Information Notice 1995-58, 10 CFR 34.20; Final Effective Date

10 CFR 34.20; Final Effective Date

ML031060175
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	12/18/1995
From:	Cool D NRC/NMSS/IMNS
To:
References
IN-95-058, NUDOCS 9512180076
Download: ML031060175 (15)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS

WASHINGTON, D.C. 20555 December 18, 1995 NRC INFORMATION NOTICE 95-58: 10 CFR 34.20; FINAL EFFECTIVE DATE

Addressees

-

Purpose

The U.S. Nuclear Regulatory Commission is issuing this information notice (IN)

to remind addressees of the effective date implementing a final provision of

the regulations in 10 CFR 34.20. It is expected that recipients will review

the information for applicability to their facilities and consider appropriate

actions. This notice also advises recipients of the Commission's plans for

enforcement action to address failures to meet 10 CFR 34.20. However, this IN

does not contain any new requirements; therefore, no specific action or

written response is required.

Background:

Paragraph (e)of 10 CFR 34.20 provides that all radiographic exposure devices

and associated equipment in use by NRC licensees after January 10, 1996, must

comply with the requirements specified in Section 34.20 of 10 CFR Part 34.

Section 34.20, and other changes to 10 CFR Part 34, were published in the

Federal Register (55 FR 843) as a final rule on January 10, 1990. As stated

in the Federal Register notice, the effective date of the final rule was

January 10, 1991. Paragraph (d)of 10 CFR 34.20 provided that all newly- manufactured radiographic exposure devices and associated equipment

(manufactured after January 10, 1992) acquired by NRC licensees must meet

10 CFR 34.20 requirements. The statement of considerations for the final rule

provided notice that failure to implement the requirements for equipment by

the required date may be considered a Severity Level III Violation. Such

violations are considered for civil penalty assessments.

After publication of the final rule, NRC transmitted copies of the notice to

each of its radiography licensees at that time. Copies of the notice were

also provided to each of the Agreement States so that they might share the

information with their radiography licensees. Further information identifying

and explaining the effective dates of the various provisions of the rule was

also provided in the March-June 1990 (NUREG/BR-0117 Nos. 90-1 and -2) issues

of the EKS_ Licensee Newsletter.

9512180076 POR U E P ^t1C~t. 9-T-NQ5

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IN 95-58 December 18, 1995 Discussion:

The NRC reminds its industrial radiography licensees that after January 10,

1996, only radiographic exposure devices and associated equipment which

complies with the requirements specified in 10 CFR 34.20 and is authorized by

the license, shall be used in industrial radiography operations conducted

within NRC's jurisdiction. NRC also reminds Agreement State licensees working

in areas of NRC Jurisdiction under reciprocity (10 CFR 150.20) that they are

also subject to these requirements. The regulations in 10 CFR 34.20 apply to

all radiography equipment. This includes portable, mobile, and fixed

radiography cameras (both pipeliner and 'crank-out' type devices), source

changers, and other associated equipment used with radiography cameras, i.e.,

source assemblies, drive cables, guide tubes, control tubes, source stops, etc. Some provisions of 10 CFR 34.20 only apply to certain types of

equipment. For example, 10 CFR 34.20(c) only applies to 'crank-out' cameras, while 10 CFR 34.20(a) and (b) apply to all radiography cameras and all

associated equipment. As another example, the criteria specified in 10 CFR

34.20(c)(9) only applies to the source changer used in conjunction with a

'crank-out' device.

The requirements in 10 CFR 34.20 require licensees to ensure that all

equipment they will use in radiographic operations after January 10, 1996, complies with the applicable requirements. Since publication of NRC's final

rule, the radiography equipment manufacturers have worked to develop

radiography devices and associated equipment that complies with 10 CFR 34.20

criteria. In some instances, existing equipment already complies with the

regulatory requirements. Attachment 1 lists the radiography cameras, radiography systems, and sealed sources that have been recognized by NRC as

meeting 10 CFR 34.20 requirements.

