ML20148G556
| ML20148G556 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 05/26/1997 |
| From: | Reece W TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 97-0118, 97-118, NUDOCS 9706060011 | |
| Download: ML20148G556 (4) | |
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l TEX AS E NGIN E E RIN G EXPElllM ENT STATION
, TEXAS A&M UNIVERSITY l COLLEGE STATION, TEXAS 77843-3575
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! May 26, 1997 NUCLEAR SCIENCE CENTER l 409'845-7551 Nuclear Regulatory Commission 97-0118 >
Document Control Desk Washington, D.C. 20555-0001
Subject:
Request for Amendment to License R-83 *
Reference:
Reactor Facility License R-83 Amendment 13, Docket 50-128 .
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Dear Sir:
In a phone conversation between Ted Michaels, Senior Project Manager, and Sean O' Kelly, Nuclear Science Center Assistant l Director, on May 23, 1997 it was determined that changes are j required in the wording of the original license amendment request i dated April.15, 1997. It is respectfully requested that the j Nuclear Science Center (NSC) Facility License R-83 be amended as I follows: l To support'the NSC's wide range of research activities, the l facility license condition II.B.3 should be changed to read Pursuant to the Act and 10 CFR, Chapter I, Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material," to receive, posses, and use in amounts as j required any byproduct material without restriction to I chemical or physical form in connection with operation of the reactor that has a definite research and development purpose and any byproduct material generated by the licensed /
activities, but not to separate such byproduct material j except for byproduct material produced in reactor I experiments In addition to the above amendment, it is requested that an d
additional condition II.B.7 be added as follows:
Pursuant to the Act and 10 CFR, Chapter I, Part 30, " Rules l of General Applicability to Domestic Licensing of Byproduct i
Material" to posses and store for decay such byproduct materials as are within the facility boundary at the time of this amendment.
N b h PDRI28 $ ,bh 1 RESEARCH AND DEVELOPMENT FOR MANKIND l
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... 97'0118 ,
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To define the decay in storage procedures it is requested that !
-10CFR 35.92 be added to the list of applicable regulations in !
II.C of the facility license. j Attached to this letter is the new fourth revision of the NSC l Operator Requalification Program that was changed in a letter to i the NRC dated April 16, 1997. This revision incorporates comments [
and suggestions made by Ted Michaels to the NSC Management. l Finally, a' draft NSC Health Physics procedure is. attached. This ,
procedure formalizes the quarterly and semiannual sealed source !
leak checks. This was identified as a program weakness during !
the NRC inspection in March. This procedure will insure that routine leak checks will continue to be performed as required in i NRC Regulatory Guide 10.5 and 10.7. This procedure will be }
-submitted for approval at a Reactor Safety Board meeting this ,
month. j Please contact Sean O' Kelly or me at 409-845-7551 if you need any j additional information. Your attention to this matter is '
appreciated.
Resfect f $y, i !
Dr. arr a . Reece !
Director 'j u
WDR/sjm
Attachment:
NSC Operator Requalification Program-4th Revision cc: Ellis W. Herschoff, NRC RGN-IV
-Theodore S. Michaels, NRR/DRPM/PDND B. Don Russell, TEES Larry A. Krisanits, NSC David Hearnesberger, NSC
-12110/ Central. File
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Nuclear Science Center Senior Reactor Operator and Reactor Operator Requalification Program Facility License R-83 Docket 50-128 Texas A&M University System Texas Engineering Experiment Station NSC Director: * . 4C '
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Revision 4 April 1997
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. Tcxac A&M Univaraity Syatem/ Texas Engineering Experiment Stntion !
l Nuclear Science Center Requalification Program !
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April 1997 Rev. 4 l !
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l.0 PURPOSE ,
! To insure that all operating personnel maintain proficiency l at a level equal to or greater than that required for ;
l initial licensing.
2.0 CLASSROOM TRAINING !
i i 2.1 Lectures !
i Nuclear Science Center Operations (NSC) memos are distributed on a timely basis to keep operations personnel aware of facility changes. These changes are also covered in periodic documented operations staff meetings. However, to provide assurance that all licensed personnel are !
current in their understanding of the facility a lecture i program will be presented to' train the licensee and inform j him of modifications and changes. Basic theory and other j pertinent items will also be covered. One or more lectures :
will be scheduled within a four month interval to cover a :
topic selected from the list below. The lecture sequence l over all topics will take two years to complete and will i then be repeated. Self-study or individual tutoring may substitute for each missed lecture, however, examinations j given after each lecture in 2.2 must be taken or an j L alternate examination taken within a month after the ;
lecture. Lectures on the Emergency Plan and Security Plan !
will be given annually.
f 2.1.1 Theory and Principles of Operation 2.1.2 Reactor Regulations ,
- a. Applicable portions of 10CFR !
