ML20198P329

Responds to NRC ,Requesting Addl Info for Request for Amend to License SNM-362.Set of Pages from Matls License Document Showing Revs,Request for NIST Matls License Document,Encl

ML20198P329
Person / Time
Site:	07000398
Issue date:	12/23/1998
From:	Pevey L NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9901070030
Download: ML20198P329 (18)

Text

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UNITE 3 STATES DEPARTMENT OF COMMERCE National Institute of Standards cnd Technology k V/

Gaithersburg, Maryland 208990001 l

. December 23,1998 Division of Fuel Cycle Safety License No. SNM-362 and Safeguards Docket No. 070-00398 Office of Nuclear Materials Safety and Safeguards

' U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Response to Letter of Nov. 18,1998 Gentlemen:

This letter is in response to your letter of November 18,1998, requesting additional information for our request for amendment to license number SNM-362. Several enclosures to this letter restate our amendment requests and offer the additional information requested. Enclosure 1 is a set of pages from the Materials License Document showing the revisions we request for the NIST Materials License Document. Enclosure 2 is a drawing of the vertical teletherapy beam facility with the additional radiation monitor and additional security door interlock shown. Enclosure 3 is a description of the vertical teletherapy beam facility, with details that address the specific issues cited in your letter.

l Incorporated in the description are operational details for the facility modifications listed later in this letter.

- The current license cites Gaithersburg, MD as the authorized place of use. We request that Item 9 in the license be changed to reflect the permission for off-site operations by adding a phrase such as "and i

temporary job sites under NRC jurisdiction."

j The revised Section 1.8, page I-1-3, of the NIST Materials License Document requests exemption from certain parts of 10 CFR Part 36, in accordance with the information supplied elsewhere in this letter. With the changes in the program we are proposing, there is no need to revise Section 2.6, page I;

l-2-3, as previously submitted.

I The revised section 2.11, page I-2-4, reflects administrative changes at NIST that affect titles of persons performing cenain functions, especially the fire safety review procedures utilized for major facility change proposals, but including organizational title changes for groups involved in fire safety.

/O T The revised section 3.2.8, paragraph B, page 1-3-4, deletes the 0.05 microcurie removable contamination level for teletherapy sealed source leakage.

Certain modifications to the physical plant, operationally described in the enclosed information sheet, are being made to the vertical radiation beam facility as a consequence of the exemption request review and response. The modifications, designed to support our request for exemptions to certain (D? m g a g,j NIST PDRh

portions of 10 CFR Part 36, are as follows:

a) replacement of the existing door locks to B034 and B036 with high security locks, with a limited number of keys to be controlled by the Responsible Facility Operator (RFO);

b) installation of additional small, manually operated fire extinguishers within B034 and B036, in addition to an existing manual fire extinguisher in B035; c). -installation'of smoke detectors in B034 and in B036, with tie-in to the existing fire signal

' lines;

-d) installation of devices that will signal the security console of attempts at unauthorized entry to B034 or B036 when the system is armed; l

e) installation of locking devices on the pit grates to prevent access by unauthorized persons; and f) installation of an additional radiation monitor system, battery powered, with logarithmic l

readout, that will indicate an elevated radiation level when the beam is on and will provide

. visible and audible alarms when the door is opened following a beam-on elevated level even though the shutter has closed on the source and the meter has returned to the background reading.

We consider the facility to have met, throughout its lifetime and with no variances, the conditions specified in 10CFR Part 35.615(b). Should a person cnter'one of the radiation rooms without deactivating the source at the console, and should there be multiple failures ofinterlocks for closing the shutter and multiple failures of the radiation monitors to signal an elevated radiation level, the maximum "Co loading in one of the teletherapy heads, i.e.,12 kCi, yields a beam esposure rate value of approximately 30 R per second at a distance of 1.5 n:eters down from the head. Using the mie-of-

- thumb of 0.1% exposure at 90 degrees from a collimated beam (see NCRP Report No. 49, Table B-2,

' page 59), the person would be exposed to a rate of 0.03 R per second. Thus, the 5 rem whole body

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li nit for dose equivalent would be exceeded in about 3 minutes, sufficient time for an alternative indication, e.g., visual inspection of the shutter, to become effective.

If you have further questions about these requests, please contact Mr. T. Hobbs at 301-975-5800, MAIL STOP 3541, NIST.

