ML20247B983
| ML20247B983 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 09/04/1989 |
| From: | Richardson H TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247B988 | List: |
| References | |
| NUDOCS 8909130200 | |
| Download: ML20247B983 (3) | |
Text
I Texas Engineering Experiment Station The Texas A&M University System College Station, Texas 77843-3577 409/8451321 1EEE 4 September 1989 Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 REF: Docket No.58-128 Facility License No. R-83
SUBJECT:
License Amendment Request - NSCR Organizational Structure Gentlemen:
The Texas Engineering Experiment Station (licensee) respectfully requests the approval of changes to facility operating License R-83 regarding the NSCR Organizational structura as described in Section 6.0 and a change tc the reporting requirements of reactor administration personnel changes as required in Section 6.6.2(b) (1) of the Technical Specifications. The proposed changes are formally presented on retyped pages 46, 47, 50, 51 and 57 of Sections 6.0 and 6.6.2 of the Technical Specifications. The proposed changes have been reviewed and approved by the licensee, the Director of the Nuclear Science Center ar,d the Reactor Safety Board with a conclusion that the naw organization is an improvement in administrative controls and provides for improved communications and more efficient operations. This proposed change will provide for a more streamlined and better functioning organization with clearly defined responsibilities.
The proposed changes are consistent with the organizational structure outlined in the research reactor standard ANSI /ANS 15.1 "The Development of Technical Specifications for Research Reactors". Responsibilities are stated for individuals at all levels of reactor administration and operations, associated advisory- organizations, and support organizations. License responsibilities have been assigned to the Deputy Director of the Texas Engineering Experiment Station. Assignment of the license to the Deputy Director (TEES) does not change the financial commitment and responsibilities made to the USNRC by the Texas Engineering Experiment Station in support of NSCR activities.
I Implementation of the proposed changes would not result in any unfavorable safety implications and does not present any unreviewed safety questions. It is concluded that the safety and operational efficiency of the NSCR will be greatly enhanced by the new l
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' Nuclear Regulatory Commission 4 September, 1989 Page 2 l
l organizational structure and will result in improved management ,
control of the routine daily function of operations and health !
physics programs.
l In addition to the above changes in the NSCR Organizational structure it will be necessary to change the designated licensee in the reporting requirements of Section 6.6.2(b) (1) of the Technical Spec'.fication. This change is reflected on page 57.
The individual named to be responsible for the license, including mailing address and telephone number, is as follows:
Dr. K. R. Hall, Deputy Director Texas Engineering Experiment Station Texas A&M University College Station, Texas 77843 (409) 845-3357 Thank you for your consideration.
Respectfully submitted, 8Wh4Y k l m Herbert H. Richardson, Director y Texas Engineering Cuperiment Station HHR/ bas Enclosures Sworn of ),/)
to before me the undersigned authority this M day
, 1989.
/
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BARBARA BLAINE SMITH '
Mtsfy Pub!c. State of Tczas
/ th comrnission Expires IMHO
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m'e.esessaawwwwa In and For Brazos County, Texas 4 Commission expires /d- 7 1 4 l b 4
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cc: Mr. R.'D. Martin, Regional Administrator, USNRC, Region IV Mr. T. Michaels, Project Manager,'USNRC, Washington Dr. K. R. Hall, Deputy Director, TEES Mr. D. E. Feltz, Director, NSC Dr. K. L. Peddicord, Assistant Director, TEES Dr. C. A. Erdman, Associate Dean, TEES Dr. J. W. Poston, Head, Dept. of Nuclear Engineering Mr. F. Jennings, Chairman, Reactor Safety Board Dr. M. E. McLain, Radiological Safety Office Dr. J. A. Reuscher, Nuclear Science Center y
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'6.0 Admir.istrative Controls' l- h.1 Organization l_
6.1.1 Structure (a)' A line management organizational structure shall provide for-
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the administration and operation of the reactor facility.
The Deputy Director of the Texas Engineering Experiment Station (TEES) and'the Director (NSC) shall have line manage-ment responsibility. for adhering to the terms and conditions of the NSCR license and technical specifications and for safeguarding the public and facility personnel from undue radiation' exposure. .The facility shall be under the direct control of the Director (NSC) or a licensed senior reactor operator designated by him to be in direct ?ontrol.
(b) Management Levels Level 1 - Deputy Director TEES (Licensee) - Responsible for the NSCR. facility license.
Level 2 - Director (NSC) Responsible for reactor facility operation and shall report to Level- 1..
Level 3 - Senior Reactor Operator on Duty - Responsible for the day-to-day operation of the NSCR or shift aperation and shall report to Level 2.