Traditionally, certain associated equipment has not been independently

registered and/or evaluated by the NRC or the Agreement States. This includes

drive cables, guide tubes, or source stops. With the new camera models

introduced, the manufacturers and NRC have taken the system approach as

denoted in the American National Standard N432-1980, 'Radiological Safety for

the Design and Construction of Apparatus for Gamma Radiography,' now required

by regulations. Therefore, information concerning the drive cables to be used

with the devices was included as part of the overall system evaluation.

However, older 'associated equipment' items may not have been evaluated as

part of a device registration process. Licensees are reminded that 10 CFR

34.20 makes the licensee responsible for ensuring that the equipment meets

regulatory requirements. The licensee should obtain information from the

equipment manufacturer which shows the equipment complies with 10 CFR 34.20

criteria, including any required testing. Equipment that has not been

registered will, at minimum, require prototype testing to meet the

requirements of 10 CFR 34.20. If a similar piece of equipment has already met

the test requirements. then an engineerina analysis may be used in lieu of

actual testing. The engineering analysis can be performed by the user or the

manufacturer and submitted to the appropriate regulatory authority for

evaluation and approval.

'NyJ

IN 95-58 December 18, 1995 Your present license may include equipment whose use must be discontinued

after January 10, 1996. In this instance, the NRC regulations effective

January 10, 1996, take precedent over authorizations previously provided in a

license. For example, if your license contains an Amersham Model 900, you are

not authorized to continue using this device after January 10, 1996. Please

also note that you may need to amend your license to include additional

equipment that complies with 10 CFR 34.20. .

Exemptions will not normally be considered for portable radiographic devices

that do not comply with 10 CFR 34.20. If uninterrupted use of a device which

does not comply with 10 CFR 34.20 is intended, then an exemption request

should be submitted prior to January 1, 1996, to allow the staff adequate time

to process the request. Exemptions to 10 CFR 34.20 may be considered only for

limited special or unique cases, where the licensee can demonstrate that the

engineered safety features, use limitations, and procedures would compensate

for not meeting the requirements and afford similar or increased radiation

safety protection. An example of a limited special or unique case would

include a nonportable device used in a fixed radiographic facility.

Performance of radiography after January 10, 1996, with equipment which does

not comply with the requirements of 10 CFR 34.20 is a violation of Commission

requirements. In accordance with example C.8 of Supplement VI of the

Commission's Enforcement Policy, such violations are considered violations of

significant regulatory concern and may be categorized at Severity Level III

and subject to civil penalties. In light of the notice that has been given

licensees to meet this regulation, the time that has been provided licensees

to achieve compliance, and the importance of meeting the requirements of

10 CFR 34.20, the NRC intends to levy a civil penalty without considering the

normal civil penalty assessment process pursuant to Section VII.A.1 of the

Enforcement Policy. Accordingly, a civil penalty of $5,000, the base Severity

Level III civil penalty, may be assessed for each camera a licensee uses after

January 10, 1996, that does not meet the requirements of 10 CFR 34.20. If

during an inspection, the NRC identifies that a licensee is not meeting the

regulation, the licensee will need to suspend an) operation with nonconforming

cameras. Failure to do so may be considered deliberate violations and may

subject the licensee to significant civil action, including license

revocation, and to.criminal sanctions. Individuals responsible for such

violations may be subject to sanctions for violating 10 CFR 30.10, rule on

Deliberate Misconduct.'

However, the Commission intends to exercise its enforcement discretion for

licensees who make a good faith effort to comply with 10 CFR 34.20 before the

effective date of the rule. Therefore, a licensee who performs radiography

after January 10, 1996, with equipment that does not meet 10 CFR 34.20 will

not be subject to civil penalties or suspension of operations for such

violations if the licensee has evidence that on or before January 10, 1996, it

in good faith ordered equipment for prompt replacement that meets the

requirements of 10 CFR 34.20. It should be noted that Agreement State

licensees conducting radiography under reciprocity will be subject to these

regulatory requirements and enforcement policy.

IN 95-58 December 18, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate regional office.

