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

Regulatory Material Safety No. 00-3 

Commission and Safeguards Sept-Oct 2000

DISCRIMINATION TASK GROUP 

On July 27, 2000, the U.S. Nuclear Regulatory 

Commission (NRC) established a management

level review group to evaluate the NRC processes 

used in the handling of discrimination allegations 

and violations of employee protection standards. 

The Discrimination Task Group's overall objective 

is to develop recommendations for possible 

changes to regulatory requirements, the Agency 

Enforcement Policy, or other guidelines, as 

appropriate. Another of the group's primary 

objectives is to promote active and frequent 

involvement of internal and external stakeholders 

in the development of recommendations for 

changes to the process. 

The group's preliminary schedule is to begin work 

in September 2000, to evaluate current NRC 

processes and develop recommendations for 

process improvements. The Task Group plans to 

complete its work by June 30, 2001. Specific 

activities being considered include interaction with 

other agencies, conduct of internal and external 

stakeholder meetings to solicit input, and 

consideration of issues raised in a Petition for 

Rulemaking regarding requiring training of 

supervisors on their responsibilities in imple

menting the employee protection regulations. 

Over the next several months, the Task Group 

plans to hold several internal stakeholder 

meetings in the regional offices, and public 

stakeholder meetings in various areas of the 

country. These public meetings will be held at the 

NRC Headquarters offices; Chattanooga, TN; San 

Luis Obispo, CA; and in the vicinity of the 

Milestone Nuclear Power Plant; the Chicago area; 

and the Paducah Gaseous Diffusion Plant. With 

the input from these meetings, the Task Group 

will begin to develop recommendations for 

process improvements.

The Task Group Charter and other pertinent 

documents related to the group's activities will be 

periodically posted and updated on the NRC 

Office of Enforcement WEB site homepage 

[http://www.nrc.gov/OE/]. Any questions about the 

group should be directed to Mr. Barry Westreich, 

telephone number: 301-415-3456, or e-mail: 

bcw@nrc.gov. 

(Contact: Barry Westreich, 301-415-3456, 

e-mail: bcw@nrc.gov). 

NRC STAFF COMPLETES 

DECOMMISSIONING STANDARD 

REVIEW PLAN 

In July 1998, the U.S. Nuclear Regulatory 

Commission (NRC) directed the staff to develop a 

Standard Review Plan (SRP) for evaluating 

information to support the decommissioning of 

nuclear facilities. The goal of the SRP is to allow 

NRC staff to evaluate information submitted by 

licensees, in a timely, efficient, and consistent 

manner, to determine if the decommissioning can 

be conducted, such that the public health and 

safety are protected and the facility can be 

released in accordance with NRC's requirements. 

The staff has completed development of the SRP 

and is making it available to interested individuals 

for use in developing Decommissioning Plans 

(DPs) and other information to support the 

decommissioning of nuclear facilities. 

The SRP describes a risk-informed, iterative 

approach developed by the staff, and provides 

guidance on the information that should be 

included in a DP, including evaluation and 

acceptance criteria for reviewing the information, 

and suggestions on the format and content of the 

information. It also provides NRC staff with a 

description of the contents of specific decom

missioning plan modules, as well as evaluation 

and acceptance criteria for use in reviewing 

decommissioning plans and other information
NMSS LICENSEE NEWSLETTER 

(September- October 2000) 

Contents 

Page 

1. Discrimination Task Group .............. 1

2. NRC Staff Completes Decommissioning 

Standard Review Plan ................... 

3. Oklahoma Assumes Licensing Authority 

under Agreement with NRC .............

1 

2

4. Domestic Licensing of Special Nuclear 

Material; Possession of a Critical Mass 

of Special Nuclear Material .............. 3 

5. Operational Experience ................. 3 

6. Significant Enforcement Actions .......... 5 

7. Selected Federal Register Notices 

(July 1, 2000-August 31, 2000) ........... 6 

8. Generic Communications Issued 

(July 1, 2000-August 31, 2000) ........... 7 

NRC STAFF COMPLETES 

DECOMMISSIONING STANDARD 

REVIEW PLAN (continued) 

submitted by licensees to demonstrate that their 

facilities are suitable for release in accordance 

with NRC requirements. To obtain input from the 

regulated community on issues that needed to be 

addressed in the SRP, NRC staff held a series of 

workshops on dose modeling surveys, 

demonstrating as low as is reasonably achievable, 

and restricted use/alternate criteria in 1998-2000. 

