ML20141F408

NMSS Licensee Newsletter.Number 97-1

ML20141F408
Person / Time
Issue date:	04/30/1997
From:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
References
NUREG-BR-0117, NUREG-BR-0117-N97-1, NUREG-BR-117, NUREG-BR-117-N97-1, NUDOCS 9705210299
Download: ML20141F408 (11)

Text

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,...,' s U.S. Nuclear Office of Nuclear NUREGlBR-0117 9

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Regulatory Material Safety No. 97-1 Commission and Safeguards March-April *1997 i

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_g DOE INTENT TO SEEK NRC facilities, because they should be in the best REGULATION OF NUCLEAR SAFETY compliance state, are most similar to NRC-regulated facilities, and are expected to remain stable and operational during the transition On December 20,1996, Secretary O' Leary period.

announced the U.S. Department of Energy's intent to submit legislation for U.S. Nuch Under the DOE recomnandations, NRC would Regulatory Commissica regulation of nudear focus on NE and ER facilities while legislation safety at DOE facilities, based on DOE is being drafted, during the first 2 years. NRC i

Working Group Recommendations. The would compare NRC and DOE programs, legislative phase is expected to last 2 years, identify needed regulatory changes, and become with DOE and NRC developing the legislation familiar with the facilities. Once legislation is and seeking views from stakeholders. As

! passed, NRC would begin to license / certify l NE, ER, and selected EM and DP facilities proposed by DOE. after necessary legislation is enacted, external regulation would be (privatization projects), with the object of implemented through a multi-phase process regulating the entire group of ER and NE 6at involves placing DOE facilities under facilities by the end of the first 5-year period.

NRC regulation, as summarized below:

The Commission considered its potential Phase 1 - Regulation of all Nuclear Energy future role in regulating DOE nuclear safety (NE)ies would be transferred toand Energy Research (ER) in Direction Settmg Issue No. 2, as part of facilit NRC's strategic assessment and rebaselining NRC and the States (Years 1-5).

mtiative. In response to the Secretary of Energy's decision, strong public support during the comment process on strategic assessment, Phase 2 - Regulation of all Environmental and additional NRC evaluations, the Com-Management (EM) facilities mission endorses NRC's taking responsibility would be transferred to NRC and f r the regulatory oversight of certain DOE the States (Years 6-10).

nuclear facilities, provided: (1) there is a clear delineation of the facilities, activities, and t

Phase 3 - Regulation of all Defense Pro-issues that NRC will have to address; and grams (DPs) facilities would be (2) NRC is given the necessary funding and transferred to NRC and the Fbte staffing resources and the regulatory authority (after Year 10).

to fulfill its mission effectively in this area.

The number of DOE nuclear facilities is Regulation of DOE nuclear safety could have expected to decreasc as a result of closure, large impacts on NRC. In recognition of these decontamination, and decommissioning, over potential impacts, the Commission is estab-the next 12 years. As planned by DOE, NRC lishing a sen r-level NRC task force to work l

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regulation would begin with ER and NE with DOE in assessing the impacts, planning Ma map IlllilllIlll!lllljillljilligill>

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9705210299 970430 o

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3 the transition, and developing the necessaiy Page legislation.

1. DOE Intent to Seek NRC Regu-(Contact: Michael F. Weber, NMSS, lation of Nuclear Safety (Contact:

301-415-7190, e-mail: mfw@nrc. gov)

Michael Weber, NMSS, 301 -415 - 7990).................... 1 NEW CONSTRAINT RULE ON AIR EMISSIONS

2. New Constraint Rule on Air Emissions (Contact: Sami Sherbini, In 1989, the U.S. Environmental Protection NMSS, 301-415-7902)............. 2 Agency (EPA) promulgated a regulation that

3. Extension of License Terms for required the U.S. Nuclear Regulatory Com

.t Material Licenses (Contact: Diane S.