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-Sincerely,

.L. E. Pevey, Ch ef Occupational H<

h and Safety Division (Materials License Manager) enclosures CC: U. S. Nuclear Regulatory Commission ATTN: Document Control Desk

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i enclosure 3 FACILITY DESCRIPTION - VERTICAL TELETHERAPY BEAMS ROOMS B034, B035,8036 BUILDING 245 December 23,1998 Fire Safety - Smoke and heat detectors are installed, or are being installed, inside Rooms B034 and B036, the vertical beam rooms. These will cause Fire Protection Services response to the area upon signal activation at the security / fire console at a smoke-or heat producing condition. Manual fire extinguishers are located just inside the entrances to B034 and B036, as well as inside the door of the control room, B035, permitting occupants to fight small fires that pose no danger to the individual present at a small fire situation. The RFO will exercise administrative control to limit combustible materials within B034 or B036 for extraneous beam scatter, for fire control, and for other purposes.

Security - Tamper-resistant door locks are installed, or are being installed, on the doors of B034 and B036. Keys are controlled by the Responsible Facility Operator (RFO) and the Alternate RFO. A facility user would be issued a key and be responsible for observing facility security procedures during possession of the key. An interlock is being installed to signal the security console of attempts to enter the radiation room in use when the operator is not present and the console has been armed for such detection. Upon activation of the signal, the console attendant will cause rapid response by Security personnel to the area. Should the responding security person observe a true entry attempt, he or she will remain at the area until the situation stabilizes. The console operator will attempt to notify the RFO or Altemate RFO. If neither of these is avpilable, Health Physics will be notified.

Radiation Safety - Two radiation monitors are in each room, B034 and B036. One monitors the area radiation and produces an audible signal to alert persons in the room that a field greater than background exists; the alarm level is set at a rate about two (2) mrem per hour. The alarm silences at termination of the field. This monitor alarm also triggers a visible signal, a red light, inside the room and outside over the entry door. The second is a battery-powered logarithmic ratemeter just inside the entry door to the room. The meter indicates the existing level, i.e., it rises on initiation of a field and falls at the termination of the field. An alarm relay is set and latched when the level passes about two (2) mrem per hour. An interlock with the door causes the alarm relay to create an audible signal when the door is opened following an elevation of the radiation level to beyond the trigger level. The person entering the room must manually reset the audible alarm signal with a pushbutton beside the indicating meter, thus observing that an elevated level no longer exists.

Occupancy Control - The facility mer, prior to closing the room for use, will inspect the room to insure that no persons are left in the room. He r< she will activate an inspection button and close the inner lead sliding door. Upon leaving the room, he or she will insure that the entry door closes and locks. Both doors are interlocked, so once this sequence is completed, the source cannot be activated if either of these doors are opened, unless the full inspection process is repeated. If the user is to leave tla area for a period of time, he or she arms the alert mechanism by contacting the security console.

User Familiarization - Safety reviews, safety performance evaluations, and emergency responses are to be conducted annually, with topical information presentations, operational observations, written tests, and drills.

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This enclosure is a set of the pages proposed as replacements for the existing pages in the Materials License Document dated 6/19/97, i.e., with the material either deleted or added, as appropriate.

'PAGES INVOLVED

-I-1-3 I-2-4 I-3-4 II-8-2 II-8 - 11-8-4 (new) 11-9-3 11-1 0 II-l1 II-l1-5 i

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j Among the types of activities that may be authorized, the following topical list illustrates typical projects that may exist. Also listed are those buildings that would most probably be involved in a particular type of activity, although special authorizations by Health Physics could alter the locations listed.

. materials and equipment irradiations - Bldgs 235 and 245 -

e source preparations - Bldgs 220-226,235, and 245 a

' source calibrations - Bldgs 220-226,235, and 245 m

instrument calibrations - Bldgs 220-226,235, and 245 e

m sample assays - Bldgs 220-226,235, and 245 source characterizations - Bldgs 220-226,235, and 245 u

instrument and device characterizations - Bldgs 220-226,235, and 245 m

reference or counting source uses - Bldgs 101,220-226,235, and 245 m

s radiochemistry - Bldgs 220-226,235, and 245 general research and development - Bldgs 101,220-226,235, and 245 s

sources incorporated into devices or equipment - Bldgs 101, 2 20 '.26, 235, and 245 m

miscellaneous, e.g., static elimination - Bldgs 101,220-226,233, and 245 a

l 1.8 Special Authorizations We request that radioactive material use be authodzed at off-site locations subject to the a.

following provisions:

the proposal is reviewed and approved by Health Physics and, if required, by the Ionizing a

Radiation Safety Committee.

