ML20148E399

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Forwards IE Bulletin#78-13.(See ANO:7811060166.)
ML20148E399
Person / Time
Issue date: 10/27/1978
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
USX CORP. (FORMERLY UNITED STATES STEEL)
References
NUDOCS 7811070006
Download: ML20148E399 (5)


Text

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.'.E REGION I 631 PARK AVENUE o .If? # KtNG OF PRUSSIA, PENN5Yt.V ANI A 19406

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U. S. Steel Corp.

Fairless Works ATTN: Chief Instrumentation Engr.

Fairless Hills, Pennsylvania 19030 Gentlemen:

The enclosed Nuclear Regulatory Commission (NRC) IE Bulletin No. 78-13 requires action by you with respect to certain gauging devices in your pcssession. 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 regu-laticn 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, h'

ooyce H. Grier

' Director

Enclosures:

1. IE Bulletin No. 78-13
2. List of IE Bulletins Issued in 1978 CONTACT: Robert 0. McClintock (215) 337-5206 781107000 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, T 7051, 7051B, 7060, 70608, 7061, AND 7061B Description of Circumstances: ,

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 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 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 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 I 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  :

af ter completing all the required actions.

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. . l TE Bulletin No. 78-13 i Date: October 27, 1978 I Page 2 of 2 l 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 I comply, with the requirements of 10 CFR 31.5(c)(8) or (9) and l 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 i you complied with the requirements of 10 CFR 30.41 and provide the l name and address of the persons or organizations to whom the gauge <

I 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.

In addition to the above specific actions, we recomend 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 GA0 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

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w e- -=m%4# .%hR-IE Bulletin No. 78-13 October 27, 1978 Page 1 of 2 LISTING OF IE BULLETINS ISSUED IN 1978 8ulletin 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 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 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 78-06 Defective Cutler- 5/31 /78 All Power Reactor "

i Hammer, Type M Relays Facilities with an '

With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor r by Air-Line Respirators Facilities with an  :

and Supplied-Air Hoods OL, all Class E and F Research Reactors with an OL, all Fuel Cycle

' Facilities with an OL, and all Priority 1 Material Licensees i

i

IE Bulletin No. 78-13 October 27, 1978 .

Page 2 of 2 LISTING OF IE BULLETINS ISSUED IN 1978

)

Bulletin Subject Date Issued Issued To

.No. t 78-08 Radiation Levels from 6/12/78 All' Power, Test, and 1 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 t Cities 1 and 2, Hatch 1, Monticello and >

Vermont Yankee. All other BWR Power Reactor Facilities with an OL r 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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0FFICE 3F INSPECTION AND ENFORCEMENT b

Licensee Name:

Address:

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v.eei .in .N:' .

Telephone:

If you possess the gauges under & 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 specific source heads in your possession. (date) -
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 heads inspected in the items above which (numoer) had weld cracks.
5. Date support brackets were received from Kay-Ray.

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6. Date installation of support brackets was completed.

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

After completing the above actions and entering the required information,  !

sign the fc rm, fold it so that the NRC return address is showing, tape or l staple clot:ed and place in the mail. No postage is required.

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UNITED ST ATES F ]i NUCLEAA REGULATORY COMMISSION POST AGE Amo Fast Pato r u.s. mWCLsam asswbaTom?

CFFICI AL SustNEss consene ssa em Pf h ALTY FOR PatgV ATE USE.1300 J L .

U. S. NUCLEAR REGULATORY COMMISSION  :

OFFICE OF INSPECTION & ENFORCEMENT REGICN i 631 PARK AVENUE KING OF PRUSSIA, PA.19406 e

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UNITED STATES NUCLEAR REEULATORY COMMISSIGN RULES and REGULATIONS TITLE 10, CHAPTER 1, CODE OF PEDERAL REGULATIONS-ENERGY PART GENERAL DOMESTIC LICENSES FOR SYPRODUCT MATERIAL i

31 8**-

manufactured for the purpose of

{ 31.3 Certain devices and equipment. detecting, measuring, gt.uging or 31.1 Purpuna and scope-31.2 Terms and conditions. A general h. cense is hereby issued t controHing thickness, density, level, inter-

  • 31.3 certain devices and equipment.

31.s certain meneurtas, sausins or controding transfer receive, acquire, own, possess and use byproduct material incorporated in qualitative or quantitative chemical devices. the following devices or equipment which 31.6 General usenee to instan devices sen- composition, or for producing light or an erauy tacensed in 131.s. have been manufactured, tested and ionized atmosphere.

31.7 1.u afety devica for use in labeled by the manufacturer in ac- , gg g g cordance with the specifications con-

t. (a) o thi8 8ec o applies only to by-31.s Anierteium-341 in the form of caHbre- tained in a specifl3 license issued to him tion or reference sources, product material contained in devices 31.9 General ticense to own byproduct me. by the Commission. . which have been manufactund or teriet. g (a) Stane eliminarfon device. Devices initially transferredt and labeled in ac-31.10 General license for strontium-90 in ice -designed for use as static eliminators emdance with de speericatens en-
    • '***" d*'**- Ewhich contain, as a sealed source or tained in a specific license issued pursuant 31.1 General tacense for um of byproduct u. sources, byproduct material consisting of materiais for certain in vitro clinical g to { 32.51 of this chapter or in ac-or laboratory tutins. a total of not more than 500 microcuries cordance with the specifications con-ta ed in a sp se Scense inued W an ted 3 FR 6 51.1 ^ 8'"
  • e n t State which authorizes (c) (Deleted 35 FR 3982.1 uu.on of the devices to persons (d) lon generating tube. Devices de- genera y , ense signed for ionization of air which contain, W e Agne nent as a sealed source or sources, byproduct "

material consisting of a total of not more

^"I 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 2 8*'* * *
  • E*"

g for the possession and use of byproduct 50 minicuries of hydrogen-3 (tritium) per

  • g material contained in certain items and a ~

device.

