ML20147H381
| ML20147H381 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 03/31/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20147H367 | List: |
| References | |
| TR-05-A-008, TR-5-A-8, NUDOCS 9704030100 | |
| Download: ML20147H381 (6) | |
Text
Ja atou y" k UNITED STATES j T
~f j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 o
,,o NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY DOCKET NO. 50-184 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. TR-5
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to Facility Operating License No. TR-5 filed by the National Institute of Standards and Ta hnology (the licensee), dated January 17, 1997, complies with the standards and-requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission.
C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C (2) of License No. TR-5 is hereby amended to read as follows:
9704030100 970331 PDR ADOCK 05000184 p PDR
i 2-(2) Technical Specifications ;
The Technical Specifications contained in Appendix A, as revised through Amendment No. 8, are hereby incorporated in the license i The licensee shall operate the facility in.accordance with the Technical
. Specifications. '
- 3. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,e , eE ;
Seym'our H. Weiss, Director i Non-Power Reactors and Decommissioning (
Project Directorate i Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosure:
Changes to the Technical Specifications ;
Date of Issuance: March 31, 1997 I
1 1
Y ENCLOSURE TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. TR-5 DOCKET NO. 50-184 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contains vertical lines indicating the areas of change.
Remove Pace Insert Pace 31 31 32 32 33 33
1 c 7.0 ADMINISTRATIVE CONTROLS 7.1 Oraanization The organization for the management and operation of the reactor facility shall be as indicated in Figure 7.1. The Director, NIST Center for Neutron Research, and the Chief Nuclear Engineer, Reactor Operations, shall have line l responsibility for direction and operation of the reactor facility, including l safeguarding the general public and facility personnel from radiation exposure I and adhering to all requirements of the Operating License and Technical Specifications.
The minimum qualifications with regard to education and experience backgrounds of key supervisory personnel in Reactor Operations shall be as follows:
(1) Chief Nuclear Enaineer The Chief Nuclear Engineer must have a college degree or equivalent in specialized training and applicable experience, and at least 5 years experience in a responsible position in reactor operations or related fields, including at least 1 year experience in reactor facility management or supervision.
(2) Deoutv Chief Nuclear Enaineer l The Deputy Chief Nuclear Engineer mest have a combined total of at least 7 years of college level education and/or nuclear reactor experience with at least 3 years experience in reactor operations or related fields. The .
person must also be qualified to hold a senior operator's license. i I
(3) Reactor Supervisor (a) At least 4 years experience in reactor operations, including experience in the operation and maintenance of equipment and in the supervision of technicians and/or reactor operators.
(b) A high school education or equivalent and formal training in reactor technology and reactor operations. (An additional 2 years of experience may be substituted for education and formal training.)
(c) Qualified to hold a senior operator's license.
For operation, the normal crew complement for a shift shall be three persons.
The minimum crew complement for a shift shall b'e two persons, including at least one licensed senior operator.
7.2 Safety Evaluation Committee The Safety Evaluation Committee shall be composed of at least four senior technical personnel who collectively provide a broad spectrum of expertise in reactor technology. The Committee members shall be appointed by the Director, NIST Center for Neutron Research. At least two members shall be from the NIST Center for Neutron Research and one shall be from Health Physics. The quorum requirement of the Committee shall be three members. Alternates appointed by the Director, NIST Center for Neutron Research, may serve during the absence l of regular members.
31 Amendment No. 8 i
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l Director, NIST Center for Neutron Research
___________, l.l ;
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~NIST Health Physics Reactor Operchons Technicci Support l
Safety Evoluotion Safety Audit Commmee Committee Figure 7.1 organization for the management and operation of the reactor facility 32 knendnent No. 8 I
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The Safety Evaluation Committce shall meet semiannually during reactor l
operations and as circumstances warrant. Written records of the proceedings, including any recommendations or concurrences, shall be maintained. The 1 Committee shall report directly to the Director, NIST Center for Neutron j Research. i The Safety Evaluation Committee shall )
(1) Review proposed changes to the NBSR facility equipment or procedures when such changes have safety significance, or involve an amendment to the i facility license, a change in the Technical Specifications incorporated !
in the facility license, or an unreviewed safety question pursuant to 10 CFR 50.59. J (2) Review propos.ed tests or experiments significantly different from any previously reviewed or which involve any unreviewed safety question pursuant to 10 CFR 50.59.
(3) Determine whether proposed changes or reactor tests or experiments have been adequately evaluated and documented and provide recommendations for action.
(4) Review the circumstances of all repcrtable occurrences and violations of Techni 21 Specifications and the measures taken to preclude a recurrence I and provide recommendations for action. I 7.3 Safety Audit Committee The safety Audit Committee shall be composed of three senior technical personnel who collectively provide a broad spectrum of expertise in reactor technology. The Committee members shall be appointed by the Director, NIST l Center for Neutron Research. Members of the Safety Audit Committee shall not be regular employees of the National Institute of Standards and Technology. ,
At least two members must pass on any report or recommendation of the '
Committee.
l The Safety Audit Committee shall meet annually and as required. The Committee shall audit NBSR facility operations and the performance of the Safety Evaluation Committee. The Safety Audit Committee shall report in writing to the Director, NIST Center for Neutron Research.
l I
7.4 Procedures All procedures and major changes thereto, before being effective, shall be reviewed by the Safety Evaluation Committee and approved in writing by the Chief, Reactor Operations, or his Deputy. Changes, which do not significantly change the original intent of a procedure, may be approved by the Chief, Reactor Operations, or his Deputy.
Written procedures shall be provided and utilized for the following:
(1) normal startup, operation, and shutdown of major components and systems 33 Amendment No. 8