NIST is responsible for the safe use of the radioactive material, which is controlled by m

an authorized individual who possesses written operating instmetions whilc engaged in the project.

the radioactive material is an integral part of a measurement instrument or a contained a

source, such as a check or reference source.

lead-in-paint detectors may not exceed 100 millicuries of cadmium-109 or americium-241 a

as sealed sources in each device, otherwise the total quantity of radioactive material for a single authorized use may not exceed ten times the activity listed in 10CFR20, Appendix C, or, for those radionuclides not listed in Appendix C, may not exceed one microcurie of activity.

' b.

We request authority to release contaminated equipment to uncontrolled areas in i

accordance with the USNRC's April,1993 " Guidelines for decontamination of facilities and equipment prior to release for unrestricted use or termination oflicenses for byproduct, source, or special nuclear material."

j c.

We request exemption from 10 CFR Part 36, Sections 23(a), 23(c), 23(d), 27(b), 31(a),

and 67(a), in accordance with our letters ofMay 20,1998 and December 23,1998.

OP20/98 I-1 -3

_.- _. _ _. m..

' Supervisory. Health Physicist conduct radiation workplace safety observation tours at least e

quarterly 'for those workplaces that pose significant potential for radiation exposures or releases of-radioactive materials, following written plans. Results of the tours.are documented and

. corrective action needs found during the tours are transmitted to workplace supervisors in a L timely fashion.

2.9 Investigations and Reporting of Off-Normal Occurrences

- Health Physics, based on reports from Division Chiefs or. workers, or on results of monitoring or surveillance, investigates suspected off-normal occunences. The Chief, Occupational Health and Safety Division, reports these conditions to authorities and to management, as required by applicable regulations, procedures, and license conditions.

2.10 Records Health Physics maintains documentation on the results ofrequired monitoring and surveillance, the results of approved proposal reviews, off-normal occurrence investigations, and other

. radiological. safety program information, sufficient to demonstrate the adequacy of the radiological safety program. The Ionizing Radiation Safety Committee documents and retains information on audits and provides reports to management as required. Retention times for

' documents are as required by regulations or for at least two years.

' l 2.11 Fire Protection A Fire Protection S cie::: gGroup in the Facilities Services Division provides a trained fire

'and emergency response organization. Any proposed-laboratory or facility construction or modification must be reviewed by and have the approval of such management interests as representatives of the h::d ofi: S:fety Of". :, i: Ch::f cf $ Fire Prc::: tion Services,the Chiefof the OccupationalHealth and Safety Division and the Chicf af the Plant Division, and the Fire Protection Specialist or his designated representative. Members of the staff of the Fire Protection Sercie: gGroup are trained to the equivalent of Fire Fighter III level. Maintenance of fire fighting equipment is conducted according to written procedures. Extensive pre-fire plans i

I exist, with information on locations of radioactive materials, flammable materials, and other i

hazardous materials, and includes fire fighting protocols for those areas. The plans include

locations of water supplies, storage areas, and other appropriate information. The Fire Protection L

hviees Group maintains extensive documentation on maintenance and deployment of equipment, pre-fire planning, facility characteristics, training, results of actual occurrences, etc.

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2.

The periodic leak test required by this section does not apply to sealed sources that are stored and not being used. Prior to any use or transfer to another person, the source shall

'be leak tested within 6 months prior to the date of use or transfer.

i B. -

. The' test shall be capable of detecting the presence of 0.005_ microcuries of radioactive

material on the test sample. The sample shall be taken from the' sealed source or appropriate accessible surfaces of the container or from the device where the sealed source is mounted or stored in which one might expect contamination to accumulate. Records ofleak test results shall be kept in units of micrairies and maintained for inspection by the USNRC.

If the test reveals the following:

1.

The presence of 0.005 microcuries or more of removable contamination from the sealed i

sources other than described below, or-i 2.

H e pa nne: cf 0.05 micrceu-in c: m c x cf.....cvab!: contamina:icn frc= Se tekiespy :;=bd zu=:, c

32. An indication that the i ndb:: ' sealed source which is stored in the water pool for shielding purposes is leaking, then NIST shall immediately withdraw the-sealed ~ source from use and shall cause it to be

' decontaminated and repaired by.a person appropriately licensed to make such repairs or.to be disposed ofin accordance with USNRC regulations.