In addition, as draft SRP modules were com

pleted, they were posted on the NRC Website. 

The SRP supersedes numerous existing Regula

tory Guides, including Regulatory Guide 3.65, 

"Standard Format and Content of Decom

missioning Plans for Licensees under 10 CFR 

Parts 30, 40, and 70," and Policy and Guidance 

Directive FC 91-2, "Standard Review Plan: 

Evaluating Decommissioning Plans for Licensees 

under Parts 30, 40, and 70." In addition, in 

recognition that similar information was being 

presented in the SRP and Draft Regulatory Guide 

DG-4006, "Demonstrating Compliance with the 

Radiological Criteria for License Termination," 

staff has consolidated the guidance in the SRP and 

will not publish a final version of the Draft

Regulatory Guide. Comments submitted by 

interested individuals on DG-4006 were 

considered as the staff finalized the SRP. 

Currently, NRC staff is preparing the SRP for 

publication as a NUREG. However, to allow 

interested individuals to begin using the SRP, the 

staff has placed it on NRC's Decommissioning 

Website at: http://www.nrc.gov/NMSS/DWM/ 

DECOM/decomm.html. 

NRC staff will begin using the SRP to evaluate 

DPs and other information in September 2000, and all interested individuals are urged to review 

the SRP before they begin developing DPs and 

other information to support the decommissioning 

of their facilities. 

(Contact: Nick Orlando, 301-415-6749; e-mail: 

dao@nrc.gov) 

OKLAHOMA ASSUMES LICENSING 

AUTHORITY UNDER AGREEMENT WITH 

NRC 

Governor Frank Keating of the State of Oklahoma 

and Dr. Richard Meserve, Chairman of the U.S. 

Nuclear Regulatory Commission (NRC) signed an 

Agreement and, on September 29, 2000, 

Oklahoma became the 32nd Agreement State. 

The Agreement with Oklahoma allows Oklahoma 

to assume regulatory authority over 11e.(1) 

byproduct material; source material used to take 

advantage of its density and high-mass properties, where the use of the specifically licensed source 

material is subordinate to the primary specifically 

licensed use of either 11e.(1) byproduct material 

or special nuclear material; and special nuclear 

material in quantities not sufficient to form a 

critical mass. Oklahoma will also assume authority 

to regulate the disposal of low-level radioactive 

waste at a land disposal site as described in 

10 CFR Part 61. With this agreement, approximately 235 NRC material licenses in 

Oklahoma were transferred to the State of

2

Comments, and suggestions you may have 

for information that is not currently being 

included, that might be helpful to licensees, 

should be sent to: 

E. Kraus 

NMSS Licensee Newsletter Editor 

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
Oklahoma. Individuals who need to perform 

licensed activities, as listed above, in the State of 

Oklahoma, should contact Mike Broderick, 

Administrator, Oklahoma Department of 

Environmental Quality, Radiation Management 

Section, P. 0. Box 1677, Oklahoma City, OK 

73101-1677. The Department of Environmental 

Quality's phone number is 405-702-5155. 

(Contact: Anthony Gaines, Region IV, 

817-860-8252, e-mail: adgl@nrc.gov) 

DOMESTIC LICENSING OF SPECIAL 

NUCLEAR MATERIAL; POSSESSION OF A 

CRITICAL MASS OF SPECIAL NUCLEAR 

MATERIAL 

The U.S. Nuclear Regulatory Commission (NRC) 

has amended its regulations, in 10 CFR Part 70, 

governing the domestic licensing of special nuclear 

material (SNM) for certain licensees authorized 

to possess a critical mass of SNM. 

The amendments establish performance 

requirements that require the affected licensees to 

perform an integrated safety analysis (ISA). An 

ISA is a systematic analysis that identifies: 

1) plant and external hazards and their potential 

for initiating accident sequences; 2) the potential 

accident sequences and their likelihood and 

consequences; and 3) the items relied on for 

safety to prevent or mitigate potential accidents 

at a facility. The amendments also require the 

implementation of measures to: (a) ensure that 

the items relied on for safety are available and 

reliable to perform their functions when needed; 

(b) require the safety bases to be maintained and 

report changes to NRC; (c) allow licensees to 

make certain changes to their safety program 

and facilities without prior NRC approval; (d) 

require reporting of certain events; and (e) 

require NRC to perform a backfit analysis under 

specified circumstances. 

