U.S. Nuclear Office of Nuclear NUREG/BR-0117

Regulatory Material Safety No. 04-01

Commission and Safeguards March 2004

NMSS Licensee Newsletter

Contents Page

1. Licensee Reporting for Nuclear Materials

Management and Safeguards System,

NRC Bulletin 2003-04....................................... 1

2. Medical Events Caused by Failure to

Properly Measure the Radioactivity of

Samarium-153 Dosages..................................... 2

3. What’s New on the Medical Uses

Licensee Toolkit Web Page ............................... 2

4. Significant Events ............................................. 2

5. Significant Enforcement Actions ....................... 4

6. Generic Communications Issued

(September 29, 2003 - January 21, 2004)........... 5

7. Selected Federal Register Notices

(December 1, 2003 - February 29, 2004) ........... 6

LICENSEE REPORTING FOR

NUCLEAR MATERIALS MANAGEMENT

AND SAFEGUARDS SYSTEM,

NRC BULLETIN 2003-04

Presently, the U.S. Nuclear Regulatory Commission

(NRC) requires certain NRC and Agreement State

licensees and certificate holders (hereafter referred

to as licensees) to submit data to the Nuclear

Materials Management and Safeguards System

(NMMSS) about their receipts, shipments,

inventories, and changes in inventory of special

nuclear material (SNM). Additionally, reporting is

required for source material pursuant to meeting

international treaty commitments (hereafter referred

to as foreign obligated source material). The U.S.

Department of Energy (DOE) has additional

reporting requirements associated with other

material types owned by the Government in licensee

possession (i.e., deuterium, tritium, curium,

americium, neptunium, californium, berkelium,

and enriched lithium).

In October 2001, the DOE Office of the Inspector

General (OIG) issued a report entitled, “Accounting

for Government-Owned Nuclear Materials Provided

to Non-Department Domestic Facilities.” Based on

information available from NMMSS, one of the

findings in the report was that DOE “. . . could not

fully account for nuclear materials loaned or leased

to domestic licensees.” As a result of the OIG

findings, NRC believes that NMMSS balances

should be confirmed and corrected as necessary, on

the basis of a one-time reporting of licensee material

balances to NMMSS.

To accomplish that goal, NRC is requesting,

through a Bulletin, that licensees submit, to

NMMSS, current material balance information for

SNM and foreign obligated source material.

Additionally, licensees will be requested to report

material balance information for other Governmentowned material types in their possession. The

Bulletin is available through the NRC public web

page at: www.nrc.gov/reading-rm/doc-collections/

gen-comm/bulletins/2003/bl03004.pdf. Once those

values are submitted to NMMSS, the NMMSS staff

will compare the reported information to the

NMMSS book values and assist licensees in the

resolution of any NMMSS book discrepancies.

Discrepancies that cannot be readily resolved may

be referred to NRC for further action. However, it

is not the intent of this effort to cite licensees for

past reporting errors unless those errors demonstrate

a deliberate act of non-compliance with regulations

and/or negatively impacted the licensees’ safety or

safeguards controls.

All licensees, including those licensed pursuant to

10 CFR Part 30, should review the Bulletin to

determine if it is applicable to their operations.
2

Licensees may communicate directly with the

NMMSS contractor or forward their questions to

NRC via e-mail to nmmss@nrc.gov.

(Contact: Larry Harris, NSIR, 301-415-5072,

e-mail: lch1@nrc.gov)

MEDICAL EVENTS CAUSED BY

FAILURE TO PROPERLY MEASURE

THE RADIOACTIVITY OF SAMARIUM153 DOSAGES

Seven medical events were reported to the U.S.

Nuclear Regulatory Commission (NRC), between

November 2003 and January 2004, each involving

licensee failure to properly measure the radioactivity

of samarium-153 dosages with dose calibrators.