1 nussion and Agreement State licensees to umi their air emissions of radioactive materials so Flack, NMSS, 301 - 415 - 5681)....... 3

-i that no member of the public would receive an

4. Use of Alarm Ratemeters in effective dose in excess of 0.1 mSv (10 mrem)

Industriai dadiography (Contact:

in a year froin til radionuclides in the emissions, Bruce Carrico, NMSS, 1

and no more than 0.03 mSv (3 mrem)in a year 301 -415 - 7826).................... 4 from radioiodine. Licensees whose emissions exceeded 0.01 mSv (1 mrem)in a year from all

5. Integrated Safety Analyses at Fuel radionuclides were also required to file reports Cycle Facilities (Contact: Mary T.

with EPA. The regulation was contained in Adams, NMSS, 301 - 415 - 7249)...... 5 EPA's 40 CFR Part 61, Subpart I.

6. Problems with Occupational Exposure In addition to being subject to EPA's Subpart I, Reports (Contact: Mary L. Thomas, NRC licensees continued to be subject tc the RES, 301 -415-6230)............... 5 limits on effluents contained in 10 CFR Part 20' which requires licensees to limit exposures t

7. Inspection of Licensee Ouality members of the public to 1 mSv (100 mrem)in Management Programs (Contact:

a year from all sources, mcludm, g extern t Sally Merchant, NMSS, radiation exposures as well as exposures 301 -415 -7874)................... 6 received from air and water effluents. NRC

8. Defacing Radioactive Material also requires licensees to implement as low as Labels before Release of Containers is reasonably achievable (ALARA) measures (Contact: Susanne Woods, NMSS, to minimize exposures to the public.

301 -415 -7267).................... 7 Promulgation of EPA's rule resulted in two

9. Selected FederalRegister Notices Federal agencies regulating the sanu wtivity (General

Contact:

Paul Goldberg,

-namely, air emissions from NRC mensees.

NMSS, 301-415-7842)............. 7 To avoid such duplication, EPA and NRC

10. Generic Communications Issued (General

Contact:

Kevin Ramsey, Comments, and suggestions you may NMSS, 301 -415-7887)............. 8 have for information that is not currently being included, that might be helpful to

11. Significant Enforcement Actions licensees, should be sent to:

(Contact:.ioseph DelMedico, OE, E. Kraus 301 -415 -2739).................... 9 3

NMSS Licensee Newsletter Editor Office of Nuclear Material Safety and Safeguards j

Two White Flint North, agreed tc transfer the 0.1 mSv/yr (10 mrem /yr) l Mail Stop 8-A-23 dmit on air emissions in EPA's Subpart I to i

U.S. Nuclear Regulatory Commission NRC's Part 20 as a constraint on air emissions.

Washington, D.C. 20555-0001 This was achieved in two steps: NRC announced

]

its new constraint rule, incorporated into 1

a

Part 20, in the Federal Register on Decem-on Releases of Airborne Radioactive Materials her 10,1996, to be effective January 9,1997; to the Environment for Licensees Other Than and EPA rescinded Part 61, Subpart I, for NRC Power Reactors," published in December licensees, in a Federal Register notice on 1996. Licensees may obtain a copy of the December 30,1996. Summary information on guide, free of charge, by writing to the Office Subpart I, as well as the Federal Register of Administration, Attention: Distribution and rescission notice, may be accessed via the Services Section, U.S. Nuclear Regulctory Internet at http://www. epa. gov / radiation /

Commission, Washington DC 20555-0001, or neshaps.

by fax at (301) 415-2260.

The constraint rule, contained in 10 CFR (Contact: Sami Sherbini, NMSS, 20.1101, states the following:

301-415-7902, e-mail: sxs2@nrc. gov)

EXTENSION OF LICENSE TERMS FOR To implement the ALARA requirements of AIATERIAL LICENSES

@ 20.1101(b), and notwithstanding the requirements in @ 20.1301 of this part, a Effective February 6,1997, the U.S. Nuclear constramt on air emissions of radioactive Regulatory Commission extended the license material to the environment, excluding term for material licenses issued pursuant to Radon-222 and its daughters, shall be 10 CFR Part 30,* " Rules of General Applica-established by licensees other than those bilit" to Domestic Licensing of Byproduct subject to @ 50.34a, such that the individual Material"; Part 40," Domestic Licensing of

