ML20003H234
| ML20003H234 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 03/25/1981 |
| From: | OHIO STATE UNIV., COLUMBUS, OH |
| To: | |
| Shared Package | |
| ML20003H231 | List: |
| References | |
| 18859, NUDOCS 8105050383 | |
| Download: ML20003H234 (7) | |
Text
. :- - - - -
. _ __ ( .
~O
- . a APPENDIX A LICENSE NO. R-110 TECHNICAL SPECIFICATIONS ~
FOR IDAHO STATE UNIVERSITY AGN-201 REACTOR (SERIAL #103) .
DOCKET NO. 50-284 DATE: November 15, 1978 AS MODIFIED TO INCLUDE ANSI N378-1974 AND REGULATORY GUIDE 2.2 GUIDANCE 5
1 I
i l
I l
l t
i Tib5OSO'AT53
{ : . . . . .. ..
1 6.0 ' ADMINISTRATIVE CONTROLS 6.1 Organization The administrative organization for control of the reactor facility and its operation shall be as set forth in Figure 1 attached hereto. The authorities and responsibilities set forth below are designed-to comply with the. intent and recuirements for administrative controls of the reactor facility as set forth by the Nuclear Regulatory Commission.
6.1.1 University Officer The University Officer is an administrative officer-a responsible for the University and in whose name the application for licensing is made.
6.1.2 Dean, School of Engineering The Dean of the School of Engineering is the administrative officer responsible for the operation of the' School of Engineering.
6.1.3 Reactor Administrator
. The Reactor Administrator is the administrative officer
- ! responsible for the operation of the AGN-201 Reactor Facility. In this capacity he shall have final authority and ultimate responsibility for the operation, maintenance, and safety of the reactor facility-within
- the limitations set forth in the facility license.
! He shall be responsible for appointing personnel to all positions reporting to him as described in 1 Section 6.1 of the Technical Specifications. Ee shall seek the advice and approval of the Radiation 2
Safety Committee and/or the Reactor Safety Committee
! in all matters concerning unresolved safety questions,
- new experiments and new procedures, and facility modifications which might affect safety. He shall i be an ex officio member of the Reactor Safety Committee.
6.1.l Reactor Supervisor I
I The Reactor Supervisor shall be responsible for the preparation, promulgation,- and enforcement of administrative controls including all rules, regulations, instructions, and operating procedures to ensure that the reactor facility is operated in a safe, competent, and authorized manner at all times. He shall direct the activities of operators and technicians in the daily operation and maintenance of the reactor; schedule reactor operations and maintenance; be responsible for 17
FIGURE 1 .
Administrative Organization of the Idaho State University AGN-201 Reactor Facility NRC License R-llo .
Idaho State University Officer Radiation Safety Reactor Safety Committee
~
Committee -
Reactor Administrator
- Reactor Supervisor * ,
4 Reactor Operators **
t .
1
- Requires NRC Senior Operators License
- Requires NRC Operators License except where exempt per 10 CFR 55 paragraph 55.9 N
18
- u. a_ . .. - -- :
~_:
6.1.4 the preparation, authentication, and storage of all contd prescribed logs and operating records; authorize all experiments, procedures, and changes thereto which have received the approval of the Reactor Safety Committee and/or the Radiation Safety Committee and the Reactor Administrator; and be responsible for the preparation of experimental procedures involving use of the reactor.
6.1.5 Reactor Ooerate _
Reactor Operators shall be responsible for the manipulation of the reactor controls, monitoring of instrumentation, operation of reactor related equipment, and maintenance of complete and current records during operation of the facility. Reactor Operators who are exempt from holding an NRC license per 10 CFR 55 paragraph 55.9 shall only operate the reactor under the direct and immediate supervision of a licensed Reactor Operator.
6.1.6 Reactor Safety Committee The Reactor Safety Committee shall be responsible for, but not limited to, reviewing and approving safety standards associated with the use of the reactor ,
facility; reviewing and approving all proposed experiments
~
and procedures and changes thereto; reviewing and approving all modifications eo the reactor facility which might af fect its safe operation; determining whether proposed experiments, procedures, or modifications involve unreviewed safety questions, as defined in 10 CFR 50 paragraph 50.59 (c), and are in accordance with these Technical Specifications; conducting periodic audits of procedures, reactor operations and maintenance , equipment performance, and records; review all reportable occurrences and violations of these Technical Specifications, evaluating the causes of such l
events.and the corrective action taken and recommending measures to prevent reoccurence; reporting all their findings and recommendations concerning the reactor facility to the Reactor Administrator.