One medical event occurred when both a nuclear

pharmacy and a medical licensee failed to properly

measure the radioactivity of a samarium-153 unit

dosage. During initial measurement of the dosage

radioactivity, the nuclear pharmacy erroneously

multiplied the dose-calibrator displayed

radioactivity by a “10 factor.” However, the dose

calibrator was set to display the actual radioactivity.

Therefore, the nuclear pharmacy labeled the dosage

vial to indicate 10 times the actual radioactivity

before transfer to a medical licensee. When the

medical licensee measured the dosage, it noted that

the radioactivity displayed on its dose calibrator was

approximately one-tenth of that on the vial label and

the prescribed radioactivity on the written directive.

The medical licensee contacted the nuclear

pharmacy to discuss the discrepancy between the

radioactivity measured with its dose calibrator and

that indicated on the label. The nuclear pharmacy

informed the technologist that a “10 factor” had to

be applied to the radioactivity measured by the dose

calibrator to obtain the actual radioactivity. The

medical licensee applied the factor provided by the

nuclear pharmacy and erroneously determined that

the dosage contained the prescribed radioactivity,

before administering it to a patient. As a result, the

patient received approximately one-tenth of the

prescribed samarium-153 radioactivity.

Six other medical events occurred because a

medical licensee used an incorrect dose calibrator

potentiometer setting during measurement of the

radioactivity in samarium-153 dosages. As a result,

the administered radioactivities were approximately

30 percent less than prescribed.

On June 12, 2002, NRC issued Information Notice

(IN) 2002-19, “Medical Misadministrations caused

by Failure to Properly Perform Tests on Dose

Calibrators for Beta- and Low-Energy PhotonEmitting Radionuclides.” The IN described the

circumstances of medical misadministrations that

occurred as a result of inaccurate radioactivity

measurement of samarium-153 dosages and some of

the potential sources of errors in measurement of

beta- and low-energy gamma emitters. Based on the

recent medical events described above, licensees are

encouraged to review the IN and to verify that the

radioactivities of beta- and low-energy gammaemitting dosages are properly measured. This IN

can be found on NRC’s website at http://

www.nrc.gov/reading-rm/doc-collections/gencomm/info-notices/2002/in02019.pdf.

(Contact: Robert G. Gattone, RIII/DNMS,

630-829-9823, e-mail: rgg@nrc.gov)

WHAT’S NEW ON THE MEDICAL USES

LICENSEE TOOLKIT WEB PAGE

Nuclear Material Safety and Safeguards staff

recently revised the “Medical Uses Licensee

Toolkit: Regulations” section to add a link to the

proposed rule “Recognition of Specialty Boards.”

Although the public comment period has closed, this

link can be used to review the draft proposed rule

and the public comments. The “Medical Uses

Licensee Toolkit: Other Guidance” section was

revised to add licensing guidance for the Nucletron

seedSelectron® System, Isotron brachytherapy

sources, and Nucletron FIRSTTM System, the newest

10 CFR 35.1000 medical use. The licensing

guidance for the TheraSphere and SIRSphere

Yttrium-90 Microspheres was revised to clarify use

of the medical end-point of stasis in the written

directive as a means of specifying when to terminate

implantation of the microspheres. Also the “Notes

to Licensee” section in the licensing guidance for

each 10 CFR 35.1000 medical use was revised

to inform licensees that they can apply for

amendments that would permit them to make

changes to their radiation safety programs, to

conform with future revisions in the licensing

guidance. These changes were made to inform

licensees of current rulemaking activities or provide

them with greater flexibility.

(Contact: Donna-Beth Howe, 301-415-7848,

e-mail: dbh@nrc.gov)

SIGNIFICANT EVENTS

Event 1: Dose to Fetus

Date and Place: November 20, 2003;

Hillcrest Hospital, Mayfield Heights, Ohio
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Nature and Probable Causes: The Ohio Bureau of

Radiation Protection reported that a 19-year-old

female patient was administered 5.18 gigabecquerel

(140.1 millicurie) of Iodine-131 for thyroid

carcinoma as prescribed. The patient did not

believe that she was pregnant and completed the

required forms indicating that she was not pregnant

before the dose was administered. On December 5,

December 8, and December 11, 2003, quantitative

tests confirmed that the patient was pregnant. The

results were provided to her endocrinologist, who

recommended that a fetal dose calculation be

performed. The licensee’s consultant informed the

endocrinologist that the fetus would have received a

whole body dose of 19.6 centigray (rad). The

endocrinologist sent the results to the Center for

Human Genetics at the University Hospital in

Cleveland, Ohio, where an assessment determined

that the pregnancy could safely continue.

