operation of             ,
* of the on-off mechanism and indicator is of this section and any safety documents performed or until the sealed source is dentified in the label of the device and transferred or disposed of. Records which within 30 days of the transfer, report to are required by paragraph (c)(3) of this the Director of Nuclear Material Safety section shall be maintained for a period and Safeguards, U.S. Nuclear R'egulatory of two years from the date of the Commission, Washington, D.C. 20555, recorded event or until the device is the manufacturer's name and model
E the device until it has been repaired by           use by a generallicensee.
_ transferred or disposed of.
I R the manufacturer or other person holding               (10) Shall comply with the provisions a specific license pursuant to Parts 30 and     of 9 j 20.400 and 20.403 of this chapter 32 of this chapter or from an Agreement       for reporting radiation incidents, theft or loss of licensed material, but shall be State to repair such devices, or disposed of by transfer to a person authonzed by a exempt from the other requirements of Parts 19,20. and 21* of this chapter, specific license to receive the byproduct material contained in the device and,
number of device transferred, the name and address of the transferee, and the
* Amended 4: FR :8891 t Amended 43 FR 6915.
~
September 1,1978                                                 g l
(5) bpon the occurrence of a failure of or damage to, or any indication of a name and/or position of an individual wno may constitute a point of contact possible failure of or damage to, the between the Commission and the trans-shielding of the radioactive material or the on off mechanism or indicator, or I"f"; 0f (ii) Where the device is held in storage
. upon the detection of 0.005 microcune the original shipping container at its k or more removable radioactive material, ended location of use prior to initial
' shall immediately suspend operation of I
E the device until it has been repaired by use by a generallicensee.
R the manufacturer or other person holding (10) Shall comply with the provisions a specific license pursuant to Parts 30 and of 9 j 20.400 and 20.403 of this chapter for reporting radiation incidents, theft or 32 of this chapter or from an Agreement loss of licensed material, but shall be State to repair such devices, or disposed exempt from the other requirements of of by transfer to a person authonzed by a Parts 19,20. and 21* of this chapter, specific license to receive the byproduct material contained in the device and, Amended 4: FR :8891 t Amended 43 FR 6915.
September 1,1978 g
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KAY NAY INC.
KAY NAY INC.
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i
            'NN5 TRIAL PROCESS CON 1ROL EQUIPMENT 516 West Campus Drive e Arlington Heignts. Illinois 60004 * (312) 259 5600 e TELEX: 281 085 e CABLE: KAYRAY                                                                             j J6ne 30, 1978 Dear Sir; In follow-up to our letu . of March 6, 1978, (copy attached) we                                                                                                                       !
~
wish to advise you of'adda.ional action taken by Kay-Ray concern-ing the referenced source head structural problem. These rare failures have not resulted in any definable radiation overexposure to plant personnel, but we believe that every reasonable precaution should be undertaken.
'NN5 TRIAL PROCESS CON 1ROL EQUIPMENT 516 West Campus Drive e Arlington Heignts. Illinois 60004 * (312) 259 5600 e TELEX: 281 085 e CABLE: KAYRAY j
Kay-Ray has developed a support bracket that can be simply added by your maintenance people to your source heads which will prevent the dome from separating from the head if a weld fracture should                                                                                                                   i occur.                  This bracket substantially reduces the possibility of a radiation hazard developing by keeping the lead dome attached to the source head independently of the welding. The attached drawing illustrates'the brackets that have been designed to be compatible with the different variations of source heads in this family.                                                                                         The bracket can be easily added to your source head in less than fifteen minutes, while the head is in normal operation. No process downtime is required.
J6ne 30, 1978 Dear Sir; In follow-up to our letu. of March 6, 1978, (copy attached) we wish to advise you of'adda.ional action taken by Kay-Ray concern-ing the referenced source head structural problem.
To encourage use of this safety feature, Kay-Ray will supply this bracket free of charge at your request. Please s fill out the attach-ed card to confirm the specific source heads presently installed at your facility so that the proper bracket and instructions can be.sent.
These rare failures have not resulted in any definable radiation overexposure to plant personnel, but we believe that every reasonable precaution should be undertaken.
In closing, we would like to emphasize the importance of this safety precaution. We hope to hear from your shortly.
Kay-Ray has developed a support bracket that can be simply added by your maintenance people to your source heads which will prevent the dome from separating from the head if a weld fracture should i
This bracket substantially reduces the possibility of a occur.
radiation hazard developing by keeping the lead dome attached to the source head independently of the welding.
The attached drawing illustrates'the brackets that have been designed to be compatible with the different variations of source heads in this family.
The bracket can be easily added to your source head in less than fifteen minutes, while the head is in normal operation.
No process downtime is required.
To encourage use of this safety feature, Kay-Ray will supply this bracket free of charge at your request.
Please fill out the attach-s ed card to confirm the specific source heads presently installed at your facility so that the proper bracket and instructions can be.sent.
In closing, we would like to emphasize the importance of this safety precaution.
We hope to hear from your shortly.
Sincerely, KAY-RAY, INC.
Sincerely, KAY-RAY, INC.
C. Grabowski National Service Manacement
C. Grabowski National Service Manacement I
* I
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                                                                                                                                                              \ ,' ' y 4                            ;
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WO5tLDw1OE SALES AND SERVICE OFFICES:
y WO5tLDw1OE SALES AND SERVICE OFFICES:
Atnca e Argentina e Austraha e Benelun e Brazil e Canada e Chile
Atnca e Argentina e Austraha e Benelun e Brazil e Canada e Chile
* Columtna e France                                                                         i                       m G:rmany
* Columtna e France i
m G:rmany
* Indonesia e my e Japan e Mexico e New Zealand
* Indonesia e my e Japan e Mexico e New Zealand
* Peru e Scandinavia e Spain Scuin Afnca e Unned Angcom . Venezueia
* Peru e Scandinavia e Spain Scuin Afnca e Unned Angcom. Venezueia
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Latest revision as of 12:46, 11 December 2024