These amendments were in response to a Petition 

for Rulemaking (PRM) -70-7, submitted by the 

Nuclear Energy Institute (NEI), which was 

published on November 26, 1996 (61 FR 60057). 

The proposed rule was intended to grant the NEI 

PRM in part and would modify the petitioner's 

proposal. The majority of the proposed 

modifications to Part 70 were included in a 

proposed new Subpart H, 'Additional 

Requirements for Certain Licensees Authorized 

to Possess a Critical Mass of Special Nuclear 

Material." These modifications were proposed to 

increase confidence in the margin of safety at the 

facilities affected by the rule.

During the rulemaking process, the staff used 

several methods to seek stakeholder participation 

and comment. All important documents and 

significant drafts of selected documents were 

posted on the NRC web site (www.nrc.gov, under 

"Rulemaking and Technical Conference"). These 

postings included postings providing revised rule 

and standard review plan language; staff 

comments on related issues; postings of comments 

received; and postings of the transcripts of public 

meetings. Potentially interested parties were 

e-mailed notifications when a new document was 

added to the site. In addition, between December 

of 1998 and September of 2000, the NRC staff 

held 10 public stakeholder meetings to discuss the 

rule and associated guidance documents. 

Through extensive stakeholder involvement, the 

final rule was approved by the Commission on 

September 6, 2000, and is to be published in the 

Federal Register in mid-September. The staff 

continues to work with affected stakeholders to 

develop guidance documents that would 

implement the proposed requirements. 

(Contact: Heather Astwood, 301-415-5819, 

e-mail: hma@nrc.gov) 

OPERATIONAL EXPERIENCE 

The U.S. Nuclear Regulatory Commission (NRC) 

is providing summaries of these events to inform 

licensees of conditions they may encounter and of 

actions that may be taken to deal with them. 

1. Contamination Resulting from Use of 

Feeding Tube to Administer 

Radiopharmaceutical 

NRC is alerting licensees to the possibility of a 

contamination and exposure hazard when a 

feeding tube is used in the administration of 

radiopharmaceuticals. The following event 

involved the contamination of two individuals and 

a skin overexposure of 1 sievert (Sv) (100 rem) to 

one of the individuals. 

A physician, assisted by a nuclear medicine 

technologist, was administering a dosage of 

140 millicuries (mCi) of Iodine-131 (1-131) to a 

patient for thyroid oblation. The method of 

administration was by injection into an existing 

stomach tube. On completion of the 

administration/procedure, the patient coughed 

and caused some of the 1-131 to spray from 

the tube, which contaminated the technologist 

and physician. 

The physician was decontaminated, but after 

showering, the nuclear medicine technologist was 

still contaminated on the hands, neck, hair, and

3
torso. Within 2 hours of the event, the nuclear 

medicine technologist was administered a blocking dose of potassium iodide. A thyroid count showed 

an uptake of 81.4 becquerels (Bq) (0.0022 

microcuries) of I-131, which would give an 

estimated thyroid dose of 35 millisieverts (35 

millirem). The licensee estimated the skin dose to 

the nuclear medicine technologist to be 1 Sv (100 

rem) over a period of 20 days. 

(Contact: Roberto Torres, 301-415-8115; e-mail: 

rjt@nrc.gov) 

2. Radiography Camera Model IR-100 Crank 

Assembly Malfunction 

Date and Place-March 31, 2000; Naval Fuel 

Supply Depot; Jacksonville, FL. 

Nature and Probable Consequences-On March 31, 

2000, at approximately 6:00 p.m., the licensee 

-Space Science Service-reported that it was 

unable to fully retract a 1.81-terabecquerel 

(49-curie) Iridium-192 source into the shielded 

position of its radiography exposure device, an 

Industrial Nuclear Company, Inc. (INC) IR-100. 

The work was being conducted at the Navy Fuel 

Depot in Jacksonville, FL, under reciprocity with 

NRC. The radiographers isolated the area and 

controlled access while taking corrective actions. 

The radiographers disassembled the crank that 

drives the source in and out of the exposure 

device. They found that a piece of the crank 

internals had malfunctioned and jammed the 

crank gears. The radiographers contacted the 

Radiation Safety Officer (RSO) by telephone, who 

consulted with them as they attempted to retract 

and lock the source. One of the radiographers 

loosened the drive cable connection from the 

device and manually pulled the source back into 

the camera by the cable, to a fully retracted and 

locked position. 