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member of the public likely to receive the Source Material"; and Part 70," Domestic highest dose will not be expected to receive Licensing of Special Nuclear Material," from a total dose equivalent in excess of 10 mrem the current 5-year period to a 10-year period, (0.1 mSv) per year from these emissions. If on the next renewal of the affected licenses, a heensee subject to this requirement with the exception of licenses issued pursuant exceeds this dose co straint, the licensee to 10 CFR Part 35. The 5-year term for licenses shall report the exceedance as provided in other than those issued pursuant to Part 35 has

@ 20.2203 and promptly take appropriate been a matter of practice and is not codified in action to ensure against recurrence, the regulations. The license term for licenses issued pursuant to Part 35 is established by The rule imposes a constraint on air emissions regulation and must be revised by rulemaking.

of 0.1 mSv (10 mrem) in a year, in addition to the existing limit on public dose of 1 mSv/yr In late 1996, the staff prepared a paper for the (100 mrem /yr) from all sources originating in Commission, SECY-96-252," Extension of the licensee's operation. The difference License Term for Material Licenses," that con-betweea a constraint and a limit is that tains information on the purpose, background, enforet rc nt action is taken if a limit is and discussion of the extension of the license exceeded, but not if a constraint is exceeded.

dmation period. This paper is available through Licensees are, however, required to report to NRC's Public Document Room (202-634-NRC any exceedance of the constraint, and 3273 or 1-800-397-4209) for a nominal the report should include a description of the charge (to cover copying). NRC believes that actions to be taken to prevent recurrence and the license duration period can be extended the schedule for completion of these actions.

without adverse impact on public health and Enforcement action may be taken if the safety. Applications for new or renewed licensee does not file the required report, or if material licenses will continue to undergo a appropriate action is not taken to prevent thorough technical review to ensure that the recurrence. There are no reporting require-licensed program employs up-to-date technology ments connected with the constraint rule for and practices in the protection of health, safety, licensees who do not exceed the constraint, and the environment and compliance with any new or amended regulations. Licensees will Acceptable methods to show compliance with the constraint on air emissions are described

• Reference to Part 30 is intended to indude 10 CFR Parts 32,33. 34, in NRC's Regulatory Guide 4.10," Constraint s' dea, and any ther regulations that are developed in the Part 39 3

continue to be required to apply for license failed to conduct a required survey to confirm amendments for certain proposed changes to that the cobalt-60 source was safely stored and their programs. Staff will continue to identify, shielded. Instead the source was only returned by inspection or other means, violations that to a " flexed" area within the source guide tube affect public health and safety, and to take and remained fully exposed. The radiography appropriate enforcement actions. Finally, was conducted within an enclosed " exposure licensees will continue to be made aware of vault" diat the first radiographer locked when health and safety issues through the issuance he exited. When the second radiographer of generic communications, arrived to start his shift, he confirmed that his alarm ratemeter and other personnel monitor-Although beh new and renewal applications ing devices were properly functioning. He then for materials licenses will be considered for a positioned his ear plugs, because the exposure 10-year license term, NRC retains the option vault was in a high-noise area and hearing pro-to issue licenses for shorter terms in situations tection was required. He entered the vault to where the industry or NRC has not had exten-set up the equipment in preparation for the sive experience in using or regulating the next exposure. The second radiographer as-proposed use of the material, and any other sumed that the exposed source was safely stored situations that would warrant increased atten-in the device. While the radiographer conducted tion on a case-specific basis. Headquarters staff setup activities, the site break whistle blew and is currenfty developing furtaer guidance on the noise level was greatly reduced. At this this issue for the licensing staff.

point, the radiographer noted that his alarm ratemeter had activated and that his pocket The Commission has approved the rulemaking dosimeter was offscale. He checked the device plan to remove the 5-year term for medical controls immediately, retracted the source into licenses in Part 35 so that there will no longer the radiography device, and initiated emergency be an inconsistency between how heense terms response procedures.

for medical licenses and all other material licenses are established. Staff is currently pre-paring a proposed rule that would revise 10 NRC has been notified of other events where CFR 35.18 to delete any reference to the 5-year radiographers were unable to hear alarm rate-license term, so that future Commission meters in high-noise environments or where decisions regarding the duration of materials hearing protection was required. Although the licenses would apply uniformly to all types of alarm ratemeter manufacturers all confirm material licensees.