Actions Taken to Prevent Recurrence

Licensee: The licensee has implemented pregnancy

testing for child-bearing-age female patients

receiving radiation therapy.

Event 2: Release of Uranium Hexafluoride

Date and Place: December 22, 2003,

Metropolis, Illinois

Nature and Probable Causes: Honeywell

International, Inc., reported an inadvertent release of

uranium hexafluoride (UF6

) that occurred on

December 22, 2003. The release, which lasted

approximately 45 minutes, went beyond the site

boundary of Honeywell. The licensee declared a

Site Area Emergency, and all persons within a 1.6-

kilometer (1-mile) radius were evacuated. The local

sheriff was notified and responded to the scene.

Personnel from U.S. Nuclear Regulatory

Commission (NRC) Headquarters and Region 2,

NRC, also responded. The licensee estimated that

approximately 3.2 kilograms (7 pounds) of UF6

were released. About 25 people offsite were

temporarily evacuated, and some 75 persons

remained sheltered for a time in their homes. Offsite

air samples showed uranium levels up to 100 times

that of normal levels, but at or below the NRC

regulatory annual average effluent concentration

limits. Urine bioassays from five members of the

public were below public dose limits. Four

members of the public reported to the hospital;

three were examined and released, and the fourth

was released after 24 hours.

NRC appointed an Augmented Inspection Team to

inspect the circumstances surrounding the UF6

 leak.

The cause of this event was the assistant fluorine

operator’s failure to configure valves correctly,

which caused a section of the piping to pressurize

and leak. Contributing factors included the operator

not having a procedure or checklist to designate the

proper valve positions, no oversight nor review to

ensure correct valve position, and the infrequent

nature of this task.

Actions Taken to Prevent Recurrence

Licensee: Corrective actions were discussed at a

public meeting held in NRC Headquarters on

February 11, 2004.

(Contact: Angela Williamson, NMSS,

301-415-5030; e-mail: arw@nrc.gov)

ERRATA

Licensee: Rush Copley Medical Center,

Aurora, Illinois.

Error: In the December 2003 edition of the NMSS

Licensee Newsletter, a whole-body dose of 1587

centisievert (rem) was reported.

Correction: The preliminary whole-body dose of

1587 centisievert (rem) concerning Rush Copley

Medical Center (as reported in the December 2003

edition of the NMSS Licensee Newsletter) has not

been verified because of the pending question of

preexisting hypothyroidism in the patient.

Licensee: Community Hospital of Anderson,

Anderson Indiana.

Error: In the December 2003 edition of the NMSS

Licensee Newsletter, this event was inappropriately

categorized as a “misadministration.”

Correction: For U.S. Nuclear Regulatory

Commission (NRC) licensees, the term

“misadministration” has been replaced by “medical

event” in revised 10 CFR Part 35, “Medical Use of

Byproduct Material.” Furthermore, the licensee

correctly reported this event, to NRC, as an

unintended dose to the embryo/fetus, in accordance

with 10 CFR 35.3047.

(Contact: Angela R. Williamson, NMSS,

301-415-5030; e-mail: arw@nrc.gov)
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SIGNIFICANT ENFORCEMENT

ACTIONS

The U.S. Nuclear Regulatory Commission’s

(NRC’s) enforcement program can be accessed via

NRC’s homepage [http://www.nrc.gov/] under

“What We Do.” Documents related to cases can be

accessed at [http://www.nrc.gov/], “Electronic

Reading Room,” “Documents in ADAMS.”