  • general license for ownership of by- @ 31.4 [ Deleted 36 FR 16898-) to the device at the time of receipt and 8 product material. Part 30 of this chapter .5 Cntain measuring, gauging or bearing a statement that removal of the also contains provisions applicable to the nerolling devices.* label is prohibited are maintairied thereon subject matter of this part. (a) A general license is hereby issued and shall comply with allinstructions and 31.2 Terms and conditions. g to commercial and industrial firms and precautions provided by such labels; o (a) The general licenses provided in $ research, educational and medicalinstitu- (2) Shall assure that the device is tested for leakage of radioactive material 2 this part are subject to the provision of } tions, individuals in the conduct of their and proper operation of the on-off E @ l 30.14(d), 30.34(a) to (e), *30.41, ' business, and Federal, State or local mechanism and indicator, if any, at no
  • 30.51 to 30.63 and Parts 19,20, and 21t E government agencies to acquire, receive, 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;

, sense.

terial contained in devices designed and (i) devices containing only krypton

  • Attention is directed particularly to the need not be tested for leakage of radio- '

provisions of the regulations m Part *0 of this 8

Persons possessms byproduct material in active mater:al, and charter which relate to the labetins of con. devices under the seneral license in g 31.s tamers.

before Jan. 15.1975 may conimue to possess. (ii) devices containing orily tritium or '

use or transfer that matenalin accordance with not more than 100 microcunes of other Amended 38 FR 3396a. the fequirements of i 31.s in effect on Jan.14 t Amended 43 FR 69 s. g 73, l

l 31 8 September 1,1978 l

PART 31 o CENERAL DOMESTIC LICENSES FOR BYPRSDUCT MATERIAL . m 10 microcuries of alpha emitting matenal within 30 days, furnish to the Director of (d) The general license in paragraph and devices held in storage in the ongmal the appropnate Nuclear Regulatory Com- (al of this section does not authorize the shipping container prior to initialinstalla. mission Inspection and Enforcement manu facture 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 material; containment, are performed: (7) Shall not export the device E (i) in accordance with the instructions containing byproduct matenal except in 6 provided by the labels;or accordance with Part i10 of this e (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 rnaintain 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 shc w 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, servicing, 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

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device by manufacturer's name and Records of tests for leakage of radio- modal number and the name and address '

active material required by paragraphh 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 g ferred to the specific licensee in order to test is performed or until the sealed R 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:

e and indicator, required by paragraph (i) Where the device remains in use at e (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 indic; tor is of this section and any safety documents performed or until the sealed source is identified 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. 205 55, recorded event or until the device is the manufacturer's name and model

, transferred or disposed of, number of device transferred, the name

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(5) (spon the occurrence of a failure and address of the transferee, and the of or damage to, or any indication of a name and/or position of an individual possible failure of or damage to, the who may constitute a point of contact shielding of the radioactive material or between the Commission and the trans-I"; 0f the on-off mechanism or indicator, or upon the detection of 0.005 microcurie (ii) Where the device is held in storage in the original shipping container at its

@ or more removable radioactive material. intended location of use prior to initial

! shall immediately suspend operation of I 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 { 20.402 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 authorized 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,

September 1,1978

YN/\ g - KAY-NAY INC.

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-A 1 B 'NO.STRIAL PRO !SS CONTROL ECWPMENT 516 West Carnpus Drive

  • Ariegton Heights. !!!inces 60004 * (312) 259-5600
  • TELEX: 781.C85
  • CABLE: KAYRAY J ne 30,1978 Dear Sir; In follow-up to our letter of March 6, 1978, (copy attached) we wish to advise you of additional 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 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

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with the dif ferent variations of source heads in this family. The bracket can be easily added to your source head in less than fif teen minutes, while the head is in normal operation. No process downtime is required.

To enecurage use of this safety feature, Kay-Ray will supply this bracket free of charge at your request. Please sfill out the attach-ed card to confirm the specific source heads presently installed at your facility so that the preper bracket and instructicns can be sent.

In closing, we would like to emphasize the importance of this safety precaution. We hope to hear frem your shortly.

Sincerely, KAY-RAY, INC.

  • mLD C. Grabowski Naticnal Service Manacement s* % w.3Q.

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Postage Will Be Paid By KA Y-RA Y INC.

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Please send i= mediately the brackets listed below:

Company Name: Ship *- ng Address:

1 Name: Street:

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Title:

City / State:

l Special Shipping Instructions:

Source Rd. Mod.No.(s) No.cf Eds.

Source Ed. Ser .No. (s) l 1

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