Within'5 days after determining that any source has leaked, NIST shall file a report with the Division of Fuel Cycle Safety and Safeguards, USNRC, Washington, D. C. 20555, describing the source, test results, extent of contamination, apparent or suspected cause of source failure, and L

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corrective action taken. A copy of the report shall be sent to the Administrator of the NRC j

Regional Office for Region I.

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8.4 Maps, Buildings, and Site Information Attachment I contains a NIST site plan and a topographical representation, building locations on site, and floor phns for buildings. The site exhibits a gently rolling topography and contains both open and wooded areas. Buildings include a central complex of the main administration 1

building'and several general purpose buildings designed to contain laboratories that accommodate customary scientific research and development functions, buildings that house the support L

functions ranging from grounds management, heating and air conditioning, and the like, to procurement, and special purpose laboratory buildings that are dedicated to specific research and development functions. This last category includes the Reactor and the Radiation Physics Buildings, where the majority of the _ work involving radiation and radioactive materials is conducted.

8.5 License History '

j Table. II.8-2 shows a chronologicd ordering of licensing history at NIST for radioactive 1

materials. This history tracks licenses to the most recent renewal. In some cases, e.g., for 08-00566-05, the byproduct material license, a full history would extend to more than thirty years with many amendments and renewals. In 1980 a Materials License Manager was named to bear j

responsibility for Feensing other than for the NIST Reactor. In 1985, five major licenses were j

consolidated into single SNM-362 license.

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i TABLE II.8-2 NIST MATERIALS LICENSING

SUMMARY

YEAR LICENSE L ACTION (identifier) 1997-SNM-362 renewal 1990 -

SNM-362 amendments 1 - 4 1994 ll 1985 -

SNM-362 amendments 1 - 4 1990 1

1985' 08-00566-05, 08-00566-10, 08-consolidation, incorporation into 0056612, SMB-405, SNM-362 License No. SNM-362 t

1983 08-00566-05 Class I irradiator request l

1982 all-Ionizing Radiation Safety I

Committee 08-00566-05 change in limits (byproducts) l L.

all personal dosimetry technique I'

1981 SNM-362 filter process (SNM)

SNM-362 change in limits

'08-00566-10 renewal (teletherapy) 1980 SMB-405 license manager named (source) l 1979 SNM-362 renewal l

08-00566-05 change in limits 1978 SMB-405 renewal 08-00566-12 renewal (irradiator) 1977 08-00566-05 renewal i--

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05/20/98 11-8 3 I

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l 8.6 Changes in Procedures, Facilities, and Equipment NIST emp;oyees and other individuals working on the NIST site are responsible for obtaining authorizations from Health Physics for radiation source acquisitions, for any l

modifications in radiation source use that might affect radiological safety, or for disposition of l

radiation sources. Division Chiefs are responsible for ensuring that staff members comply I

with radiological safety rules and that staff members are aware of radiological safety procedures. The Chief, Occupational Health and Safety Division, is charged with managing the radiological safety program and with representing the National Institute of Standards and Technology in all matters relating to materials licensing. The Chief, Health Physics, is charged with administering the radiation safety program at NIST, including maintaining 1

documentation to demonstrate the adequacy of the radiological safety program. The Ionizing Radiation Safety Committee is responsible for reviewmg major radiation facility proposals l

and significant proposals for use of radiation, including modifications to existing facilities, and for assuring the performance quality of operations that provide radiological safety assurance.

)

8.7 Examples of Operations That Might Be Conducted As an example of the miscellany of types of work done at NIST, consider NCRP Report No. 58, if handbook of radioactivity measurements procedures, second edition. Of the tifteen

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consultants listed in the preface to the first edition, ten were from one working group within NIST (then NBS), as well as the chairman of the scientific committee. The preface to the second edition names twenty-four persons who made contributions to that edition. Of those, fifteen were NIST (then NBS) personnel, including Health Physics staff members. The wide variety of operational activities and of radionuclides described in the publication, essentially j

the product of only onr of the groups at NIST, illustrates the extremely broad scope of work done at NIST.

