ML19343D268
| ML19343D268 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 02/05/1981 |
| From: | Kosla B NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8105040092 | |
| Download: ML19343D268 (5) | |
Text
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, NUCLEAR REGULATORY COMMISSION.. _.
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UNITED STATES B
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FEB 5 1981 Docket No.70-152 S24-142 -
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] v.s.Pg 2 I EU MEMORANDUM FOR:
W. T. Crow, Section Leader
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klgg/Sg7 Uraniin Process Licensing.Section Uranita Fuel Licensing Branch 4
FR(M:
Bernice Kosla f,x Uranium Process Licensing Section.
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Uranium Fuel Licensing Branch
SUBJECT:
TRIP REPORT Purvose To visit the Fast Breeder Blanket Facility (FBBF) at Purdue University, to observe an inspection by Region III inspector, Mr. C. Peck, and to discuss the application for renewal of Special Nuclear Material License No.142, dated December 28, 1978 with FBBF representatives.
Place & Date FBBF, Physics Building; Radiation Safety Office, Pharmacy Building; and Reactor, Duncan Annex; at Purdue University, West Lafayette, Indiana 47907.
January.12-14, 1981.
Discussion On Monday afternoon, January 12, 1981 Charles Peck and I were welcomed by Dr. R. R. Landolt, Assistant Radiological Control Officer. Mr. Peck comenced the inspection with a discussion of areas of interest fran a previous inspection of material covered under Broad Scope Byproduct Materials License 13-02812-04. This was followed by a review of monitoring recortis kept by Dr. Landolt.
Mr. Peck and I toured the FBBF, in the company of Dr. F. M. Clikeman, FBBF Project Director, who presented a detailed description of the development and instc11ation of the facility. He indicated the safety instrumentation and described the safety procedures specifically used in each area. We entered the concrete block shielded area which houses the FBBF after proceeding through the standarti shutdown. process. While viewing the suberitical assembly, Dr. Clikeman discussed the configuration of the rod assembly calling attention to size differences and color coding of the rods.
l 8105040092
7 FEB 5 1981...
On Tuesday morning, Januar,y.13. Mr. Peck and I met with Drs. Clikeman, P. L. Ziemer, Radiological Control Officer, and G. Rorn, Assistant j
Radiological Safety Officer (responsible for license applications) to discuss Purdue's application for license renewal. The application currently under review is not wholly applicable to the present situation, as it contains material about a proposed facility which is now a reality. It was agreed that a new application reflecting the existing facility and current trends in radiation safety should be submitted. Specific areas to be covered by the revised application were discussed, as shown in the '
enclosed outline. Since the current application already contains much of the information required for the revised renewal application, it was agreed that early March 1981 would be a reasonable target date for resubmittal.
The balance of the time at Purdue was spent touring the reactor in Duncan Annex, and observing Mr. Peck's inspection and the subsequent exit interview.
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- sh_J Bernice Kosla Urania Process Licensing Section Uranim Fuel Licensing Branch
Enclosure:
Outline l
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An application should be written as a dedication to the letter and intent of the regulation, and as such, the application will become a con-dition of the license It should also be a measureable entity which can be evaluated by an investigator.
For demonstration purposes, or expan-sion of a point, etc., a second part should accompany the application which will not be included as a condition of the license.
Information which shall,be provided:
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A.
Compiete identification of the applicant as per 10 CFR 70.22.
Include:
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The full name of the institution, address and state where p o,%g%/Sg 1.
r organized or incorporated.
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2.
Listing of principal officers, with name, title, address Q and citizenship.
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Information known to the applicant concerning the control, Mi,-
if any, exercised over the applicant by any alien, foreign corporation, or foreign government.
B.
Be specific *, provide:
1.
Existing licensa number and its renewal date.
2.
Location (including building name.and number) of any facility where SNM will be used and/or stored. Clarifying maps should be included.
3.
Listing of SNM, identifying each by isotopic; chemii:a1 or physical fann and mass in grams.
a.
sealed sources should be further identified by the manufacturers name and model number
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b.
possession limits requested should cover the total anticipated inventory including stored materials.
' 4.' Description of activitie's which involve the licensed material in terms of use and procedures employed.
C.
Administration & Organ'ization: Description in this section are best served if the positioe' requirements are described and not the quali-fications of the individual presently filling the position.
1.
Personnel requirements, list:
a.
key positions 1.
minimal' technical qualification required for each position 2.
include safety ielated responsibilities 3.
indicate the line of authority for reporting purposes for RSO and RSC O
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radiation (be its compositon, indicate the responsibil'-
ntrol comittee b.
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descri ities and qualifications required for each position c.
radiation safety officer and/or criticality safety specialist 1.
describe the education and experience requirements i
of the position
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list the position, responsibilicies and duties ",,crp,uj.
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Procedures - (conduct fissile material processing only in ace'ordance Y
with properly issued procedures).
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indicate review policy
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describe control:
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for adopting and issuing operation, maintisce and test procedures 2.
to change safety related procedures 3.
to ensure that prior to the start of any new activity involving nuclear materials approved procedures are available D.
Audits and/or Inspections State the frequency of on site inspections for radiation safety.
E.
Radiation Safety - Policies of radiation safety sh*ould reflect the spirit of ALARA.
1.
Personnel monitoring, state:
a.
type of equipment used b.
frequency of reading c.
frequency of review of radiation exposure 2.
Contamination detection instruments should be identified by type and numbers employed. -
a.
include the sensitivity range and alam set.-point where applicable b.
what is the frequency of calibration and whi.c standards are used Surface survey - h'ndards of tolerance for both fixed and 3.
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a.
what are sta j
removable contamination b.
state action level to cocuense decontamination c.
what is the maximum time allowed before decontamination is actually started 4.
Personal survey - re: clothing and skin a.
what are the stantards and action procedures 5.
, Leak Testing - see Annex A 6.
Waste - indicate the type of waste generated during use of licensed material.
a.
air contamination 1.
what is monitorinq plan and location of instruments 2.
state policy for oispersal., describe stacks and/or l
filters l
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describe bioassory program
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b.
liq'uid waste - how di::pased 1.. sewage (10 CFR 20.303) s state type and frequency 2.
stored, describe vessel of monitoring and leak testing i
c.
solid 1.
state remeval frequency 2.
method of disposal
% b A p-#^"#/N' F.. Radiation Safety. Training Trainihg is an integral part of radiation safety and is required for new empicyees and/or. students. State-the general topics which will be presented, as well as method employed for evaluation.
In addition, the training policy sho61d. include provisions for refresher courses to be conducted at some stated frequency.
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G.
Criticality - Describe quantity, disburser nt and safeguards to ensure an adequate margin of safety 1.
Indicate alarm instruments, location and frequency of reliability testing.
2.
Indicate emergency procedure in regard to criticality.
3.
If exemption to 10 CFR 70.24 is appropriate - please' state request and justification.
H.
Decontamination - See Annex C 4
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