Forwards IE Bulletin 78-13 to City of Lancaster,Pa & Martin Elec Svc,Inc.(See ANO:7811060166)
ML20148F563
Person / Time
Issue date: 10/27/1978
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Judith Weaver
LANCASTER COUNTY, PA
References
NUDOCS 7811090075
Download: ML20148F563 (5)


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UNITED STATES c

.,k NUCLEAR REGULATORY COMMISSION 5[,jPlj y '!D REGICN 1 y/ - : [

631 P ARK AVENUE f-xtNo oF PRUSSI A, PENN5YL,V ANI A 19406

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ov October 27, 1978

  • ..s City of Lancaster Martin Electrical Services, Inc.

c/o Water Filtration Plant ATTN:

John Weaver Columbia, Pennsylvania 17512 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 Xay-Ray, Incorporated.

There gauges contain radioactive material regulated by the NRC.

The possession and use of the radiccctive material contained in the gauges -is governed by either a specific NRC license issued to you or under the gereral 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 regu-lation 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, f

'thw oyce

. Grier Director

Enclosures:

1.

IE Bulletin No. 78-13 2.

List of IE Bulletins Issued in 1978 CONTACT:

Robert 0. McClintock (215)337-5206 f/

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l l

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 IE Bulletin No. 78-13 Date: October 27, 1978 Page 1 of 2 FAILURE IN SOURCE HEADS OF KAY-RAY, INC., GAUGES MODELS 7050, 7050B, 7051, 7051B, 7060, 70608, 7061, AND 7061B Description of Ci. cumstances:

The U.S. Nuclear Regulatory Commission (NRC) has received information that on 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 radioactive material in tne yuges is 9,0verned 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 In one case, the radioactive source itself fell loose from the source.

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 de-veloped 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.

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 tele-phone number, complete the other actions according to the instruc-tions, and sign the preaddressed form and return it to the NRC after completing all the required actions.

TE Bulletin No. 78-13 Date:

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 provide 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, 70508, 7051, 7051B, 7060, 70608, 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.

l In addition to the above specific actions, we recommend that you read i

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

l IE Bulletin No. 78-13 October 27,.1978 Page 1 of 2 LISTING OF IE BULLETINS t

ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.

78-01 Flammable Contact -

1/16/78 All Power Reactor i

Arm Retainers in G.E.

