ML20058M974
| ML20058M974 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 08/09/1990 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058M966 | List: |
| References | |
| R-109-A-003, R-109-A-3, NUDOCS 9008130147 | |
| Download: ML20058M974 (6) | |
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UNITED $TATEs NUCLEAR REGULATORY COMMISSION e-WASHINGT ON, D. C. 20$$$
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-BRIGHAM YOUNG UNIVER$1TY DOCKET NO.-50-262 AMENDHEllT TO FACILITY llCENSE Amendment No. 3 License No. R-109 1.
1he Nuclear Regulatory Concission (the Connission) has found that:
TheapplicationforamendmenttoFacility)LicenseNo.R-109 A.
filed by Brigham Young University (the licensee, dated June 28, 1950, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's regulations es set forth in 10 CFR Chapter It 1
B.
The facility will be maintained in conforn.ity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized by this anwndment con be conducted without endangering the health
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and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Cosnission's regulations and all applicable requirenwnts have been satisfied; and F.
Prior notice of this amendo,ent was not required by 10 CFR 2.105(a)(4) and publication of notice for this amendment is not required by 10CFR2.106(a)(2),
i 9008130147 900809 DR ADOCK 0500 2
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license an.endment, follows: graph 2.C.T.-of License No. R-109 is hereby asended to read as and para 2.
Technical Specifications The Technical Specifications contained in Appendix A, es revised through Amendn.ent No. 3, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective' as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III,
!Y, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: August 9, 1990 1
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_ ENCLOSURE T0 f.! CENSE AMENDftENT NO. 3
' L EACILITY LICENSE NO. R-109 4;
t DOCKET NO. h.262' Replace the following p ges of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 4
4 5
5 9
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-Comittee @$C) to conduct sessaremente pursuant go decommissi: sing activities.
- c S.2.- Reactor bcilityt' The reactor is located in the Nuclear Laboratory.?
3;1 This-is'a dedicated facility located on the southwest portion of: the
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. Seigham Towns University campus. The buildlag is of concrete and masonry
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cometruction.. 93.secompanied, access is limited to the Radiation Safety _ '
i Mficer and _ the Reactor p cility Chief or University polise. Any other j
access shall be under the supervision of the R80 or the Facility Chief.
L The dcore shall renais locked and the alara engaged whenever there are ra i
l-escapante in the building.
5.3.
.taticipated changes la configuration: Under the possession Only License the major anticipated configuration change may be the removal of 4
the piuttoiva/ beryllium source. Until the source is removed, the sbividia6. uter shall be maintained at a level no less than one foot below t%e top edgi of the shielding task.
6.
Administrative Controle 6.1.
0,genisatiint (see figure 1) 6.1.1<. president. The president is the Chief Administrative Officer responntble for the University. As such he shall have ultiaste responsibility tir the operation and man.teensat of the nuclear reacWr.
i 6.1.2. Associate Aozninistrative Vice President (AAVP). The AAVP l
reports directly to the president and shall have direct responsibility for the reactor.
6.1.3.
Radiation $sfety' Officer. The Radiation Safety Officer (150) shall be appointed by the AAVP
-with the advice of l
the Chairman of the ksdietion IWty Committee. We shall be responsible to the AAVP for the by-to-day administration of the radiation' safety program and-serves as the Secretary of the Radiation Safety Ccesittee. - Re propsres the University's Radiation. Safety 1
Manual. The Radiation Safety Officer shall also be responsible for preparing, for the signatare ef the Chairman of the~ Radiation Safety Committee.. reports of all reportable occurrences to the appropriate regulatory agency and for ensuring that appropriate follow up action is:taken.
6.1.4.
Training Requirements. At least one member of the Radiation Safety cosaittee-shall have a pbD in physics. The-Radiation Safety Officer shall have a minima of one year asperience in working with radiation and radiation safety.
6.1.5.
Radiation Safety Committee. The members of this committee shall be appointed by the AAVP
. This ceamittee l
shall be composed of four members, to includes the Radiation Safety Officer, a f aculty seaber from the physics Department. a f aculty member from the College of Biological Science, and a member from the 4
Amendment No. 3
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,1 Campus Safety Office. - The Radiation Safety' Committee.(RSC) shall f
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meet quarterly.' S of 4 members shall constitute a quorum. Thet ainstes aball be: recorded and sent to the couaittre members. The
- sinstes shall be. read and approved-st.'the start of each meeting. The l/
p RSC reporte directly to the AAVP g
Tbh Radiation Safety Couaittee shall beve both review and audit:
I functions;with regard to the Reactor Facility. l The RSC-shall' advise the. Reactor Administrator as well as. level one management on all t
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astters pertaining to reactor facility safety.
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6.1.5.1.
Any changes in equipment, procedures, facilities c
or license: = including these technical specifications shall be j
reviewed by the RSC.
l-6.1.5.2.
Audit Function: The records; of safety. surveys ~ and '
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deficiency reports aball be esamined by the Radiation-Safety :
Commit t ee. Audits aball be performed on an annual basis'.
6.1.5.3.
The RSC shall review surveillance performed in s'
compliance with technical specifications.
l 6.2.
Procedures Procedures aball be adequate to assure both the safety ll and adequate. security of the reactor.
Substantive' changes to the procedures aball be made only witb approval of the RSC. Teaporary changes to procedures which-do not change their original intent may be made by the RSO. All.such tosporary changes shall be documented and submitted to subsequent review by the RSC. Procedures aball be in ef fect fe-the following iteast 6.2.1. Emergency procedures.
6.2.2. ~ Security.
6.2.3. Calibtation.
6.2.6. Surveys.
6.2.5. Surveillance.
6.3.: Required Actions 6.3.1.
Action to be taken in the event of an occurrence defined in section 6.4.2.1.
6.3.1.1.
Corrective action shall be td.en to return conditions to normal.
6.3.1.2.
All such occurrences ob311 be promptly reported to the Level 2 authority or designated alternates.
5 Amendment No. 3 I
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Figure 1 1
Organisation Chart
' University President I
AAVP l
(Level 1)
-r Radiation Safety Radiation. Safety officer-Committee o
I Reactor - Administrator L.
Dean of the. College I
of Physical and-l Mathematical Science (Level 2) y i
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(..
Facility Chief i
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L Amendment No. 3
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