This radiographer received a whole-body exposure 

of 1.25 millisieverts (mSv) [125 millirem (mrem)] 

as measured by a self-reading pocket dosimeter, 

for the entire job during which the event occurred. 

Of this, 0.25 mSv (25 mrem) were attributed to 

actions taken to return the source to the camera. 

Cause or Causes-The INC examined the crank 

assembly and found that the inner lining of the 

drive cable, which is a Teflon tube, had pulled out 

of the outer drive cable housing and fed into the 

cranking mechanism between the gears, causing 

the malfunction. The exposed inner Teflon tube 

end was stretched and frayed. 

The NRC staff contacted INC on June 4 and 6, 

2000, regarding its investigation of the incident.

The INC informed the NRC staff that it examined 

the failed component. The outer drive cable 

housing was measured for stretch and was found 

to be the correct length of 7.6 meters (25 feet). 

The inner Teflon tube was examined and found to 

be in the original condition, at the crank end, but 

it was pulled back 12.7 centimeters (5 inches) 

from the source connector end. 

The manufacturer of the cable housing, Universal 

Metal Hose, was unable to determine the cause 

and stated that this type of failure had never 

occurred before. 

Based on the NRC staff's review of the case, 

improper handling of the radiography camera 

most likely caused the failure. Specifically, the 

operator probably pulled or lifted the camera by 

the drive cable. The cable stretched and returned 

to its original length. When the inner Teflon tube 

was stretched, it pulled loose from the outer drive 

cable housing. Before jamming, cranking of the 

source probably became more difficult as the 

inner Teflon tube moved into the drive cable 

housing connector. It is not clear why the operator seemed to ignore this problem and did not report 

it to the RSO or management. 

Actions Taken to Prevent Recurrence 

Licensee-The licensee's corrective actions 

include installing a backup drive cable and 

modifying its quarterly maintenance check to 

include the removal of the cover plate of the crank 

assembly, to inspect and service the drive cable 

and gears. 

NRC-The NRC staff reviewed the INC's inves

tigation on this incident and determined that this 

is not a generic issue for the following reasons: 

(1) The control sheath is designed to withstand 

112.5 ± 0.5 pounds of tensile force for 30 

seconds per cycle through 10 cycles. NRC's 

endurance tests, conducted by the Savannah 

River Technology Center (Page J-4 of 

NUREG/CR-6652) indicated that INC 

cameras did perform well within the specifica

tions similar to other manufacturers' cameras. 

(2) The crank assembly jam would not have 

occurred if the company's maintenance 

procedures, as well as daily and quarterly 

inspection procedures, were followed properly. 

(3) There are no similar incidents reported 

either for INC cameras or for cameras of 

other manufacturers. 

No actions are recommended because this failure 

is a single occurrence. However, the licensees

4
should follow the manufacturer's maintenance and 

inspection procedures. 

(Contact: Seung Lee, 301-415-5787; e-mail: 

sjl@nrc.gov) 

3. Electronic Pocket Dosimeters 

Both Siemens and MGPI have issued a "Customer 

Notification" on their electronic pocket 

dosimeters (EPDs). Siemens model Mk2 EPD 

occasionally has a software bug when configured 

with the EasyEPD2 program. This bug appears 

only when the "Intermittent Single Slow" alarm 

type is used. MGPI's model DMC 100 EPD may 

not function as expected when used incorrectly 

with the personal external alarm (PEA) -100. The 

problem occurs when the interface back jumper 

configuration is incorrect. 

A software bug has been identified when an 

EasyEPD2 program (version 1.5 or earlier) is used 

to configure the Siemens EPD Mk2. The bug can 

sometimes cause EPDs, written by the batch 

method, to have an incorrect setting in relation to 

that defined by the stored batch write file. 

Specifically, if the alarm tone type "Intermittent 

Single Slow" is used for any alarm, the alarm may 

be set in the EPD to the "Off" condition and 

therefore inactive. To correct this problem, the 

user can first read a sample EPD, then open the 

stored batch file. After performing this procedure, 

the settings in the file will overwrite the screen 

values, and subsequent EPDs will have the same 

settings as those specified in the batch parameters. 

