ML20212Q034

Proposed Tech Spec Section 6.0, Administrative Controls

ML20212Q034
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	03/10/1987
From:	RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY
To:
Shared Package
ML20212Q032	List: ML20212Q029 ML20212Q034
References
NUDOCS 8703160487
Download: ML20212Q034 (12)

Text

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i SECTION 6.0 ADMINISTRATIVE CONTROLS TECHNICAL SPECIFICATIONS (Proposed *)

License No. CX-22 Docket No. 50-225

• FoiIowing recommendatlon In Questlon No. 26 of " Request for AddItlonal Information. RPI Docket No. 50-225. HEU/ LEU Core Conversion Proposal" enclosure to letter from John J. Dosa to D.R. Harris on January 6, 1987.

0703160487 DR 870310 ADOCK 05000225 PDR

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6.0 ADMINISTRATIVE CONTROLS I 6.1 Oraanization 6.1.1 Structure The organization for the management and operation of the Reactor Critical Facility shall incorporate the structure Indicated in Figure 6.1.

Level 1: The Director of the Critical Facility is responsible to the Provost, via the chain of command, for conduct in accordance with the facility license and for requisite site admininistration.

Level 2: The Supervisor of the Critical Facility is responsible to the Director for operation, maintenance and management of the facility.

Level 3: Licensed senior operators are responsible for dally reactor operations.

Level 4: Licensed operators are the operating staff.

The Director, Office of Radiation and Nuclear Safety shall be a health physicist who is organizationally Independent of the operations personnel depleted in Figure S.1. It shall be his job to advise the Supervisor in matters concerning radiological safety. The office maintains inventories, provides consulting services, responds in emergencles, and conducts inspections in support of safety efforts. The Director of this office also has Interdiction responsibility and authority.

6.1.2 Resnonslbility The Supervisor of the Rensselaer Polytechnic Institute Reactor Critical Facility shall be responsible for the safe operation of the facility. He shall be responsible for ensuring that all operations are conducted in e safe manner and within the.Ilmits prescribed by the facility license, including those Technical Specifications.

In all matters pertaining to the operation of the reactor and these Technical Specifications, the Facility Supervisor shall report and be directly responsible to the Facility Director.

6.1.3 Staffina a) The minimal staffing when the reactor is not shutdown as described in these specifications shall be:

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1) An operator or senior operator licensed pursuant to 10 CFR 55 be present at the controls.

2) A licensed senior operator shall be present or readily available on call.

3) The loc.'tity of and method for rapidly contacting the licensed senior operator on duty shall be known to the operator, b) A list of reactor facility personnel by name and telephone number shall be readily available in the control room for use by the operator. The list must include:

1) Management personnel.

2) Radiation safety personnel.

3) Other operations personnel, c) Events requiring the direction of the Supervisor of the Critical Facility:

1) All fuel or control rod relocations within the reactor core.

2) Recovery from unplanned or unscheduled shutdown.

6.1.4 Selection and Trainina of Personnel The selection, tralning and requalification of operations personnel shall meet or exceed the requirements of American National Standard for Selection and Training of Personnel for Research Reactors, ANSl/ANS-15.4-1977, Sections 4-6.

Additionally, the minimum requirements for the Supervisor of the Critical Facility are at least four years of reactor operating experience and possession of a Senior Operator License for the RPI Critical Facility. Years spent in baccalaureate or graduate study may be substituted for operating experience ora a one-for-one basis up to a maximum of two years.

6.1.5 Review and Audit A Nuclear, Safety Review Board (NSRB) shall review and audit reactor operations and advise the Facility Director in matters rdlating to,the health and safety of the public and the safety of facility operations.

6-3 6.1.5.1 ca=aomition and oumlification The NSR8 shall have at least four members of whom no more than the minority shall be from the line organization shown in Figure 6.1. The board shall be made up of senior personnel who shall collectively provide a broad spectrum of expertise in reactor technology. Quallfled and approved alternates may serve in the absence of regular members.

6.1.5.2 Charter and Rules The Review Board shall function under the following rules:

a) The Chairman of the NSRB shall be approved by the Facility Director.

b) The Board shall meet at least semiannually.

c) The quorum shall consist of not less than a majority of the full Board and shall include the Chairman or his designated alternate.

d) Minutes of each Board meeting shall be distributed to the Director, NSRB members, and such others as the Chairman may designate.

6.1.5.3 Review and Anoroval Function The following items shall be reviewed and approved before Implementation.

a) Proposed experiments and tests utillzing the reactor facility which are significantly different from tests and experiments previously performed at the facility, b) Reportable occurences.

c) Proposed changes to the Technical Specificatins and proposed amendments to facility license.