that their equipment complies with American National Standards Institute criteria, radiog (Contact: Diane S. Flack, NMSS, raphy licensees and their workers need to be 301-415-5681, e-mail: dsfl@nrc. gov) aware that some high-noise environments will exceed these limits. In these cases, devices that USE OF ALARM RATEMETERS IN provide alternative means for alerting users to INDUSTRIAL RAPP) )RAPIIY the alarm should be considered. NRC has been informed that headphones, which also In the U.S. Nuclear Regulatory Commission's provide hearing protection, may be used with regulations for industrial radiography (10 CFR some devices, and other devices with very bright Part 34), Section 34.33(a) requires that indi-LED lights are available too. Licensees need viduals performing radiographic operations to emphasize to their employees both the wear an alarm ratemeter. Recently, an NRC importance of performing complete and ade-hec nsee reported an event related to the use quate smveys and the fact that alarm ratemeters of riarm ratemeters.

must not be relied on in lieu of a survey. As the above event indicates, in radiography, it is This event.mvolved two radiographers at an always better, even when not required, to survey mhstrial complex--one of them received an and ensure safe conditions, than to assume.

g e3,0sure exceedmg the regulatory limit. The event began when the first radiographer failed to completely return the source to the (Contact: Bruce Carrico, NMS radiography device after an exposure and 301-415-7826, e-mail: jbc@nr y

4

INTEGRATED SAFETY ANALYSES AT SRP section. The SRP, and the revised Part 70, FUEL CYCLE FACILITIES will allow for flexibility in acceptance criteria based on the varying levels of risk associated The Division of Fuel Cycle Safety and Safe-with structures, systems, equipment, and guards (FCSS) has developed a plan for administrative procedures important to safety, revising 10 CFR Part 70," Domestic Licensing This approach is in accordance with NRC's of Special Nuclear Material," to correct identi-risk. informed, performance-based regulatory fied deficiencies in the current rule. Six U.S.

direction.

Nuclear Regulatory Commission-developed alternatives are being considered for the Part 70 (Contact: Maty T. Adams, NMSS, revision, and the industry has proposed an 301-415-7249, e-maih mta@nre. gov) additional alternative in a rulemaking petition PROBLEMS WITII OCCUPATIONAL submitted on September 30,1996. NRC is EXPOSURE REPORTS considerm, g the revision options m light of the Commission's direction toward risk-informed, Licensees authorized to perform one of the performance-based regulation.

activities specified in 10 CFR 20.2206(a) are required to submit annual occupational radia.

Several of the propcsed alternatives, including tion exposure reports to the U.S. Nuclear the industry's petition. contain a requirement Regulatory Commission. These specified for the performance of Integrated Safety activities include radiography, reactor fuel Analyses (ISAs) of licensed processes. NRC fabrication, and the manufacture and distribu-and industry generally agree on the need to tion of certain quantities of byproduct material.

perform ISAs or equivalent analyses, and most If you are one of these licensees, you must fuel cycle licensees have committed to per-submit a separate NRC Form 5 for each forming them for their licensed operations.

person for whom monitoring is required each However, there is not a consistent understand-year. Electronic media containing the same ing of the depth and breadth of an ISA. FCSS information are acceptable also. The informa-has developed a draft ISA guidance document tion in these repotts is entered into the (Draft NUREG-1513) that provides guidance Radiation Exposure Information and to NRC fuel cycle applicants and licensees on Reporting System (REIRS).

how to perform an ISA and document the results. The guidance document defines an The following problems have been encountered 5

ISA as a systematic examination of a facility's in reviewing the annual occupational radiation processes, equipment, structures, and per.

exposure reports:

sonnel activities to ensure that all relevant hazards that could result in unacceptable

1. Some licensees are continuing to submit consequences have been adequately evaluated, the statistical summary, to NRC, that yvas and appropriate protective measures have required by 10 CFR 20.407. This require-been identified. The guide also identifies the ment was deleted as of January 1,1994.

role of an ISA in a facility's safety program,

2. Some licensees are continuing to subm'it identifies and describes several generally termination reports, to NRC, that were i

accepted ISA methods, and provides guidance required by 10 CFR 20.408. This require-in choosing a method.

ment was deleted as of January 1,1994.