ADAMS is the Agency-wide Document Access and

Management System. Help in using ADAMS is

available from the NRC Public Document Room,

telephone: 301-415-4737 or 1-800-397-4209.

Decommissioning

Westinghouse Electric Company, LLC (Hematite

Facility) (EA-03-182)

On December 22, 2003, a Notice of Violation was

issued for a Severity Level III violation involving

two examples of the failure to follow enhanced

work plans for decommissioning activities specific

to the preparation of contaminated materials for

shipping to a metal recycling facility.

Gauges

Imaging Subsurface, Inc. (EA-03-223)

On February 6, 2004, a Notice of Violation was

issued for a Severity Level III violation involving

the failure to secure from unauthorized removal, or

limit access to, licensed material [nominally 296

megabecquerels (Mbq) (8.0 millicuries (mCi)) of

cesium-137 and 1480 MBq (40 mCi) of americium241:beryllium, in two moisture-density gauges] in

unrestricted areas at the licensee’s facility, and

failure to control and maintain constant surveillance

of this licensed material.

Specifically, licensee staff left two unlocked

moisture-density gauges unsecured and unattended

in an unlocked storeroom at the licensee’s facility.

Hannibal Testing Laboratories (EA-03-206)

On November 28, 2003, a Notice of Violation was

issued for a Severity Level III violation involving

the failure to secure from unauthorized removal, or

limit access to, licensed material [nominally 296

megabecquerels (MBq) 8 millicuries (mCi) of

cesium-137 and 1480 MBq (40 mCi) of americium241:beryllium in two moisture-density gauges] in

unrestricted areas at the licensee’s facility, and

failure to control and maintain constant surveillance

of this licensed material. Specifically, licensee staff

left two unlocked moisture density gauges

unsecured and unattended in two areas of the

licensee’s facility.

Medical

Union City Diagnostic Center (EA-03-170)

On January 13, 2004, a Notice of Violation was

issued for a Severity Level III problem involving:

(1) the receipt, possession, and use of byproduct

material without the supervision of an Authorized

User (AU) or a Radiation Safety Officer; and

(2) the creation of false records indicating that the

AU had ordered licensed material during that

period, when, in fact, the AU was no longer

employed at the facility.

Rice Memorial Hospital (EA-03-205)

On December 15, 2003, a Notice of Violation was

issued for a Severity Level III violation involving

the failure to secure from unauthorized removal, or

limit access to, licensed material [approximately

5365 megabecquerels (MBq) (145 millicuries

(mCi)) of technetium-99m and an approximate

aggregate activity of 7104 Mbq (192 mCi) of

gadolinium-153 contained in sealed sources] in

controlled areas, and the failure to control and

maintain constant surveillance of the licensed

material. Specifically, a technologist left the doors

to a mobile nuclear van unlocked and unsecured

when the technologist was in the client hospital and

did not maintain constant surveillance of the

licensed material located in the van.

Radiography

Cooperheat-MQS, Inc. (EA-03-151)

On December 30, 2003, a Notice of Violation and

Proposed Imposition of Civil Penalty in the amount

of $6000 was issued for a Severity Level III willful

problem involving the failure to conduct required

radiographer refresher training and the failure to

provide complete and accurate unformation, to the

U.S. Nuclear Regulatory Commission, involving

radiographer-training records.

Individual Actions

Gary L. Youler (IA-03-036)

On December 30, 2003, a Notice of Violation was

issued for a Severity Level III violation based on the
5

individual’s deliberate activities while employed at

Cooperheat-MQS, Inc. As the facility Radiation

Safety Officer, the individual deliberately provided

false information to the U.S. Nuclear Regulatory

Commission, involving radiographer training records.

(Contact: Sally Merchant, 301-415-2747, e-mail:

slm2@nrc.gov)

GENERIC COMMUNICATIONS ISSUED

(September 29, 2003 - January 21, 2004)

The following are summaries of U.S. Nuclear

Regulatory Commission (NRC) generic

communications. If one of these documents appears

relevant to your needs and you have not received it,

please call one of the technical contacts listed

below. The Internet address for the NRC library of

generic communications is: http://www.nrc.gov/

reading-rm/doc-collections/gen-comm/index.html.