2:)M1A111'4, 6$

Donald A. Cool, Director

Division of Industrial and

Medical Nuclear Safety

Office of Nuclear Material

Safety and Safeguards

Contacts: J. Bruce Carrico, NMSS (For general information)

(301) 415-7826 Thomas W. Rich, NMSS (For device information)

(301) 415-7893 Attachments: 1. List of Approved Equipment

2. List of Recently Issued NMSS Information Notices

3. List of Recently Issued NRC Information Notices

4 A,4s ev 1i (A

Attachment 1 IN 95-58 December 18w, 1995 11/21/95 List of Models That Heet 10 CFR Part 34 Requirements

_________

CAMERtA(S)

Status Description

Model Manufacturer

ACTIVE Co-60 110mCi,

660 A AMERSHAM

Cs-137 10.8Ci, Yb-169 2OCi, Tm-170

200Ci, Ir-192 120Ci

AMERSHAM ACTIVE Co-60 l1OmCi,

660 AE Cs-137 10.$Ci, Yb-169 2OCi, Tm-170

200Ci, Ir-169 12OCi

AMERSHAM ACTIVE Co-60 llOmCi,

660 B Cs-137 10.8Ci, Yb-169 20Ci, Tm-170

200Ci, Ir-192 14OCi

AMERSHAM ACTIVE Co-60 llOmCi,

660 BE Cs-137 10.8Ci, Yb-169 2OCi, Tm-170

200CI, Ir-192 14OCi

AMERSHAM ACTIVE Co-60 llOmCi,

660 SYSTEM Cs-137 10.8Ci, Yb-169 2OCi, Tm-170

200Ci, Ir-192 14OCi

AMERSHAM ACTIVE Co-60 33OCi, DU 168

676 A kg

ACTIVE Co-60 330Ci, DU 168

676 AE AMERSHAM

kg

AMERSHAM ACTIVE Co-60 330Ci, DU 168

676 B kg

AMERSHAM ACTIVE Co-60 330Ci, DU 168

676 BE kg

ACTIVE Co-60 llOCi, DU 129

680 A AMERSEAM

kg

ACTIVE Co-60 llOCi, DU 129

680 AE AMERSHAM

kg

Attachment 1 IN 9F-58

-1-~

December 18, 1995 11/21/95 Requirements

List of Models That Meet 10 CFR Part 34

-____________________

CAMERA(S) (continued)

____________________

Manu-acturer Status Descript ion

Model

AMERSHAM ACTIVE Co-60 111DCi, DU 129

680 B kg

AMERSHAM ACTIVE Co-60 11' DCi, DU 129

680 BE kg

AMERSHAM ACTIVE Co-60 llCi, Ir-192

684 A 240Ci, DU 68 kg

AMERSHAM ACTIVE Co-60 llCi, Ir-192

684 AE 24OCi, DU 68 kg

AMERSHAM ACTIVE Co-60 llCi, Ir-192

684 B 240Ci, DU 68 kg

AMERSHAM ACTIVE Co-60 llCi, Ir-192

684 BE 240Ci, DU 68 kg

AMERSHAM ACTIVE Co.60 33Ci, Ir-192

741 A 24OCi, DU 90 kg

AMERSHAM ACTIVE Co-60 33Ci, Ir-192

741 AE 240Ci, DU 90 kg

AMERSHAM- ACTIVE Co-60 33Ci, Ir-192 J41. B 24OCi, DU 90 kg

AMERSHAM ACTIVE Co-60 33Ci, Ir-192

741 BE 240Ci, DU 90 kg

AMERSHAM ACTIVE Ir-192 240Ci, DU 18

865 kg

INDUSTRIAL NUCLEAR ACTIVE Ir-192 12OCi, DU

IR-100 14.5 kg

ACTIVE Ir-192 ISOCi, DU 17 SPEC 150 SPEC

kg

NORDION ACTIVE Ir-192 14OCi

TITAN

Attachment 1 IN 95- 58 December 18, 1995 11/21/95 List of Models That Meet 10 CFR Part 34 Requirements

SOURCE(S) (continued)