The PEA-100 is designed to provide audible, 

visual, and tactile alarms in high-noise 

environments when connected to MGPI's model 

DMC- 100 EPD. The PEA is also designed to 

alert the user if its plug becomes partially 

removed from the dosimeter's interface back. If 

the interface back jumper configuration is 

incorrect, the PEA-100 will not perform as 

expected in the case that the PEA-100 plug 

becomes partially removed. MGPI's customer 

notification outlines the correct jumper 

configuration and warns customers of problems 

arising from jumper misconfigurations. This 

information is also available at the MGPI web 

site http://www.mgpi.com. 

There are currently no known Nuclear Material 

Safety and Safeguards licensees that use either of 

these EPD models, but it is important that the 

licensees be aware that this EPD problem exists. 

All current users of the previously mentioned 

EPDs, which consist of six nuclear power plants, 

have been notified of the problem. The U.S. 

Nuclear Regulatory Commission considers the

actions taken by Siemens and MGPI appropriate 

corrective measures. 

(Contact: Brian Smith, 301-415-5723; e-mail: 

bwsl@nrc.gov) 

SIGNIFICANT ENFORCEMENT ACTIONS 

Detailed information about these enforcement 

actions can be accessed via the U. S. Nuclear 

Regulatory Commission's (NRC's) homepage 

http://www.nrc.gov/OE/. Click on "Enforcement 

Actions." Cases are listed alphabetically. To access 

the complete enforcement action, click on the 

highlighted text after the name of the case. 

Gauge Licenses 

Bass Energy, Inc., Bruceton Mills, West Virginia 

EA 00-118. A Notice of Violation and Proposed 

Imposition of Civil Penalty in the amount of $8800 

was issued June 30, 2000. The action was based on 

failures: (1) to obtain written consent from NRC, 

before transferring control of licensed material to 

unlicensed companies, on two occasions; (2) to 

secure, or maintain constant surveillance of, 

licensed material, from unauthorized access; and 

(3) to provide information to NRC that was 

complete and accurate in all material aspects. 

Burning Rock Coal Company, Daniels, West 

Virginia EA 00-119. A Notice of Violation was 

issued June 30, 2000, based on a violation 

involving the deliberate operation of a fixed 

gauging device containing 740 megabecquerels 

(mBq) [20 millicuries (mCi)] of cesium-137 and 

11.1 gigabecquerel (300 mCi) of americium-2 4 1, 

without a specific or general license issued by 

NRC. Specifically, between July 8 and August 10, 

1999, Burning Rock Coal Co. possessed and used 

byproduct material by operating a coal ash 

analyzer located at Bass Energy, Inc.'s Deep Coal 

Mine No. 1, without a specific or general license 

from NRC authorizing the use or possession of 

such a device. 

Caribbean Quality Control Services, Inc., St. 

Croix, U.S. Virgin Islands EA 00-090. A Notice 

of Violation was issued on May 31, 2000, based on 

a violation involving the transfer of a portable 

moisture-density gauge containing licensed 

material to Alton A. Adams, Jr., Inc., a person 

who was not authorized to possess or use such 

byproduct material. During the time in which the 

non-licensed entity had possession of the gauge, 

an untrained technician was allowed to operate it. 

David Blackmore & Associates, Inc., Pottsdown, 

PA EA 00-124. A Notice of Violation was issued 

May 17, 2000, based on the failure to control and 

maintain constant surveillance of licensed

5
materials. Specifically, a portable nuclear density 

gauge containing 370 mBq [10 millicuries (mCi)] 

of cesium-137 and 5.15 mBq (150 mCi) of 

americium-241 was left unattended for a short 

period of time. During that time, the gauge was 

run over by a construction vehicle and was crushed. 

Medical 

Glendive Medical Center, Glendive, Montana EA 

00-076. A Notice of Violation and Proposed Imposition of Civil Penalty, in the amount of 

$2750, was issued June 29, 2000. The action was 

based on the failure to secure molydenum-99/ technetium-99m generators from unauthorized 

removal or access. During the inspection it was 

discovered that during certain weekends the 

generators were delivered to the nuclear imaging 

room where they remained unsecured for 

several hours. 

Clara Maass Medical Center, Belleville, NJ 

EA 99-257. A Notice of Violation was issued 

April 26, 2000, based on a violation involving the 

treatment of patients with a high-dose-rate 

(HDR) afterloading brachytherapy unit, after the 

source was replaced, without first checking to 

ensure that the source strength was consistent 

with the value provided by the manufacturer. 