For the specific nuclides listed in Table I.1-1, the following examples of research, development, and other activities will suggest the variety of operations involving radioactive materials at NIST. Uranium at any enrichment, frora depleted through 99.9% "U,233U,any 2

nuclide of plutonium, and thorium, might be used in metallurgical research, for beam transmission studies, in neutron beam research, for check sources, or as beam filters. Sealed 238 sources of Pu are used as thermal sources. PuBe, Puli, and other sealed Pu-X sources are used in neutron research and are calibrated for customers. Sealed sources of"Co, '37Cs, 2 n>pg (sometimes as PoBe),24'Am,252Cf, or "Sr might be used in research requiring photon, neutron, or beta radiations, for instrument calibratims, in neutron physics research, medical device (implant seeds, eye irradiation applicators, etc.) calibrations and research, or basic nuclear chemistry and physics research such ts half-life studies. Miscellaneous byproduct materials, including materials and containers irradiated in the NIST Reactor and brought out of the Reactor licensed area, might be used i.s check sources, m laboratory intercomparison tests and studies, for light sources, for basic radiochemistry and nuclear physics research, for sample preparations for authorized customers, or in research for medical or other specific laboratory types.

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05'20/98 n-8-4 l

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Wastes with short half-lives are treated by decay-in-storage. Disposal of decay-in-storage waste, as provided in 10CFR20.2001(a)(2), is in accord with conditions given in 10CFR35.92.

9.5 Chemical Systems Nonradioactive chemical operations are the responsibility of the Environmental Compliance 4

Group of the Occupational Health and Safety Division. Any facility or operation involving toxic materials is reviewed to insure compliance with appropriate regulations.

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9.6 Fire Protection The buildings andfacilities at NIST were constructed in accordance with applicable 05/20/97 1193

.- ~.... - -.

regulationsfor Federalfacilities in effect at the time of construction and are maintained l

under thefire protection auspices of the Fire Protection Group of the Facilities Services l

Division. The coverage by this trainedfire and emergency response group includes around-l the-clockfire, emergency medical, and hazardous material response capabilities.

l The Fire Protection Group reviewsfacility plans, including locations offire hydrants, sprinkler systems layouts, access pathways, and other layout information related to fire l

fighting. The plans are maintained in the offices and workspace of the Fire Protection l

Group work area. Training offirefighters is according to the State ofMaryland and local l

County having authorization, in conjunction with NFPA. Materials and equipment available to the Fire Protection Group include appropriate vehicularfirefighting apparatus, l

water supply systems, automatic sprinkler systems, portablefire extinguishers, protective clothing, and tools used in fighting a variety offires, e.g., structural, vehicular, etc.

Maintenance and deployment offirefighting equipment is in accordance with NFPA codes.

Extensive pre-fire plans have been developed incorporating information on location of radioactive materials, flammable substances, and ha:ardous materials storage areas. The plans includefirefightingprotocolsfor those areas, with locations of water supplies, automaticfirefighting response mechanisms that might be employed, and other pertinent information. The Fire Protection Group maintains extensive documentation on deployment and maintenance of equipment, pre-fire planning, facilite characteristics, training of persor.nel, results of actual occurrences, etc. Portablefire extinguishers are deployed accordmg to NFPA 10; these are commonly dry chemical and CO, types. In addition, portable extinguishers are commonly located in each laboratory and building hallways.

Portablefire extinguisher agency is determined by thefire load in the area of work.

I Building entrances and stairwells have standpipe connections; fire hydrants are located at j

various positions on the exterior of buildings. The loading dock of Building 245 has a sprinkler system.

Laboratories are monitored with automaticfire alarm devices activated by heat or smoke, or both. Thefire alarm device type is determined by thefire ha:ard within the work area covered. Manualfire alarm boxes (pull stations) are located according to the NFPA code.

Upon activation of any alarm, the signalis received at two locations: in the Fire Station in Bldg. 303 and in the Security Office in Bldg.101.

l l

l f

1 I

i 05/20/97

!!-9-3 l

. __ ~_

1 radiation safety program.

10.1.4 Division Chiefs Each Division Chief managing radiation work is responsible for the following:

Ensuring that staff members comply with radiation safety rules in implementing the a.

NIST radiation safety policy; b.

Ensuring that staff members are aware of radiation safety procedures and receive training as required; e

c.

Reporting potential items of substantial safety hazard as defined in 10CFR21.3(k) to the Chief, Health Physics, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of occurrence or discovery, except for items relating to the Reactor license which are to be handled according to that license; and d.