6.1.5.4 Audit Function The audit function shall include selective (but comprehensive) examination of operating records, logs, and other documents. Where necessary, discussions with cognizant personnel shall take place. In no case shall the Individual immediately responsible for the area audit in the area. The following areas shall be audited at least annually:

6-4 a) Reactor operations and reactor operational records for compliance with internal rules, regulations, procedures, and with licensed provisions; b) Existing operating procedures for adequacy and to assure that they achieve their Intended purpose in light of any changes since their Implementation; c) Plat equipment performance with particular attention to operating anomalles, abnormal occurrences, and the steps taken to identify and correct their use.

6.1.6 Radiation and Nuclear Safety Ccmmittee 6.1.6.1 Membershio The Radiation and Nuclear Safety Committee is appointed by and reports to the Provost (or his designated representative). Members must have experience in the use of radiation and in some aspect of radiation safety.

The Director of the Office of Radiation and Nuclear Safety (Director of ORNS) is an ex officio member of the Committse.

l The Chairman is appointed by the Provost (or his designated representative). The Chairman's responsibilities include:

1) Calling meetings of the Committee.

2) Making recommendations to the Provost concerning the size and composition of the Committee.

3) Preparing reports of Committee activities for l the Provost. i Upon recommendation of the Chairman and approval of the Provost, the Committee may seek the advice i of a consultant having special expertise in some aspect of radiation safety.

6.1.6.2 Responsibilities

' The Committee is charged with:

1) Setting Institute policies for radiation and nuclear safety.

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2) Giving such advice and assistance as may be requested by the Director of ORNS.

3) Giving approval to reactivate an operation involving radiation if such an operation has been stopped by the Director of ORNS.

4) Evaluating the institute's overall radiation safety program and the effectiveness of the administration of this program and making a brief written annual report to the Provost.

f 6.1.6.3 Meetings The Committee meets at least bi-monthly during the academic year (September through May). Meetings may be called at any time during the calendar year whenever matters of urgency arise, as determined by the Provost, the Chairman or the Director of ORNS. Guests may attend meetings at the invitation of the Chairman. In the event that meetings are held in the absence of the Chairman, a Chairman pro tem will be selected from the attending members.

The Committee holds some of its meetings at institute radiation facilities for the purpose of inspecting the facilities and providing the members with a first-hand knowledge of each

, facility. The committee attempts to visit each facility at least once a year.

! Minutes of meetings are distributed to the members, the Provost (or his designated representative), the Assistant Director of ORNS and to the Chairman of the Nuclear Safety Review Board (NSRB).

4 6.2 Procedures Written procedures shall be prepared, reviewed and approved prior to Initiating any of the activities listed in this section. The procedures, including applicable check lists, shall be reviewed by the NSRB and followed for the following operations:

1) Startup, operation and shutdown of the reactor.

2) Installation and removal of fuel pins, control rods, experiments and experimental facilities.

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3) Corrective actions to be taken to correct specific and foreseen malfunctions such as for power failures, reactor scrams, radiation emergency, responses to alarms, moderator leaks and abnormal reactivity changes.

4) Periodic surveillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors.

5) Implementation of the facility security plan.

6) Implementation of facility emergency plan in accordance with 10 CFR 50, Appendix E.

7) Walntenance procedures which could have an effect on reactor safety.

Substantive changes to the above procedures shall be made only with the prior approval of the NSRB. Temporary changes to the procedures that do not change their original Intent may be made with approval from the Supervisor of the Critical Facility. All such temporary changes to the procedures shall be documented and subsequently reviewed by the Nuclear Safety Review Board.

6.3 Exneriment Raylew and Anoroval

1) All new experiments or classes of experiments that might involve an unreviewed safety question shall be reviewed by the Nuclear Safety Review Board. NSRB approval shall assure that compilance to the requirements of the license technical specifications shall be documented.

2) Substantive changes to previously approved experiments shall be made only after review and approval in writing by NSRB.

Minor changes that do not significantly alter the experiment may be approved by the Supervisor of the Critical Facility.

3) Approved experiments shall be carried out in accordance with established approved procedures.

4) Prior to review, an experiment plan or proposal shall be prepared describing the experiment including any safety considerations.

5) Review comments of the NSRB setting forth any conditions and/or limitations shall be documented in committee minutes and submitted to the Facility Director.