The facility's procedures require a check of the 

source strength after each installation. Although 

some quality assurance checks were performed 

on the HDR unit before use, the medical 

physicist was unable to verify the manufacturer's 

source strength certification because the 

dosimetry system used to verify the source unit 

was not available. 

Virginia Commonwealth University, Richmond, 

VA EA 00-040. A Notice of Violation, issued 

April 24, 2000, involved the failure to control and 

maintain constant surveillance of a 321.16-mBq (8 .68-millicurie) strand of Iridium-192, and the 

failure to immediately report, by telephone, to 

NRC, the loss of licensed materials. The strand 

was lost in the bed linen during a brachytherapy 

treatment. The licensee found the strand at an 

off-site commercial laundry within 4 hours of 

identifying the loss. A civil penalty was not 

proposed because the facility has not been the 

subject of escalated action within the last two 

inspections. Credit was warranted for corrective 

action which included: (1) in-service refresher 

training provided to all nursing staff from the unit 

where the incident occurred; (2) posting nursing instructions on patients' doors and in their charts; (3) reminding laboratory personnel of correct 

waste disposal procedures; and (4) reviewing pertinent sections of Title 10 of the US. Code of

Federal Regulations regarding regulatory report

ing requirements 

Radiography 

Hayes Testing Laboratory, Inc., Louisville, KY 

EA 00-089. A Notice of Violation was issued 

June 9, 2000, based on a violation involving the 

performance of radiography in areas of NRC 

jurisdiction without filing an NRC Form 241, the 

failure to file revisions, and the failure to clarify a 

May 4, 1999, NRC Form 241, to identify new job sites and to include dates, for performing 

radiography, that were not previously submitted. 

Other 

Mallinckrodt, Inc., St. Louis, Missouri EA 

00-143. A Confirmatory Order Modifying 

License was issued June 9, 2000, to Mallinckrodt, Inc. The order was to resolve certain concerns 

NRC had with recently identified exposures in 

excess of the regulatory limits in 10 CFR Part 20 

and with radiation practices at Mallinckrodt, Inc. 

Syncor International Corporation, Woodland 

Hills, California EA 00-060. A Notice of 

Violation and Proposed Imposition of Civil 

Penalty in the amount of $2750 was issued June 

28, 2000. The action was based on an apparent 

failure to properly block and brace a package of 

radioactive material that fell from a Syncor vehicle on July 9, 1999, and an apparent failure to 

ensure that the door-locking mechanisms on a 

Syncor vehicle were adequate to meet NRC 

security requirements when radioactive material 

in a vehicle is left unattended. 

(Contact: Sally Merchant, OE, 301-415-2747; 

e-mail: slm2@nrc.gov) 

SELECTED FEDERAL REGISTER NOTICES 

(July 1, 2000-August 31, 2000) 

NOTE: U.S. Nuclear Regulatory Commission 

(NRC) contacts may be reached by mail at the 

U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 

PROPOSED RULES 

"List of Approved Spent Fuel Storage Casks: 

FuelSolutions\TM Addition," July 11, 2000, 65 FR 42647. 

Contact: Richard Milstein, 301-415-8149, 

e-mail: rim@nrc.gov. 

"Licensing Proceedings for the Receipt of 

High-Level Radioactive Waste at a Geologic Repository: Licensing Support Network, Design

6

__L___
Standards for Participating Websites," 65 FR 

50937, August 21, 2000. 

Contact: Francis X. Cameron, 301-415-1642, 

e-mail: fxc@nrc.gov. 

OTHER NOTICES 

"Major Revision to 10 CFR Part 71: Compatibility 

with ST - 1-The IAEA Transportation Safety 

Standards-and Other Transportation Safety 

Issues, Issues Paper, and Notice of Public 

Meetings," 65 FR 44360, July 17, 2000. 

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

e-mail: nst@nrc.gov. 

"Consolidated Guidance about Materials 

Licenses: Program-Specific Guidance about Well 

Logging, Tracer, and Field Flood Study Licenses" 

(NUREG-1556, Vol. 14), 65 FR 45116, 

July 20, 2000. 

Contact: Carrie Brown, 301-415-8092, e-mail: 

cxb@nrc.gov. 