Reporting significant radiation safety matters to his or her supervisor.

10.1.5 Staff NIST employees and other individuals working on the NIST site are responsible for the following:

a.

Observing approved radiation safety rules; i

b.

Consulting with Health Physics early in the planning of operations that might involve radiation sources; Obtaining authorization from Health Physics for radiation source acquisitions, for any c.

modifications in radiation source use that might affect radiation safety, or for disposition of radiation sources; d.

Notifying Health Physics of any occupational radiation exposure from work at facilities other than NIST; Immediately informing Health Physics upon discovery ofloss or theft of any e.

radioactive materials; f.

Immediately informing their supervisors and Health Physics of accidents involving radiation or radiation sources; and a

g.

Informing their supervisors of aefects that could create a substantial safety hazard.

10.2 Orgr.niza:ica The !cnizing Radiatica Safety Commi :ce membe=' and a!:cmates' m mes and pertinen:

=mnes arc listed belev. The aize :.nd ecmpesi:icn of the Committee are subjec: :c change a:

the discretion of the Deputy Direc:cr.

(Chair) Dr Chris E. Kuya::, Executive Dir;c:cr, Visiting Commit ce, PhD, Physics,1960, Nebada Un.v.; experience in ;!ce::cn, phc:en, and partic!: physies-(Vie: Chair) Dr. Ha:rj L. Rock, Deputy Direc:ct, Materials Seier.cc and Engineering Labora:crj, PhD, Nuclear Analytical Chemistrj,1969, Texas A & M Univ.; experience in nac!::: chemistrj.

Dr. Ber: M Councy, Chief, Icnizing Radiation Divisien, PhD,1970, Radicchemistrj, Univ i

Occrgia, applied mdiation science.

Dr. Heather Chen Mayer, Physicist, Analytica! Chemistrj Dh bion, PhD (Physics) 1989, L

CUNY; neutron physi =.

1 05/20'97 Il-10-2 I

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t 10.2 Organization l

Members and alternates of the Ionizing Radiation Safety Committee are named by the Deputy Director ofNIST. The current list, with organi:ational titles, is:

l (Chair) Dr. Bert M. Coursey, Director, Ionizing Radiation Division (IRD), Physics Laboratory (PL)

(Vice Chair) Dr. Richard M. Lindstrom, Research Chemist, Nuclear Methods Group, t

l ACD, CSTL I

i l

l Dr. James M. Adams, Research Physicist, Neutron Interactions and Dosimetry Group, IRD,PL Mr. Jeffrey T. Cessna, Research Chemist, Radioactivity Group, IRD, PL Dr. Heather H. Chen-Mayer, Research Chemist, Nuclear Methods Group, Analytical Chemistry Division (ACD), Chemical Science and Technology Laboratory (CSTL)

Mr. Keith H. Eggert, Safety Engineer, Environmental Compliance Group, 1

Occupational Health & Safety Division (OHSD), Office of the Director ofAdministration (Admin)

Mr. Douglas M. Eagleson, Supervisory Health Physicist, Health Physics Group, OHSD, Admin Mr. Thomas G. Hobbs, Chief, Health Physics Group, OHSD, Admin Dr. Santos Mayo, Physicist, Semiconductor Electronics Division, Electronics and Electrical Engineering Laboratory (EEEL)

Mr. J. Franklin Mayo-Wells, StaffAssistantfor Technical Coordination / Operations, t

EEEL Mr. Lyman E. Pevey, Chief, OHSD, Admin Dr. Henry J. Prask, Physicist, Neutron Scattering Group, NIST Centerfor Neutron l

Research (NCNR), Materials Science and Engineering Laboratory (MSEL)

Dr. J. Michael Rowe, Director, NCNR, MSEL

\\

Dr. Francis J. Schima, Research Physicist, Radioactivity Group, IRD, PL i

Dr. Christopher G. Soares, Research Physicist, Radiation Interactions and Dosimetry Group, IRD, PL Dr. David S. Simons, Leader, Analytical Microscopy Group, Surface and Microanalysis Science Division (SMSD), CSTL I

Mr. Lester A. Slaback, Jr., Supervisory Health Physicist, Health Physics Group, OHSD, Admin l

Ms. Cynthia J. Zeissler, PhysicalScientist, Analytical Microscopy Group, SMSD, CSTL i

[

11.6 Surface Contamination Table II.11-1, Controls and Action levels, and Table II.11-2, Administrative Action Levels and L

L Actions, list controlling levels for surface contamination. Measurements'for surface contamination

-checking and protective measures are described in sections II-l1.1,11-11.4, and 11-11.7 of this manual.