- b. Technical Specifications .
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- c. Regulatory Guides
, d. Standard Operating Procedures ;
! e. Experiment Authorizations l 2.1.3 Reactor Design ,
i a. Facility Operating Chara$teristics
- b. Instrumentation and Control Systems
- c. Facility Protection and Engineered Safety Systems Page 2 of 4
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- Texas A&M Univercity System /Taxas Engineering Experiment Station Nuclear Science Center Requalification Program ;
[pril1997 Rev. 4 j If a licensee has not actively performed the functions of an operator or senior operator for a period of more than four months, he shall satisfactorily demonstrate his ;
competence before resuming his duties. He shall do this by i satisfactorily completing the performance evaluation form l l discussed in Section 3.2 of this program. He will also be .
l briefed of any changes to the facility or procedures. When .
I his competence has been satisfactorily demonstrated, the :
Director will so certify to the Commission. l l 5.0 RECORDS i I l l Records will be maintained to document the performance of f
! each licensed operator and senior reactor operator i participating in the program. The record will contain i
, copies of the written examinations administered, answers l given and results of-the console manipulation evaluations.
Any additional training and testing required for individuals exhibiting deficiencies will also be documented. I 6.0 EXEMPTIONS l
The Director or his designee will be responsible for evaluating the written examinations. The individual l preparing a particular examination is exempt from that l examination, except that the same individual shall not prepare the examination for two consecutive years. This 1 must be the qualified individual who has presented lectures and prepared the questions for that examination. No exemptions to the physical manipulation requirements will
! be granted to any licensee.
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. Se'aled Source Leak Check A. Introduction I As all sealed sources possess the potential for leakage and contamination, the NSC Health Physics Staff is to '
assess and maintain acceptable levels of surface contamination and leakage from sealed sources at the l NSC Regulatory Guide 10.5, Regulatory Guide 10.7, along '
with State regulations (TRCR 11.7). These regulations l specify tests or checks to be performed on all sealed sources above specified activities.
B. Purpose A semi-annual or quarterly leakage check shall be performed on all sealed sources. A semi-annual gamma / beta and neutron source survey, not to exceed 6 months, and a quarterly alpha source survey, not to exceed 3 months, is to be performed on all sealed sources above specified limits (Reg Guide 10.7 and TRCR 11.7) for any signs of leakage and contamination. A leak test must also be performed in the absence of a certificate for a leak test from the transferor before use.
C. Procedure All sealed sources greater than:
(i) beta / gamma emitters 100 uCi (ii) alpha / neutron emmiters 10 uCi j (iii) plated alpha, except Cf-252 0.1 uCi (iv) nickel-65 foil sources 100 uCi Some sources may be exempt from leak testing if they meet the following requirements: )
(i) any hydrogen-3 (Tritium) sources; (ii) sources of half-lives less than 30 days; ;
(iii) sealed sources in gaseous form; l (iv) less than testing limits stated aabove. j i
Stored sources not in use: 1 Each sealed source and fission detector shall be tested prior to use or transfer to another license unless tested within the previous six months.
Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prier to being placed into use. ;
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,... Startup sources and fission detectors:
f Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.
(1) Obtain a Sealed Source Leak Check Form, NSC Form 817.
(2) Complete a listing of the sources to be tested at that time.
(3) View the source and container or mounting device for any physical signs of leakage.
(4) Obtain a 100 cm2 smear from the surface of the source or from the containing or mounting device and from any other surface that might be suspected to be radioactively contaminated. Caution and i care should be exercised with thin window or plated sources to avoid damaging the source.
(5) Count the smears and convert the net cpm into uCi.
(6) Report any contamination above 0.005 uCi (185 Bq) i to the Health Physics Supervisor, mark the source ,
as contaminated, and remove the use or service. ,
(7) The Director of the NSC shall submit a written '
report in the annual report if any source is found to have leakage greater than 0.005 uCi. ,