Facilities with an CR120A Relays Operating License (OL) or

~,

Construction Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an OL or CP 78-03

~ Potential Explosive 2/8/78 All BWR Power l

Gas Mixture Accumula-Reactor Facilities

~

tions Associated with with an OL or CP BWR Offgas System Operations 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X i

78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78' All Power' Reactor l

by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all Class E and F j

Research Reactors with aa OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees i

. - _ _ _ _ _.. _. _. -., _ _ _.. ~ _. _..

m IE Bulletin No. 78-13 October 27, 1978 Page 2 of 2 LISTING 0F IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.

78-08 Radiation Levels from 6/12/78 All Power, Test, and Fuel Element Transfer Research Reactor Tubes Facilities with an OL having Fuel Element Transfer Tubes.

78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL (for action)

Closures or CP (for information).

78-10 Bergen-Paterson 6/27/78 All Power Reactor Hydraulic Shock Facilities with an Suppressor Accumulator OL or CP Spring Coils 78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action:

Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee.

All other BWR Power Reactor,

Facilities with an OL for information.

78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP.

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 4

Licensee Name:

Address:

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Telephone:

If you possess the gauges under a specific NRC license, enter the license number:

1.

If you have transferred or otherwise disposed of any Kay-Ray gauges, place a check or mark in the box and provide the

/

/

information required by action item 2 in the Bulletin instructions.

Complete the following for Kay-Ray gauges in your possession:

2.

Date the card was mailed to Kay-Ray, Inc., confirming the (date) specific source heads in your possession.

3.

Number of source heads visually inspected for evidence of weld cracks between the dome and box on models 7050, 70508, (number) 7051, 7051B, 7060, 70608, 7061, and 70618.

4.

Number of source..eads inspected in the items above which (number)

Ead weld cracks.

5.

Date support brackets were received from Kay-Ray.

(date) 6.

Date installation of support brackets was completed.

(date)

Signature and printed name of responsible individual or Radiation Safety Officer.

After completing the above actions and entering the required information,

. sign the form, fold it so that the NRC return address is showing, tape or staple closed and place in the mail.

No postage is required.

e UNITED STATES f

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NUCLE AR REGULATORY COMMISSION Postaos ano rass paso

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OP PICI AL SUSINESS Comuassson PEN ALTY POR PRIV ATE USE, $300 L

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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION & ENFORCEMENT REGION I 631 PARK AVENUE KING OF PRUSSIA, PA 19406 f

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UNITED STATES NUCLEAR RE@ULATORY COMMISSION RULES and REGULATIONS TITI.E 10, CHAPTER 1. CODE OF PEDERAL REGULATIONS-ENERGY PART GENERAL DOMESTIC LICENSES FOR BYPRODUCT MATERIAL i

1

. 31 I

manufactured for the purpose of '

S* *-

31.3 Certain devices and equipment.

detecting, measuring, gauging or 31.1 Purpose and scope.

31.2 Terms and conditions.

A general license is hereby issued to controlling thickness, density, level, inter-31.3 Certain devices and equipment.

transfer receive, acquire, own, possess and 31.s certain mensunas, sauses or contromas use byproduct material incorporated in qualitative or quantitative chemical

devices, the following devices or equipmcat which composition, or for producing light or an 31.6 General license to install devtces sen-erally 11 censed in 6 31.5.

have been manufactured, tested and iot'ized atmosphere.

31.7 Lu u safety devtcu for un in labeled by the manufacturer in ac-N N p u n! &

Mp ph ccrdance with the specifications con-(a) f this secti n applies only to by-31.a Amancium 241 in the form of calibre-tained in a specific ticense issued to him tion or reference sources.

product matenal Contained in devices

. by the Commission.

which have been manufactured or 31.9 General license to own byproduct me.

(a) Static climination device. Devices nitially transferredt and labeled in ac-tenal.