Please note that this address is case-sensitive and

must be entered exactly as shown. If you have any

questions or comments about generic

communications in general, please contact Angela

R. Williamson, NMSS, at (301) 415-5030, or

by e-mail: arw@nrc.gov.

Bulletin (BL)

No bulletins have been issued, to date, in 2004.

Information Notices (INs)

IN 2003-17, “Reduced Service Life of Automatic

Switch Company (ASCO) Solenoid Valves with

Buena-n Material,” was issued on September 29,

2003. This IN was sent to all holders of operating

licenses for nuclear power reactors, to apprise them

of potential problems caused by the hardening of

Buena-n material used in fabricating solenoid valves

manufactured by ASCO.

(Technical Contacts: Thomas Koshy, NRR, 301-

415-1176, e-mail: txk@nrc.gov; Matthew W.

McConnell, NRR, 301-415-1597, e-mail:

mxm4@nrc.gov; and Jerry Dozier, NRR, 301-415-

1176, e-mail: jxd@nrc.gov).

IN 2003-18, “General Electric Type SBM Control

Switches with Defective Cam Followers,” was

issued on September 26, 2003. This IN was sent to

all holders of operating licenses for nuclear power

reactors, except those that have permanently ceased

operations and have certified that fuel has been

permanently removed from the reactor vessel. This

IN was sent to inform addressees of recent and longterm operational experience, with control switches

and relays incorporating a plycarbonate plastic

material, known as Lexan, manufactured by

General Electric.

(Technical contacts: Vernon Hodge, NRR,

301-415-1861, e-mail: cvh@nrc.gov;

Stephen Alexander, NRR, 301-415-2995:

e-mail: sda@nrc.gov; and Joe O’Hara, Region I,

410-495-4669, e-mail: jmo@nrc.gov).

IN 2003-19, “Unanalyzed Condition of Reactor

Coolant Pump Seal Leakoff Line During Postulated

Fire Scenarios or Station Blackout,” was issued

October 6, 2003. This IN was sent to all holders of

operating licenses or construction permits for

pressurized-water reactors. This IN was issued to

alert addressees to recent identification of an

unanalyzed condition involving the design of the

reactor coolant pump seal leakoff line.

(Technical contacts: Paul Cataldo, Region I, 860-

701-3470, e-mail: pcc1@nrc.gov; Warren Lyon,

NRR, 301-415-2897, e-mail: wcl@nrc.gov; and

Phil Qualls, NRR, 301-415-1849, e-mail:

pmq@nrc.gov)

IN 2003-21, “High-Dose-Rate-Remote-Afterloader

Equipment Failure,” was issued November 24,

2003. This IN was issued to inform addressees of a

recently reported medical event that occurred during

the conduct of a high-dose-rate, remote-afterloader

brachytherapy procedure.

(Technical contact: Ronald Zelac, PhD,

301-415-7635, e-mail: rez@nrc.gov)

IN 2003-22, “Heightened Awareness for Patients

Containing Detectable Amounts of Radiation from

Medical Administrations,” was issued December 9,

2003. This IN was issued to inform addressees of

an event where a radiation detector, installed as part

of heightened homeland security measures, alarmed

when a recently released radiopharmaceutical

patient passed by it.

(Technical contacts: Teresa Darden, Region I,

610-337-5245, e-mail: thd@nrc.gov; Pamela J.

Henderson, Region I, 610-337-6952, e-mail:

pjh1@nrc.gov; and Donna-Beth Howe, PhD,

NMSS, 301-415-7848, e-mail: dbh@nrc.gov)

IN 2004-01, “Auxiliary Feedwater Pump

Recirculation Line Orifice Fouling - Potential

Common- Cause Failure,” was issued January 21,

2004. This IN was issued to all holders of operating

licenses or construction permits for nuclear power

reactors, except those that have permanently ceased
6

operations and have certified that fuel has been

permanently removed from the reactor vessel. This

IN was issued to inform addressees of the potential

common-cause failure of auxiliary feedwater pumps

because of fouling of pump-recirculation line-flow

orifices.