"Consolidated Guidance about Materials 

Licenses: Guidance about Administrative 

Licensing Procedures" (draft NUREG-1556, Vol. 

20), 65 FR 45116, July 20, 2000. 

Contact: Carrie Brown, 301-415-8092, e-mail: 

cxb@nrc.gov. 

"Revision of Policy Statement on Medical Use of 

Byproduct Material," 65 FR 47654, August 3, 

2000." 

Contacts: Thomas Young, 301-415-5795, 

e-mail: tfy@nrc.gov 

Marjorie U. Rothschild, OGC, 

301-415-1633, e-mail: mur@nrc.gov. 

Charles T Gallagher, Gammatron, Inc.; "Petition 

for Rulemaking," 65 FR 49207, August 11, 2000. 

Contact: David L. Meyer, ADM, 301-415-7162 

or, Toll-Free: 1-800-368-5642, e-mail: 

dlml@nrc.gov. 

"Notice of Availability and Request for Comments 

on NUREG-1556, Vol. 19, 'Consolidated 

Guidance about Materials Licenses: Guidance for 

Agreement State Licensees about NRC Form 241 

"Report of Proposed Activities in Non-Agreement 

States, Areas of Exclusive Federal Jurisdiction, or 

Offshore Water" and Guidance for NRC 

Licensees Proposing to Work in Agreement State 

Jurisdiction (Reciprocity),' " 65 FR 49615, 

August 15, 2000. 

Contact: Carrie Brown, 301-415-8092, e-mail: 

cxb@nrc.gov.

"Notice of Formation of Rulemaking and 

Jurisdictional Working Groups; Uranium and 

Thorium," 65 FR 52049, August 28, 2000. 

(Contact: Paul Goldberg, 301-415-7842, e-mail: 

pfg@nrc.gov) 

GENERIC COMMUNICATIONS ISSUED 

(July 1, 2000 - August 31, 2000) 

Note that these are only 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

www.nrc.gov/NRC/GENACT/GC/index.html. 

Please note that this address is case-sensitive and 

must be entered exactly as shown. 

Information Notices (INs) 

IN 2000-10, "Recent Events Resulting in 

Extremity Exposures Exceeding Regulatory 

Limits" was issued on July 18, 2000. This notice 

was issued to all material licensees who prepare or 

use unsealed radioactive materials, 

radiopharmaceuticals, or sealed sources for 

medical use or for research and development, to 

alert addressees to recent events that resulted in 

personnel receiving occupational extremity doses 

in excess of the 0.5-sievert (50-rem) shallow dose 

equivalent limit specified in 10 CFR 

20.1201(a) (2)(ii). 

Contacts: Jamnes L. Cameron, RIII/DNMS, 

630-829-9833, e-mail: jlc@nrc.gov. 

Dr. Mohamed M. Shanbaky, RI/DNMS, 

610-337-5209, e-mail: mmsl@nrc.gov. 

IN 2000-11, "Licensee Responsibility for Quality 

Assurance Oversight of Contractor Activities 

Regarding Fabrication and Use of Spent Fuel 

Storage Cask Systems" was issued on August 7, 

2000. This notice was issued to all U.S. Nuclear 

Regulatory Commission (NRC) 10 CFR Part 50 

and Part 72 licensees, and Part 72 Certificate of 

Compliance holders, to remind licensees that they 

retain responsibility for all aspects of their quality 

assurance program, even when portions of the 

program are delegated to contractors, 

subcontractors, agents or, consultants. 

Contacts: Chet Poslusny, NMSS, 301-415-1341, 

e-mail: cxpl@nrc.gov. 

Charles Petrone, NRR, 301-415-1027, 

e-mail: cdp@nrc.gov.

7
Regulatory Issue Summaries (RIS)

RIS 2000-10 (Erratum), "Technical Information 

to Facilitate Public Access to the U.S. Nuclear 

Regulatory Commission's Agencywide Documents 

Access and Management System (ADAMS)" was 

issued on August 7, 2000. This erratum to this 

summary was issued to all NRC licensees, to

correct a typographical error with an internet 

address published in the original summary. 

Contact: NRC Public Document Room, 

202-634-3273 or 800-397-4209, e-mail: 

pdr@nrc.gov. 

(General Contact: Mark A. Sitek, 

301-415-5799, e-mail: mas3@nrc.gov)

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