31.10 General licenu for strontium-90 in ic' 2 designed for use as static eliminators Ewhich contain, as a sealed source or mdang M q spe&ah con-d* " " d"i*"*

tained in a specific hcense issued pursuant for um of byproduct u. sources, byproduct material consisting of 31.1 General 11cenu to @ 32.51 of this chapter or in ac-materista for certain in vitro clinical g a total of not more than 500 microcunes cordance with the specifications con-or taboratory testins.

tained in a specific license issued by an b) eted 34 FR 51.1 Agreement State which authorizes (c) [ Deleted 35 FR 3982.)

n n f cM t pe m ns (d) lon genentting tube. Devices de, signed for ionization of air which contam, I*"

ate.

as a scaled source or sources, byproduct j material consisting of a total of not more

  • E

~@ 31.1 Purpose and scope, than 500 microcuries of polonium-210 f E **"*"'

This part establishes general licenses per device or of a total of not more than R *e*ne*d kenn 6 pawa$ W M h g

j for the possession and use of byproduct 50 millicuries of hydrogen-3 (tritium) per material contained in certain items and a device.

g

~

' general license for ownership of by-

@ 31.4 (Deleted 36 FR 16898-)

to the device at the time of receipt and N product material. Part 30 of this chapter

  • " urin g, Sauging or beanng a statement that removal of the also contains provisions applicable to the Iling devices s label is prohibited are maintained thereon n

subject matter of this part.

(a) A general heense is hereby issued and shall comply with allinstructions and 31.2 Terms and conditions.

to commercial and industrial firms and precautions provided by such labels; g

(a) The general licenses provided in W research, educational and medicalinstitu-(2) Shall assure that the device is R this part are subject to the provision of l tions, individuals in the conduct of their tested for leakage of radioactive matenal E @ @ 30.14(d), 30.34(a) to (e), *30.41, u business, and Federal, State or local and proper operation of the on-off E overnment agencies to acquire, receive, mechanism and indicator, if any, at no 6 30.51 to 30.63 and Parts 19,20, and 21t g

E of this chapter unless indicated other.

possess, use or transfer, in accordance longer than six-month intervals or at such wise in the language of the general li.

with the provisions of paragraphs (b),(c) other intervals as are specified in the and (d) of this section, byproduct ma-label; however; Jense.

tenal contained in devices designed and (i) devices containmg only krypton At tention is directed particularly to the need not be tested for leakage of radio-provuions of the regulations in Part to of this

' Persons possessms byproduct :naterial in chapter wnich relate to the labeling of con. Jevices under the senerat license in i 31.s active matenal, and before Jan. I s.19-s may continue to possess, (ii) devices containing only tntium or iainers.

use or transfer that matenal in accordance with not more than 100 microcuries of other Amended 38 FR 33968.

I 1.5 in e et n Jan.14

  • [umnents beta and/or gamma ermttmg matenal or i Amended 43 FR 6915.

31-1 September 1,1978

PART 31 o GENERAL DOMESTIC LICENSES FOR BYPRODUCT MATERIAL J

10 microcunes of alpha emitting material; within 30 days, furnish to the Director of (d) The general license in paragraph and devices held in storage in the original the appropriate Nuclear Regulatory Com-(a) of this section does not authorize the shipping container prior to initialinstalla.

mission Inspection and Enforcement manufacture or import of devices tion need not be tested for any purpose; Regional Office listed in Appendix D of containing byproduct material.

~

(3) Shall assure that the tests required Part 20 of this chapter, a report contain-by paragraph (c)(2) of this section and ing a brief description of the event and other testing, installation, servicing, and the remedial action taken; removal from installation involving the (6) Shall not abandon the device radioactive materials, its shielding or containing byproduct matenal; containment, are performed:

(7) Shall not export the device N

(i) in accordance with the instructions containing byproduct material except in 6 provided by the labels;or accordance with Part 110 of this s

(ii) by a person holding a specific chapter;t

{ license pursuant to Parts 30 and 32 of (8) Except as provided in paragraph this chapter or from an Agreement State (c)(9) of this section, shall transfer or to perform such activities; dispose of the device containing by-(4) Shall maintain records showing product material only by transfer to a compliance with the requirements of person holding a specific license pursuant paragraphs (c)(2) and (c)(3) of this sec-to Parts 30 and 32 of this chapter or from tion. The records shall show the results of an Agreement State, to receive the device tests. The records also shall show the and within 30 days after transfer of a dates of performance of, and the names device to a specific licensee shall furnish of persons performing, testing, installa-to the Director of Nuclear Material Safety tion, servicifts, and removal from installa-and Safeguards, U.S. Nuclear Regulatory tion concerning the radioactive material, Commission, Washington, D.C. 20555, a

_its shielding or containment.

report containing identification of the device by manufacturer's name and Records of tests for leakage of radio-active material required by paragraph.model number and the name and address k of the person receiving the device. No (c)(2) of this section shall be maintained, report is required if the device is trans-for one year after the next required leak f ferred to the specific licensee in order to test is performed or until the scaledR obtain a replacement device; source is transferred or disposed of.