The only exposure report that NRC requires NRC is also developing a standard review plan is the annual occupational radiation expo-l (SRP) that provides guidance to license sure report for each monitored individual reviewers who perform safety and environ-(the aforementioned NRC Form 5). The mentalimpact reviews of applications to termination report (NRC Form 4)is to be construct or modify and operate fuel cvde given to the monitored individual, on facilities. Each SRP wtion addresses the employment termination, and should not regulations pertinent to specific technical be sent to NRC.

matters, the acceptance criteria used by the staff, review procedures, conclusions, and

3. Licensees using REMIT software should directions to the staff on how to implement the send us a diskette, not paper. Reviewing 5

and performing data entry on hardcopy alock 11, DDE-

+ Block 15, CEDE Block 17 TEDE

=

reports require additional resources and can introduce errors in the data. The NRC mse value

+ mse value sum or values

=

contractor for the REIRS project has ED or NR

+ Dose Value Dose value

=

developed software called REIRView, to check for errors in electronic submittals, D se Value

+ ND or NR Dose %1ue

=

for both the Agency's and the licensees' ND or NR

, ND ND

=

use. It is available from the REIRS website at www.saic.com/home/nrc,_ rad.

Block 11, DDE

+ Biock 16, CDE Block 18, ToDE

=

4. Many of the forms submitted are incom-Dose value

+ Dose value sum or values

=

plete. If you submit an NRC Form 5 supplied by your dosimetry processor, it is ND or NR

+ Dose value Dose Value

=

your responsibility to ensure that the form Dose vaiue

+ NR NR

=

is complete. The following blocks are often incomplete: (Please note that ND = Not Nse value

+ NC NC

=

Detectable; NR = Not Required; and NC ND or NR

+ NC NC

=

= Not Calculated.)

• DDE - Deep-dose equivalent.

Block 4 - sex of the monitored individual.

7. Block 20 of NRC Form 5 provides for the (The REIRS database is covered by the signature of the li ensee's authorized Privacy Act of 1974 and thus is not available representative responsible for the data. If a to the public.)

letter is maintained on file certifying the database used to generate electronic media Block 8 - license number.

submitted to NRC, the licensee may place a note in Block 20 (e.g.,,' signature on file"). However, if the exposure reports are Block 14 - shallow dose equivalent, maxi-provided to NRC on Form 5's, rather than mum extremity. If extremity monitoring is by electronic transmission, the forms must not required, "NR" should be entered.

be signed.

Block 15 - Committed Effective Dose NRC Forms 4 and 5 are periodically revised.

Equivalent (CEDE). If internal monitoring The latest version of these forms may be is not required, "NR" should be entered.

btamed by contactmg the NRC Information and Records Management Branch at 301 - 415 - 7230.

Block 16 - Committed Dose Equivalent (CDE). If internal monitoring is not re-(Contact: Mary L Thomas, RES, quired,"NR" sliould be entered. If CEDE 301-415-6230 or e-mail: mit1@nrc. gov) is measurable, but less than 0.01 sievert (1 rem), you are not required to calculate the INSPECTION OF LICENSEE QUALITY value of CDE, and "NC" may be entered MANAGEMENT PROGRAMS in block 16. If the CEDE is greater than 0.01 sievert (I rem), you must determme On December 23,1996, the U.S. Nuclear t e value of CDE and enter the value in Regulatory Commissica ssued revised inspection guidance for regularly scheduled and reactive inspections of heensee Quah,ty Management Programs (QMPs). This guidance

6. The values entered in Block 17, Total supersedes the Temporary Instruction for Effective Dose Equivalent (TEDE), and inspection of OMPs, dated August 1,1994.

Block 18, Total Organ Dose Equivalent Under the new guidance, inspectors ac esing (TODE), are often incorrect. The following a more performance-based approach to the tables demonstrate ho v to determine review of OMP implementation. Inspectors TEDE and TODE.

will continue to observe and interview 6

o

individuals as they perform applicable duties, were identified as overpack jackets used for l

to ensure that the QMP, as implemented, Technetium-99m generators.

l provides high confidence that byproduct material, or radiation from byproduct material, Containers holding or contaminated with U.S.