____________________

Manufacturer Status Description

Model

INDUSTRIAL NUCLEAR ACTIVE Ir-192 12OCi

32 ACTIVE Ir-192 12OCi

33 INDUSTRIAL NUCLEAR

ACTIVE Ir-192 12OCi

702 RTS

AMERSHAM INACTIVE Cs-137 3OCi, Yb-169

848 200Ci, Tm-170 5OCi, Ir-192 240Ci

AMERSEHAM ACTIVE Cs-137 30 Ci,

866 Yb-169 200Ci, Tm-170 5OCi, Ir-192

240Ci

AMERSHAM INACTIVE Ir-192 12OCi

87702 AMERSHAM ACTIVE Ir-192 12OCi

87703 AMERSHAM INACTIVE Ir-192 12OCi

87704 INDUSTRIAL NUCLEAR ACTIVE IR-192 120CI

88 AMERSHAM ACTIVE IR-192 240CI

89Si'

AMERSHAM ACTIVE IR-192 240CI

89912 AMERSHAM ACTIVE IR-192 240CI

89913 AMERSHAM ACTIVE IR-192 240CI

89914 AMERSHAM ACTIVE IR-192 240CI

89916 AMERSHAM ACTIVE IR-192 240CI

89921 AMERSHAM ACTIVE IR-192 240CI

89922 ACTIVE IR-192 240CI

89923 AMERSHAM

AMERSHAM ACTIVE IR-192 240CI

89924 AMERSHAM ACTIVE Ir-192 24OCi

90003

. -

Attachment 1 IN 95-58 December 18, 1995 11/21/95 List of Models That Meet 10 CFR Part 34 Requirements

____________________

SOURCE(S) (continued)

____________________

Manufacturer Status Description

Model

91810 AMERSHAM ACTIVE Yb-169 2OCi

91811 AMERSHAM ACTIVE Co-60 2OCi

91812 AMERSHAM ACTIVE Tm-170 2OCi

AMERSHAM ACTIVE Ir-192 2OCi

91813

943 AMERSHAM ACTIVE Co-60 llOCi

A424-1 AMERSHAM ACTIVE Co-60 220Ci, Yb-169

200Ci, Tm-170 50

Ci, Ir-192 240Ci

A424-10 AMERSHAM ACTIVE Co-60 5Ci

A424-11 AMERSHAM ACTIVE Co-60 5OCi

A424-12 AMERSHAM ACTIVE Co-60 lOOCi

A424-13 AMERSHAM ACTIVE Co-60 330Ci

A424-14 AMERSHAM ACTIVE Co-60 llOCi

A424-15 AMERSHAM ACTIVE Co-60 liCi

A424-16 AMERSHAM ACTIVE Co-60 5OCi

A424-17 AKERSHAM ACTIVE Co-60 sOCi

A424-18 AMERSHAM ACTIVE Co-60 33Ci

A424-19 AMERSHAM ACTIVE Co-60 120mCi

A424-2 AMERSHAM ACTIVE Co-60 220Ci, Yb-169

200Ci, Tm-170 5OCi, Ir-192 24OCi

AMERSHAM ACTIVE Cs-137 3OCi, Yb-169 A424-20

200Ci, Tm-170 5OCi, Ir-192 240Ci

I

-I

'7.I

Attachment 1 IN 95-58 December 18, 1995 11/21/95 CFR Part 34 Requirements

List of Models That Meet 10

SOURCE(S) (continued)

Status Description

Manufacturer

ACTIVE Co-60 22OCi, Cs-137 A424-22 AMERSHAM 10.8Ci, Yb-169

200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60 22OCi, Yb-169 A424-3 AMERSHAM 200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60 22OCi, Yb-169 A424-4 AMERSHAM 200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60 22OCi, Yb-169 A424-5 AMERSHAM 200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60 22OCi, Yb-169 A424-6 AMERSHAM 200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60 22OCi, Yb-169 AMERSHAM

A424-7 200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60.22OCi, Yb-169 AMERSHAM

A424-8 200Ci, Tm-170 5OCi, Ir-192 24OCi

ACTIVE Co-60 22OCi, Cs-137 AMERSHAM

A424-9 3OCi, Yb-169 200Ci, Tm-170 5OCi, Ir-192

240Ci

ACTIVE Co-60 22OCi, Yb-169 AMERSHAM

A453-1 200Ci, Tm-170 5OCi, Ir-192 240Ci

ACTIVE Co-60 220Ci, Yb-169 AMERSHAM

A453-2 200Ci, TM-170 5OCi, Ir-192 24OCi

f ~~'Attachment 1 IN 95-58 December 18, 1995 11/21/95 List of Models That Meet 10 CFR Part 34 Requirements