6.1.7 Radiation Safety Committee The Radiation Safety Committee shall advise the University administration and the Radiation Safety of ficer on all matters concerning radiological safety at university facilities.
6.1.8 Radiation Safety Officer The Radiation Safety O'fficer shall review and approve all procedures and experiments involving radiological safety.
19
b:. . .
6.1.8 He shall enforce all federal, state, and university contd rules, regulations, and procedures relating to radiological safety. He shall perform routine radiation surveyc of the reactor facility and report his findings to the Reactor Administrator. He shall provide personnel dosimetry and keep records of personnel radiation exposure. He shall. advise the Reactor Administrator on all matters concerning radiological safety at the reactor f acility. The Radiation Safety Of ficer shall be an ejc officio m' ember of the Reactor Safety Committee.
6.1.9 Ooeratina Staff The minimum operating staff during any time in which the reactor is not shutdown shall consist of one licensed Reactor Operator and one other person capable of carrying out any' prescribed written instruction and oral instructions of operators and to summon help in the event the licensed operator becomes incapacitated.
6.2 Staff Qualifications The Reactor Administrator, the Reactor Supervisor, licensed Reactor Operators, and technicians performing reactor maintenance shall meet the minimum qualifications set forth in ANS 15.4, " Standards for Selection and
- Training of Personnel for Pesearch Reactors." Reactor Safety Committee members shall have a minimum of s five (5) years experience in their profession or a baccalaureate degree and two (2) years of professional experience. Generally, these committee members will be made up of University faculty, but outside experience may be sought in areas where additional experience is considered necessary by the Reactor Administrator.
6.3 Training The Reactor Administrator shall be responsible for directing training as set forth in ANS 15.4, " Standards for Selection and Training of Personnel for Research Reactors." All licensed reactor operators shall
! participate in requalification training as set forth I in 10 CFR 55.
6.4 Reactor Safety Coumittee 6.4.1 Meetings and Quorum
! The Reactor Safety Ccanittee shall meet as often as l
deemed necessary by the Reactor Safety Committee Chairman but shall meet at least once each calendar year.
A quorum for the conduct of official business shall be the chairran, or his designated alternate, and two (2) other regular members. At ne time shall the operating organization comprise a voting majority of the members I
at any Reactor Safety Committee meeting.
o 20
6.4.2 Reviews -
The Reactor Safety Committee shall review:
- a. Safety evaluations for changes to procedures, equipment or systems, and tests or experiments, cc:. ducted without Nuclear Regulatory Commission approval under the provision of 10 CFR 50 paragraph 50.59, to verify that such actions did not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems, and tests or experiments , conducted without Nuclear
-Regulatory Commission approval under the provision of 10 CFR 50 paragraph 50.59, to verify that such
~ actions did ndt constitute an unreviewed safety question.
- c. Proposed tests or experiments which are significantly dif ferent from previous approved tests or experiments, or those that involve an unreviewed safety question as defined in Section 50.59, 10 CFR 50 paragraph 50.59.
- d. Proposed changes in Technical Specificaitons or licenses. ,
- e. Violations of applicable statutes, codes, regulations, orders , Technical Specifications , license requirements, or of internal procedures or instruciton having nuclear safety significance.
- f. Significant operating Cbnormalities or deviations from normal and expected performance of facility equip =ent that affect nuclear safety.
- g. Reportable occurrences.
! h. Audit reports.
l l 6.4.3 Audits i Audits of facility activities shall be performed l under the cognizance of the Reactor Safety Committee I
but in no case by the personnel responsible for the
! item audited. These audits shall examine the operating records and enco= pass but shall not be limited to the l following:
l
- a. The conformance of facility operation to the l
Technical Specifications and applicable license conditions, at least once per 12 months.
i l
21
_/
5 .
- b. The performance, training and qualifications of the entire facility staff, at least once per 24 months.
- c. The results of all actions taken to correct deficiencies occuring in facility equipment, structures, systems or method of cperation that affect nuclear safety, at least once per calendar year.
- d. The Facility Emergency Plan and implementing procedures, at least once per 24 months.
~
- e. The Facility Security Plan and implementing procedures, at least once per 24 months.
6.4.4 Authority _f The Reactor Safety Committee shall report to the President and shall advise the Reactor Administrator on those areas of responsibility outlined in section 6.1.6 of .
these Technical Specifications. .
6.4.5 Minutes of the Reactor Safety Committee The Chairman of the Reactor Safety Committee shall direct the preparation, maintenance, and distribution of minutes of its activities'. These minutes shall include a summary of all meetings, actions taken, audits, and reviews.
s% $
22 iSS59
/