(Technical contacts: Jerry Dozier, NRR,

301-415-1176, e-mail: jxd@nrc.gov.; Paul Krohn,

Region III, 920-755-2309, e-mail: pgk1@nrc.gov)

Regulatory Issue Summaries (RIS’)

RIS 2003-18, “Use of NEI 99-01 - Methodology for

Development of Emergency Action Levels,”

Revision 4, dated January 2003, was issued on

October 08, 2003. This RIS was issued to all

holders of operating licenses for nuclear power

reactors and licensees that have permanently ceased

operations and have certified that fuel has been

permanently removed from the reactor vessel. This

RIS was issued to inform addressees that the U.S.

Nuclear Regulatory Commission (NRC) has

reviewed Nuclear Energy Institute 99-01 -

“Methodology for Development of Emergency

Action Levels,” Revision 4, January 2003, and is

endorsing the report for use as guidance in

developing or changing a standard emergencyclassification and action-level scheme. In addition,

this RIS provides recommendations to help

licensees determine whether to seek prior NRC

approval of deviations from the new guidance.

(Technical contact: Thomas Blount, NRR,

301-415-1501, e-mail: txb1@nrc.gov)

(General Contact: Angela R. Williamson, NMSS,

301-415-5030, e-mail: arw@nrc.gov)

SELECTED FEDERAL REGISTER NOTICES

(December 1, 2003 - February 29, 2004)

NOTE: U.S. Nuclear Regulatory Commission

(NRC) contacts may be reached by mail at the U.S.

Nuclear Regulatory Commission, Washington, DC

20555-0001.

FINAL RULES

“List of Approved Spent Fuel Storage Casks:

Standardized NUHOMS 24P, 52B, 61BT, and

24PHB Revision (Amendment 6); Correction and

Confirmation of Effective Date,” 68 FR 70121,

December 17, 2003.

(Contact: Margaret Stambaugh, NMSS,

301-415-5449, e-mail: mxs8@nrc.gov)

“List of Approved Spent Fuel Storage Casks:

Standardized NUHOMS 24P, 52B, 61BT, 32PT,

and 24PHB Revision (Amendment 7); Direct Final

Rule,” 68 FR 70423, December 18, 2003.

(Contact: Jayne M. McCausland, NMSS,

301-415-6219, e-mail: jmm2@nrc.gov)

“List of Approved Spent Fuel Storage Casks:

Standardized NUHOMS-24P, -52B, -61BT, -

24PHB, and -32 PT, Revision 5,” 69 FR 849,

January 7, 2004.

(Contact: Jayne M. McCausland, NMSS,

301-415-6219, e-mail: jmm2@nrc.gov)

“Changes to Adjudicatory Process,” 69 FR 2182,

January 14, 2004.

(Contact: Geary S. Mizuno, OGC, 301-415-1639,

e-mail: gsm@nrc.gov)

“List of Approved Spent Fuel Storage Casks: NACUMS Revision,” 69 FR 2497, January 16, 2004.

(Contact: Jayne M. McCausland, NMSS,

301-415-6219, e-mail: jmm2@nrc.gov)

“Compatibility with IAEA Transportation Safety

Standards and Other Transportation Safety

Amendments: Correction,” 69 FR 6139, February

10, 2004.

(Contact: Naiem S. Tanious, NMSS, 301-415-6103,

e-mail: nst@nrc.gov)

PROPOSED RULES

“Medical Use of Byproduct Material-Recognition of

Specialty Boards,” 68 FR 68549,

December 9, 2003.