____________________

SOURCE(S) (continued)

---

Manufacturer Status Description

Model

AMERSHAM ACTIVE Ir-192 240Ci

A58101-8 SPEC ACTIVE Ir-192 lOOCi

B-16F

SPEC ACTIVE Ir-192 lOOCi

B-16T

NORDION ACTIVE Ir-192 14OCi

C-990

G-11F SPEC UNKNOWN

SPEC UNKNOWN

G-13F

G-15F SPEC UNKNOWN

SPEC UNKNOWN

G-17F Co-60 llOCi

G-19F SPEC ACTIVE

SPEC ACTIVE Ir-192 240Ci

G-1F

SPEC UNKNOWN

G-1T Co-60 llOCi

G-21F SPEC ACTIVE

SPEC ACTIVE Ir-192 240Ci

G-23 SPEC ACTIVE Ir-192 240Ci

G-36 SPEC ACTIVE Co-60 llOCi

G-37F

SPEC ACTIVE Ir-192 240Ci

G-38 SPEC ACTIVE Ir-192 240Ci

G-3F

SPEC ACTIVE Ir-192 24OCi

G-40F

SPEC ACTIVE Ir-192 240Ci

G-40T

SPEC ACTIVE Ir-192 240Ci

G-41F

SPEC ACTIVE Ir-192 240Ci

G-41T

SPEC UNKNOWN

G-42. SPEC

G-50F UNKNOWN

SPEC UNKNOWN

G-50T SPEC Ir-192 240Ci

G-£0 ACTIVE

Attachment 1 IN 95-58 December 18, 1995 11/21/95 List of Models That Meet 10 CFR Part 34 Requirements

____________________

SOURCE(S) (continued)

_ __ _ __ __ _ __ _

Manufacturer Status Description

Model

SPEC UNKNOWN

G-9F Ir-192 lOOCi

SPEC INACTIVE

N-23 SPEC ACTIVE Ir-192 14OCi

T-1 SPEC ACTIVE Ir-192 14OCi

T-1F

SPEC INACTIVE Ir-192 14OCi

T-2F

SPEC ACTIVE Ir-192 14OCi

T-5 SPEC ACTIVE Ir-192 14OCi

T-5F

SPEC ACTIVE Ir-192 14OCi

T-6 SPEC INACTIVE Ir-192 14OCi

T-7F

CHAGER(S)

CHANGER(S)

__________

Manufacturer Status Description

Model

AMERSHAM INACTIVE IR-192 120CI, DU 18 SOO-SU KG

AMERSHAM ACTIVE IR192 240CI,C060

650L 120mCICS137

10.8C},YB169

40CITM170 400CI,

DU 42 LBS

AMERSHAM ACTIVE CO-60 550CI, DU 161

770 KG

AMERSHAM ACTIVE CO-60 llOCI, DU 97

771 KG

A80RSHAM ACTIVE Ir-192 100OCi, DU

820 100 kg

_Attachment 1 I

IN 95-58 December 18, 1995 11/21/95 List of Models That Meet 10 CFR Part 34 Requirements

_____________________

CHANGER(S) (continued)

_____________________

Manufacturer Status Descript:ion

• Model

ACTIVE IR-192 2'40CI, DU 22

650 AMERSHAM

KG

IR-192 91S0CI, DU 57

855 AMERSHAM ACTIVE

KG

ACTIVE IR-192 1iDOCI, DU

C-1 SPEC

17KG

Attachment 2 IN 95-58 December 18, 1995 LIST OF RECENTLY ISSUED

NMSS INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-55 Handling Uncontained 12/6/95 All Uranium Recovery

Yellowcake Outside of a Licensees.