Level 4 - Reactor Operating Staff - Licensed reactor operators and senior reactor operators and trainees. These individuals shall report to Level 3 (c) Radiation Safety - A qualified, health physicist shall be assigned responsibility for implementation of the radiation
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protection program at the NSCR. The individual shall repurt to Level 1 management.
(d) Reactor Safety Board (RSB) - Responsible to the Licensee for providing an independent review and audit of the safety aspects of the NSCR.
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- 6.1;2 . Responsibility - Responsibility for' the safe operation of' the .
reactor facility shall be in accordance with the lline organization established-in'6.1.1.
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6.2' Review and Audit 6.2.1 . Reactor Safety Board '-.The Reactor Safety Board (RSB) shall con-sist of at least three (3) voting members knowledgeable in fields -
which relate to nuclear safety. The RSB shall review, evaluate and' make recommendations on safety -standards associated with the operational use or' the facility. NSCR operations and health physics shall be' represented as ex-officio ~ members on the RSB.
The review and advisory functions of the' RSB shall include NSCR operations, radiation protection, and the facility license.
6.2.2 RSB Charter and Rules - The operations of the RSB shall be in accordance with a written charter, including provisions for:
(a) Mee' ting frequency - not less than once per calendar year and as frequent as circumstances warrant consistent with effective monitoring of facility activities.
(b) Voting rules (c) Quorums (d) Use of subcommittees
( e') . Review, approval and dissemination of minutes 6.2 3 RSB Review Function - The responsibilities of the RSB or a
, designated subcommittee thereof include, but are not limited to the following:
L (a) Review and evaluation of whether a proposed change, test, or experiment would constitute an unreviewed safety question or a change in Technical Specifications.
(b) Review of new procedures, major revisions of procedures, and proposed changes in reactor facility equipment or systems having safety significance.
(c) Review of new experiments or classes of experiments that could affect reactivity or result in the release of g radioac tivity .
(d) Review of proposed changes in technical specifications, license, or charter.
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!{ (e) Review of the NSCR radiation ~ protection program.
( f)- Review of violations of. technical specifications,. license, or charter, and violations of internal procedures or I
instructions having safety significance.
(g) Review of operating abnormalities having safety significance.
(h) Review of reportable occurrences listed in 6.6.2.
(i) Review of audit reports.
t 6.2.4 RSB Audit Function - The RSB or a subcommittee thereof shall audit reactor operations and radiation protection programs at least quarterly, but at intervals not to exceed four months.
Audits shall include but are not limited to the following:
(a) Faci.lity operations, lncluding radiation protection, for conformance to the technical specifications, applicable license conditions, and standard operating procedures at least oncc per calendar year (interval between audits not
.to exceed 15 months).
(b) 'The retraining and requalification program for the operating staff at least once per calendar year (interval between audits not to exceed 15 montr.s).
(c) The facility security plan and reccrds at least once per calendar year (interval between audits not to exceed 15 months).
(d) The reactor facility emergency plan and implementing procedures at least once per calendar year (interval between audits not to exceed 15 months).
6.2.5 Audit of ALARA Program - The licensee or his designated alternate (ex luding anyone whose normal job function is within the NSCR) shall conduct an audit of the reactor facility ALARA pre-ram at least once per calendar year (interval between audits not to exceed 15 months). The results of the audit shall be transmitted by the licensee to the RSB at the next scheduled meeting.
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,ce (b)- A written report within 30 days of:
(1) Personnel changes'in - the facility organization involving b
Level.1 and Level 2.
(2) Significant changes in the . transient or accident analysis as described in the Safety ' Analysis Report.
6.7 Records - Records of facility operations in the form'of logs, data sheets or other suitable forms shall be retained for the period indicated as
.follows:
- 6. 7.1. Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved
( a') Normal reactor facility operation.
(b)- Principal maintenance operations.
(c)- Reportable occurrences.
(d) Surveillance activities required by the Technical Specifications.
(e) Reactor facility radiation and contamination surveys where required by applicable regulations.
(f) Experiments performed with the reactor.
(g) Fuel inventories, receipts, and. shipments.
(h) Approved changes in operating procedures.
(i) Records of meeting and audit reports of the RSB.
6.7.2 Records to be Retained for at Least One Training Cycle - Re-training and requalification of certified operations personnel:
Records of the most recent complete cycle shall be maintained at all times the individual is employed.
6.7.3 Records to be Retained for the Lifetime of the Reactor Facility (a) Gaseous and liquid radioactive effluents released to the l environs.
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