is administered as directed by the authorized Nuclear Regulatory Commission licensed user. However, considerably less emphasis will material are required to be clearly labeled, be placed on the OMP portion of the overall pursuant to 10 CFR 20.1904. Before removal inspection, unless, during the inspection, the or disposal of empty, uncontaminated con-l inspector concludes that: (1) a OMP has not tainers to unrestricted areas, licensees are been appropriately implemented for all required to deface the radioactive material modalities requiring a QMP; (2) a recordable label or otherwise clearly indicate that the event has occurred, and the licensee did not container no longer contams radioactive identify, evaluate, and institute corrective materials [10 CFR 20.1904(b)] Such measures actions; or (3) an unreported or previously will preclude the confusion and concern unidentified misadministration was identified caused by the aforementioned case.

during the inspection. The changes are con-sistent with the performance orientation The release of contaminated containers to the associated with the Quality Management rule, pubhc is a violation of the waste disposal and should result in a less obtrusive approach regulation in 10 CFR 20.2001, which requires to inspection of the licensee's QMP.

h,eensecs to transfer contaminated containers to authorized recipients specifically licensed to receive the waste. It is a violation of 10 CFR Reactive inspections are conducted to ensure 20.1801 and 10 CFR 20.1802, also. These that the b,eensee reviews misadministrations in regulations require licensees to: (1) secure a timely, objective, systematic, and technically stored licensed material from unauthorized sound manner. Probable causes must be removal and access; and (2) maintain control exammed, and corrective actions identified, and constant surveillance oflicensed material evaluated, and instituted. The inspection of that is in a contnNd or unrestricted area and the OMP implementation will determine if the not in storage.

licensee effectively implemented policies and procedures designed to meet the objectives (Contact: Susanne Woods, NMSS, and requirements in 10 CFR 35.32," Quality 301-415-7267, e-mail: srw@nrc. gov) l Management Program," and the notification, reporting, and recordkeeping requirements in SELECTED FEDEI61L REGISTER NOTICES 10 CFR 35.33.

January 1,1997 - February 28,1997 i

I (Contact: Sally Merchant, NMSS, NOTE: Contacts may be reached by mail at 301-415-7874, e-mail: sim2@nrc. gov) the U.S. Nuclear Regulatory Commission, l

Washington, D.C. 20555.

DEFACING RADIOACTIVE MATERIAL LABELS BEFORE RELEASE OF Regulatory Guides CONTAINERS Issuance of Regulatory Guide 10.12,"Prepara-tion of Petitions for Rulemaking under 10 Radioactive material labels on empty, uncon-CFR 2.802 and Preparation and Submission of taminated containers must be defaced before Proposals for Regulatory Guidance Docu-l the containers are placed m unrestricted areas.

ments," 62 FR 1138, January 8,1997.

Contact:

Recently, a student was found using a T. Y. Chang, 301 - 415 - 6450.

4 hard-foam drink insulator that was labeled j

" Caution, Radioactive Material." At a teacher's Final Rules 4

request, the insulator was surveyed and radioactivity was not present. The student's

" Recognition of Agreement State Licenses in mother possessed two additional insulators Areas under Exclusive Federal Jurisdiction that carried the same label but were free of within an Agreement State," 62 FR 1662, radioactivity also. Subsequently, the insulators January 13,1997. Contacts: Hampton f

7 l

Newsome, 301 -415-1623, e-mail:

Policy Statement, " Policy and Procedure for HHN@nrc. gov; Mark Haisfield, Enforcement Actions," 62 FR 6677 February 301-415-6196, e-mail: MFH@nrc. gov.

12,1997.

Contact:

James Lieberman, 301 -415 - 2741.

" Duplication Fees," 62 FR 3984, January 28, 1997.

Contact:

Thomas E. Smith, (General

Contact:

Paul Goldberg, NMSS, 202 - 634 -3366.

301 - 415 - 7892)

" Criteria for the Release of Individuals GENERIC COMMUNICATIONS ISSUED Administered Radioactive Material," 62 FR (NOVEMBER 1,1996 - FEBRUARY 1, 4120, January 29,1997.

Contact:

Stewart 1997)

Schneider, 301 - 415 - 6225.

Note that these are only summaries of U.S.

" Fissile Material Shipments and Exemptions,"

Nuclear Regulatory Commission generic 62 FR 5907, February 10,1997.