(Contact: Roger W. Broseus, NMSS, 301-415-

7608, e-mail: rwb@nrc.gov)

“List of Approved Spent Fuel Storage Casks:

Standardized NUHOMS 24P, 52B, 61BT, 32PT,

and 24PHB Revision (Amendment 7); Companion

Proposed Rule,” 68 FR 70463,

December 18, 2003.

(Contact: Jayne M. McCausland, NMSS, 301-415-

6219, e-mail: jmm2@nrc.gov)

“List of Approved Spent Fuel Storage Casks: NACUMS Revision (companion proposed rule),” 69 FR

2528, January 16, 2004.

(Contact: Jayne M. McCausland, NMSS,

301-415-6219, e-mail: jmm2@nrc.gov)
7

“Revision of Fee Schedules; Fee Recovery for FY

2004,“ 69 FR 4865, February 2, 2004.

(Contacts: Ann Norris, OCFO, 301-415-7807,

e-mail: ame@nrc.gov; Tammy Croote, OCFO

301-415-6041, txc1@nrc.gov)

OTHER NOTICES

“Revision of NRC Enforcement Policy; Packaging

and Transportation of Radioactive Material

(NUREG-1600),” 69 FR 385, January 5, 2004.

(Contact: Frank J. Congel, OE, 301-415-2741, email: fjc@nrc.gov)

“Draft Regulatory Guide-7003 (Proposed Revision

2 of Regulatory Guide 7.9), ‘Standard Format and

Content of Part 71 Applications for Approval of

Packaging for Radioactive Material,’ “ 69 FR 2014,

January 13, 2004.

(Contact: N.L. Osgood, NMSS, 301-415-8513,

e- mail: nlo@nrc.gov)

“Hazardous Materials Regulations; Compatibility

with the Regulations of the International Atomic

Energy Agency,” 69 FR 3632, January 26, 2004.

(Contact: Naiem S. Tanious, NMSS, 301-415-6103,

e-mail: nst@nrc.gov)

“Order Imposing Additional Security Measures”

(Effective Immediately), 69 FR 5733,

February 4, 2004.

“State of Utah: NRC Staff Draft Assessment of a

Proposed Amendment to Agreement Between the

Nuclear Regulatory Commission and the State of

Utah” (First printing), 69 FR 7026,

February 12, 2004.

(Contact: Dennis M. Sollenberger, OSTP,

301-415-2819, e-mail: dms4@nrc.gov)

“State of Utah: NRC Staff Draft Assessment of a

Proposed Amendment to Agreement Between the

Nuclear Regulatory Commission and the State of

Utah” (Reprint), 69 FR 7803, February 19, 2004.

(Contact: Dennis M. Sollenberger, OSTP,

301-415-2819, e-mail: dms4@nrc.gov)

“Collection, Reporting, or Posting of Information;

Availability of Draft Rule Language,” 69 FR

8350, February 24, 2004.

(Contact: William D. Reckley, NRR,

301-415-1323, e-mail: wdr@nrc.gov)

“State of Utah: NRC Staff Draft Assessment of a

Proposed Amendment to Agreement Between the

Nuclear Regulatory Commission and the State of

Utah” (Reprint), 69 FR 8703, February 25, 2004.

(Contact: Dennis M. Sollenberger, OSTP,

301-415-2819, e-mail: dms4@nrc.gov)

“Issuance, Availability of Draft Regulatory Guide,

DG-7004, ‘Standard Format and Content of Part 71

Applications for Approval of Packaging for

Radioactive Material,’ “ 69 FR 8706,

February 25, 2004.

(Contact: J. Pearson, NMSS, 301-415-1985,

 e-mail: jjp@nrc.gov)

(General Contact: Michael Williamson, NMSS,

301-415-6234, e-mail: mkw1@nrc.gov)

Comments , and suggestions you may have for

information not currently included, that might

be helpful to licensees, should be sent to:

E. Kraus, Editor

NMSS Licensee Newsletter

Office of Nuclear Material Safety and Safeguards

Two White Flint North, Mail Stop 8-A-23

U.S. Nuclear Regulatory Commission

Washington, D. C. 20555-0001
8