(9) Shall transfer the device to g Records of tests of the on-off mechanism another generallicensee only:

. and indicator, required by paragraph (i) Where the device remains in use at g (c)(2) of this section, shall be maintained a particular location. In such case the

"" for one year after the next required test transferor shall give the transferee a copy

  • of the on-off mechanism and indicator is of this section and any safety documents performed or until the sealed source is dentified in the label of the device and transferred or disposed of. Records which within 30 days of the transfer, report to are required by paragraph (c)(3) of this the Director of Nuclear Material Safety section shall be maintained for a period and Safeguards, U.S. Nuclear R'egulatory of two years from the date of the Commission, Washington, D.C. 20555, recorded event or until the device is the manufacturer's name and model

_ transferred or disposed of.

number of device transferred, the name and address of the transferee, and the

~

(5) bpon the occurrence of a failure of or damage to, or any indication of a name and/or position of an individual wno may constitute a point of contact possible failure of or damage to, the between the Commission and the trans-shielding of the radioactive material or the on off mechanism or indicator, or I"f"; 0f (ii) Where the device is held in storage

. upon the detection of 0.005 microcune the original shipping container at its k or more removable radioactive material, ended location of use prior to initial

' shall immediately suspend operation of I

E the device until it has been repaired by use by a generallicensee.

R the manufacturer or other person holding (10) Shall comply with the provisions a specific license pursuant to Parts 30 and of 9 j 20.400 and 20.403 of this chapter for reporting radiation incidents, theft or 32 of this chapter or from an Agreement loss of licensed material, but shall be State to repair such devices, or disposed exempt from the other requirements of of by transfer to a person authonzed by a Parts 19,20. and 21* of this chapter, specific license to receive the byproduct material contained in the device and, Amended 4: FR :8891 t Amended 43 FR 6915.

September 1,1978 g

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KAY NAY INC.

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'NN5 TRIAL PROCESS CON 1ROL EQUIPMENT 516 West Campus Drive e Arlington Heignts. Illinois 60004 * (312) 259 5600 e TELEX: 281 085 e CABLE: KAYRAY j

J6ne 30, 1978 Dear Sir; In follow-up to our letu. of March 6, 1978, (copy attached) we wish to advise you of'adda.ional action taken by Kay-Ray concern-ing the referenced source head structural problem.

These rare failures have not resulted in any definable radiation overexposure to plant personnel, but we believe that every reasonable precaution should be undertaken.

Kay-Ray has developed a support bracket that can be simply added by your maintenance people to your source heads which will prevent the dome from separating from the head if a weld fracture should i

This bracket substantially reduces the possibility of a occur.

radiation hazard developing by keeping the lead dome attached to the source head independently of the welding.

The attached drawing illustrates'the brackets that have been designed to be compatible with the different variations of source heads in this family.

The bracket can be easily added to your source head in less than fifteen minutes, while the head is in normal operation.

No process downtime is required.

To encourage use of this safety feature, Kay-Ray will supply this bracket free of charge at your request.

Please fill out the attach-s ed card to confirm the specific source heads presently installed at your facility so that the proper bracket and instructions can be.sent.

In closing, we would like to emphasize the importance of this safety precaution.

We hope to hear from your shortly.

Sincerely, KAY-RAY, INC.

C. Grabowski National Service Manacement I

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$16 West Camous 3rin. Attington Stats. Ininers W Please send i: nediately the brackets listed belew:

Ocapany Name:

Shipping Address:

Name:

Street:

_4._.,. e Ci tv. /s tate :

Special Shipping :'nstructions:

No.cf Eds.

Source Ed. Mod. No. (s )

Scurce Rd. Ser.No. (s )

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