Facility Processing Circuit

95-51 Recent Incidents Involving 10/27/95 All material and fuel cycle

Potential Loss of Control licensees.

of Licensed Material

95-50 Safety Defect in Gammamed 10/30/95 All High Dose Rate

12i Bronchial Catheter Afterloader (HDR) Licensees.

Clamping Adapters

95-44 Ensuring Combatible Use of 09/26/95 All Radiography Licensees.

Drive Cables Incorporating

Industrial Nuclear Company

Ball-type Male Conectors

95-39 Brachytherapy Incidents 09/19/95 All U.S. Nuclear Regulatory

Involving Treatment Commission Medical

Planning Errors Licensees.

95-29 Oversight of Design and 06/07/95 All holders of OLs or CPs

and Fabrication Activities for nuclear power reactors.

for Metal Components Used

in Spent Fuel Dry Storage Independent spent fuel

Systems storage installation

designers and fabricators.

95-28 Emplacement of Support 06/05/95 All holders of OLs or CPs

Pads for Spent Fuel Dry for nuclear power reactors

Storage Installations at

Reactor Sites

95-25 Valve Failure during 05/11/95 All U.S. Nuclear Regulatory

Patient Treatment with Commission Medical

Gamma Stereotactic Licensees.

Radiosurgery Unit

\_.1 Attachment 3 IN 95-58 December 18, 1995 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-57 Risk Impact Study Regarding 12/18/95 All holders of OLs or CPs

Maintenance During Low-Power for nuclear power reactors.

Operation and Shutdown

95-56 Shielding Deficiency in 12/11/95 All holders of OLs or CPs

Spent Fuel Transfer Canal for nuclear power reactors.

at a Boiling-Water Reactor

95-55 Handling Uncontained 12/06/95 All Uranium Recovery

Yellowcake Outside of a Licensees.

Facility Processing

Circuit

95-54 Decay Heat Management 12/01/95 All holders of OLs or CPs

Practices during for nuclear power reactors.

Refueling Outages

95-53 Failures of Main Steam 12/01/95 All holders of OLs or CPs

Isolation Valves as a for nuclear power reactors.

Result of Sticking

Solenoid Pilot Valves

95-47, Unexpected Opening of a 11/30/95 All holders of OLs or CPs

Rev. 1 Safety/Relief Valve and for nuclear power reactors.

Complications Involving

Suppression Pool Cooling

Strainer Blockage

94-13, Control and Oversight of 11/28/95 All holders of OLs or CPs

Supp. 2 Contractors during Re- for nuclear power reactors.

fueling Activities and

Clarificaiton of Applica- bility of Section 50.120 of

Title 10 of The Code of

Federal Regulations to

Contractor Personnel

OL - Operating License

CP - Construction Permit

- * -

IN 95-58 December 18, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate regional office.

Donald A. Cool, Director

Division of Industrial and

Medical Nuclear Safety

Office of Nuclear Material

Safety and Safeguards

Contacts: J. Bruce Carrico, NMSS (For general information)

(301) 415-7826 Thomas W. Rich, NMSS (For device information)

(301) 415-7893 Attachments: 1. List of Approved Equipment

2. List of Recently Issued NMSS Information Notices

3. List of Recently Issued NRC Information Notices

DOCUMENT NAME: 95-58.IN SEE PREVIOUS CONCURRENCE

To receive a copy of this document. Indicate In the box: Ca = Copy without enclosures 'E' - Copy with enclosures

N' -No copy

OFFICE IMAB l INMSS lOSP RES lOE l IMAB I M~foKI

NAME PSantiago lEKraus IRBangart lTrottier JLieberman LCamper Iow

DATE 12/14/95 11/24/95 11/22/95 11/22/95 12/13/95 12/15/95 12/t/95 FFICIAL RECORD COPY

Coordinated with:

S. Treby, OGC, No Legal Objection, 11/22/95 per tel. conversation w/P. Santiago

J. Schleuter/K. Stablein, DEDS staff, 11/22/95 Email sent to L. Portner and regions on 11/22/95 A. Gallow, OI 11/21/95 per telephone message to P. Santiago

R. Baer/S. Baggett, SCDB, IMNS 11/22/95. K. Ramsey, IMOB 12/14/95