Contact:

communications. If one of these documents Naiem S. Ttmious, 301 -415-6103, e-mail:

appears relevant to your needs and you have INTERNET:NST@nrc. gov.

not received it, please call one of the technical contacts listed below.

"USEC Privatization Act: Certification and Licensing of Uranium Enrichment Facilities,"

Generic Letters (GLs) 62 FR 6664 and 6672 (Direct Final Rule ar,d Proposed Rule), February 12,1997.

Contact:

GL 96-07," Interim Guidance on Trans-C.W. Nilsen, 301 - 415 - 6209.

portation of Steam Generators," was issued on December 5,1996, to all nuclear Proposed Rules power reactor facilities. This notice notifies 4

them that the U.S. Department of Trans-

" Revision of Fee Schedules; 100% Fee portation (DOT) and NRC have agreed on Recovery, FY 1997," 62 FR 8885. February 27, how DOT and NRC transportation require-1997.

Contact:

C. James Holloway, ments apply to the shipping of discarded 301 - 415 - 6213.

steam generato:w.

Contacts:

Other Notices Richard Boyle, DOT,202-366-4545, e-mail: rick.boyle@rspa. dot. gov.

" Commonwealth of Massachusetts: Staff Earl P. Easton, NMSS, 301 - 415 - 8520, Assessment of Proposed Agreement between e-mail: exe@nrc. gov.

the Nuclear Regulatory Commission and the Commonwealth of Massachusetts," 62 FR 117, Information Notices (ins)

January 2,1997.

Contact:

Richard L. Blanton, 301-415-2322, e-mail: RLB@nrc. gov.

IN 96-63," Potential Safety Issue Regarding the Shipment of Fissile Material," was

" Draft Multi-Agency Radiation Survey and issued on December 5,1996, to all licensees Site Investigation Manual (EPA /NRC)," 62 FR authorized to possess special nuclear 736, January 6,1997.

Contact:

Robert A. Meck, material in unsealed quantities greater than 301 - 415 - 6205.

critical mass. This notice alerts thein to a potentially unsafe situation where one of Proposed Department of Energy Rule, Exten-the exemptions in 10 CFR 71.53 would not sion of Comment Period," General Guidelines provide adequate criticality safety if large for the Recommendation of Sites for Nuclear amounts of an exempt concentration of Waste Repositories," 62 FR 4941, February 3, fissile material were transported in the 1997.

Contact:

April V. Gil, DOE, presence of a special moderatirg material 1 - 800 - 967 -3477.

(i.e., beryllium). NRC has concicded that the current regulations need to be revised.

Policy Statement, "NRC Enforcement Policy,"

Contact:

62 FR 5494, February 5,1997.

Contact:

James Earl P. Easton, NMSS, 301 - 413 - 8520, Lieberman, 301 - 415 - 2741.

e-mail: exe@nrc. gov.

8

IN %-66,"Recent Misadministrations

Contact:

Caused by Incorrect Calibrations of Timothy C. Johnson, NMSS, Strontium 90 Eye Applicators," was issued 301-415-7299, e-mail: tcj@nrc. gov.

on December 13,1996, to all medical licensees authorized to use strontium-90 AL 97-01," State Initiatives to Legalize eye applicators. This notice alerts them to Schedule 1 Drugs," was issued on recent misadministrations caused by January 17,1997, to all power reactor licensees and alllicensees authorized to incorrect source sr ngth determinations.

Contacts:

Possess and transport Category I nuclear Jose M. Diaz-Velez, RII, material. This letter reminds them that the 404-331-7438, e-mail: jxd2@nrc. gov.

requirements of 10 CFR Part 26 remain in

.Emilio M. Garcia, RIV, effect even where State law attempts to 510-975-0239, e-mail: emg@nrc. gov.

legalize the use of Schedule 1 drugs.

James A. Smith, NMSS, Contacts:

301-415-7904, e-mail: jas4@nrc. gov.

Loren Bush, NRR,301-415-2944, e-mail: lib @nrc. gov.

Brett Miller, NMSS,301-415-8152, IN 96-70," Year 2000 Effect on Computer e-mail: btm@nrc. gov.