L Hand _ and shoe-monitoring may be performed with conveniently placed equipment; L

resuspension ' factors for transforming surface contamination levels to airborne activity

[

concentrations are applied as described in section M42-4 II-11.5 of this manual.

L

. I1.7 Shipping and Receivmg j

L All radioactive materials received at NIST and all radioactive materials shipped from NIST are controlled by Health Physics. Usually, incoming packages are brought to the Health Physics receiving area in Building 245, unless alternate provisions are made with the ultimate recipient.

i-In either case, surveys for compliance with transport regulations are made within time limits j

specified by ;he regulations. Health Physics and the recipient then survey the package and j

contents and determine if the shipment is acceptable for incorporation into the project for which l

the source is intended. Usually, outgoing packages are held in the NIST shipping area in Building

)

L 301 until Health Physics or a designated representative checks the package for compliance with transport regulations.

Type B shipments are made in accord with the provisions of the quality assurance program as detailed in a separately submitted document.

If an incoming shipment shows contamination at any level of packaging, the package is held in' the Health Physics'or other designated storage area until a decision is made, jointly between g

Health Physics and the recipient, on returning the source, decontaminating the source, disposing of the materials, or establishing proper controls for safe use of the source.

I1.8 Posting and Labeling Table II.11-1 shows control mechanisms and action levels under which radioactivity operations are permitted. The contamination limits shown represent a departure from customary practice in that specific nuclide limits are provided for beta-emitting nuclides when the identity of the j

nuclide is known. As an ALARA precaution, Health Physics requests decontamination of areas 1

in which any detectable contamination above normal background levels are found. Health Physics review may result in'a determination that actions other than described in this table should be implemented. Such alternate actions are documented by Health Physics l

11.9 Surveys Health Physics performs weekly routine surveys of a laboratory in which unsealed radioactive

- material is utilized when the initial proposal or subsequent evaluation of the work environment demonstrates that levels could exceed the levels at which posting is required, as shown in Table 11.11-1. As-specified by Health Physics, the surveys could include smear tests of surfaces, radiation level tests, radiation quality tests, air activity contamination tests, or combinations of these, and other radiation safety assurance procedures. For special situations, such as p

maintenance, similar surveys, time and motion studies, or practice sessions on mock 05/20/98 !!413 4

l.

r -

t

)

i contamination might be expected to accumulate. Sources will be immediately withdrawn from use and action taken to repair or dispose of the source, and appropriate actions taken to notify l the NRC, if the following limits are exceeded for removable contamination:

s any indication ofleakage from the irradiator scaled source in the water shielding pool.

e 0.05 =ierceu-ic: cr =cr: frc= a ::!:Sc=pytjp :::!:d sc=::.

m 0.005 microcuries or more from any other sealed source.

-11.12 Respiratory Protection

. Health Physics may issue dust stop or similar particulate breathing masks far dusty work environments. At the conclusion of thejob, Health Physics retrieves the masks and prepares them

- for reuse..

I1.13 Protective Clothing Health Physics maintains a nominal supply of various protective clothing items, including gloves, shoe covers, coveralls, head covers, etc. These are freely available as needed for issue to laboratory workers using dispersable radioactive materials. For situations requiring protective clothing beyond the normal issue quantities, the requesting work unit may be asked to replenish the supply.

-11.14 Reports and Records j

The Chief, Occupational Health and Safety Division, documents management and authonty notifications resulting from reports from Health Physics on off-normal investigations. Health Physics' maintains documentation on routine and special radiological surveys, personnel monitoring, licensing ~ interactions with NRC, instrument calibrations, ALARA reviews and findings, employee training and familiarization, environmental monitoring, and source control.

i The Chairperson of the Ionizing Radiation Safety Committee maintains records of meetings of-

-_the_ Committee, Committee audits,' and special reviews and investigations by the Committee.

' Normal retention time for these records and documents is two years unless otherwise specified by regulations.

11.15 Administrative Control Levels Table 11.11-2 describes the administrative action levels and the actions taken at those levels to control radiation and radioactive materials in specific situations and under specific conditions.

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