. System Software," was issued on December 24,1996 to all licensees. This (General

Contact:

Kevin Ramsey, NMSS, notice alerts them to potential problems 301-415-7887, e-mail: kmr@nrc. gov) their computer systems and software may encounter as a result of the change to the SIGNIFICANT ENFORCEMENT ACTIONS

-new century.

Detailed information regarding these enforce-ar A. Sitek, NMSS ment actions can be accessed via the U.S.

301-415-6155, e-mail: n$as6@nrc. gov.

Nuclear Regulatory Commission homepage Michael Kaltman, NRR,

gov /. Click on, Nuclear 301-415-2905, e mail: mxk2@nrc. gov.

Materials, then Enforcement Program,,, and finally "Enfon.ement Actions Issued." Cases IN 96-72," Undetected Failures that May are listed alphabetically. For details, click on Occur during Patient Treatments with the highlighted text following each case.

Teletherapy Devices," was issued on l

December 24,1996, to all teletherapy Academic licensees. This notice alerts them to a l

recently reported failure of an AECL The Pennsylvania State University, University Theratron 780 teletherapy device to expose Park, Pennsylvania, EA 96-499. A Notice of the source during patient treatment, and Violation was issued based on violations for l

- the potential for similar failures in all older failure to secure licensed material.

AECL teletherapy devices manufactured Measuring Gauges before 1985.

i

Contact:

U.S. Engineering Labs, Inc., Rahway, New Robert L Ayres, NMSS, Jersey, EA 96-245. A Notice of Violation was 301-415-5746, e-mail: rxal@nrc. gov.

issued for failure to maintain control of a l

gauge containing licensed material, and use of E" E#

E E Administrative Letters (ALs) was damaged at a temporary job site when a truck ran over it.

AL 96-05," Compliance with the Rule

' Timeliness in Decommissioning of Wilcox Associates, Cadillac, Michigan, EA Material Facilities,' " was issued on 96-257. A Notice of Violation was issued for November 5,1996, to all material and fuel failure to maintain control of a gauge containing l

cycle licensees. This letter informs them of licensed material. The gauge was damaged at l

their responsibilities and highlights a temporary job site when the user struck it applicable compliance dates.

with his vehicle.

I 9

I

Medic:1 Other MEterials Licensees Abington Memorial Hospital, Abington, Penn.

Raytheon Engineers and Constructors,Inc.,

sylvania, EA 96-186. A Notice of Violation Honolulu, Hawaii, EA 96-205. A Notice of was issued for failure to conduct a quarterly Violation was issued because a source was physical inventory of a particular brachy.

stored and used in an unrestricted area and therapy source.

was not secured nor under constant sutveillance.

Geisinger Medical Center, Danville, Pennsyl-vania, EA 96-189. A Notice of Violation was Roy Sadovsky, D.V.M., Floral Park, New York, issued for failure to maintain complete and EA 96-349. An Order Suspending License nd Demand for Information were issued accurate information on a label container and a waste disposal log, and for failure to conduct based on deliberate use of gold 198 seeds to treat horses at an unauthorized location.

required surveys, Syncor International Corporation, Chatsworth, South Haven Community Hospital, South California, EA 96-104. A $2500 civil penalty Haven, Michigan, EA 96-099. A Notice of was assessed because the lock on an employee Violation was issued for deliberate viohtions locker at the licensee's facility was deliberately involving receipt of licensed material at contaminated with technetium-99m by another locations other than those listed on the Syncor employee.

license, and failure to measure dosages of technetium-99m before patient administration-University of Oklahoma, Oklahoma City, Oklahoma, EA 96-049. A $2500 civil penalty Universal Imaging, Inc., Taylor, Michigan, EA was assessed for leaving radiopharmaceuticals96-157. A Notice of Violation was issued unattended in an unlocked vehicle during a for violations of license conditions that led to a delivery.

misadministration, and for failure to report the misadministration to NRC within the (Contact: Joseph DelMedico, OE, required time.

301-415-2739, e-mail: rjd@nrc. gov) l l

t l

r 10

• U.S. GOVERNMENT PHINTING OFFICE: 1997 417-801/60026

1 UNITED STATES pg m a i

NUCLEAR REGULATORY COMMISSION POSTAGE AND FEES PAID USNRC WASHINGTON, DC 20555M1 PERMIT NO. G67 OFFICIAL BUSINESS

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