6.4 Reaulred Actions

6-7 6.4.1 Action to be Takan in came of Safety Limit Violatione a) The reactor shall be shut dcwn, and reactor operations shalI not be resumed untiI authorired by the Nuclear Regulatory Commission.

b) The safety limit violation shall be promptly reported to the level one authority or designated alternates and to the NSRB.

c) The safety limit violation shall be reported to the Nuclear Regulatory Commission in accordance with Section 6.5.3.

d) A safety llait violation report shall be prepared. The report shall describe the following:

1) Applicable circumstances leading to the violation including, when known, the cause and contributing factors.

2) Effect of the violation upon reactor facility components, systems, or structures and on the health and safety of personnel and the public.

3) Corrective action to be taken to prevent recurrence.

The report shall be reviewed by the NSRB and any followup report shall be submitted to the Commission when authorization is sought to resume operation of the reactor.

6.4.2 Action to ha Taken in the Event of an Occurrence of the Tyna identified in section 1.0 (Ranortable occurrence) a) Reactor conditions shall be returned to normal or the reactor shall be shutdown. If it is necessary to shutdown the reactor to correct the occurrence, operations shall not be resumed unless authorized by the Facility Director or designated alternate.

b) Occurrence shall be reported to the Facility Director or designated alternates and to the Commission as required, c) All such conditions, including action taken to prevent or reduce the probability of a recurrence, shall be reviewed by the NSR8.

6.5 Renorts

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6-8 In addition to the requirements of applicable regulations, and in no way substituting therefore, all written reports shall be sent to the U.S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D.C. 20555, with a copy to the Reglon i Administrator.

6.5.1 onaratina nanorts A written report covering the previous year shall be submitted by March 1 of each year. It shall include the following:

a) Onerations Summary. A summary of operating experience occurring during the reporting period that relate to the safe operation of the facility, including:

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1) Changes in facility design;

2) Performance characteristics (e.g., equipment and fuel performance); j

3) Changes in operating procedures which relate to the safety of facility operations;

4) Results of survelllance tests and Inspections required by these Technical Specifications;

5) A brief summary of those changes, tests, and experiments which require authorization from the Commision pursuant to 10 CFR 50.59(a), and;

6) Changes in the plant operating staff serving in the following positions:

p a) Director of the Critical Facility; b) Supervisor of the Critical Facility; c) Health Physicist; d) Nuclear Safety Review Board Members, b) Power Canaration. A tabulation of the Integrated thermal power during the reporting period.

c) Shutdowns. A listing of unscheduled shutdowns which have occurred during the reporting period, tabulated according to cause, and a brief discussion of the preventive action taken to prevent recurrence.

d) Walntenance. A tabulation of corrective maintenance (excluding preventative maintenance) performed during the reporting period on safety related systems and components.

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, 6-9 e) chanaan. Tants and Ernariments. A brief description and a summary of the safety evaluation for all changes, tests, and experiments which were carried out without prior Commission approval pursuant to the requirements of 10 CFR Part 50.59(b).

f) A auaunary of the cature, amount and maximum concentrations of radioactive affluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge.

g) Radioactive Monitorina. A summary of the TLD dose rates taksn at the exclusion area boundary and the site boundary during the reporting porlod.

h) Occunational Personnel Radiation Ernosure. A summary of radiation exposures greater than 25% of the values allowed by 10 CFR 20 received during the reporting period by facility personnel (faculty, students or experimenters).

6.5.2 Non-Routina Ranorta l a) Eggortable Onarational Occurrence Recorts.

Notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of Region I followed by a written report within 10 days in the event of a reportable operational occurrence as defined in Section 1.0. The written report on these reportable operational occurrences, and to the extent possible, the preliminary telephone and telegraph

• notification shall: (a) describe, analyze, and evalute safety Impilcations: (b) outilne the measures taken to assure that the cause of the condition is determined: (c) indicate the corrective action (including any changes made to the procedures and to the quality assurance program) taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems: and (d) evaluate the safety Impilcations of the incident in light of the cumulative experience obtained from the record of previous failures and malfunctions of similar systems and components.

" Telegraph notification may be sent on the next working day in the event of a reportable operational occurrence during a weekend or holiday period.

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6-10 b) Unusual Events. A written report shall be forwarded within 30 days in the event of: 1) Discovery of any substantial errors in the translent or accident analyses or in the methods used for such analyses, as described in the Safety Analysis Report or in the bases for the Technical Specificatins.

6.6 Onaratina Recorda 6.6.1 The following records and logs shall be maintained at the Facility or at Rensselaer for at least five years:

a) Normal facility operation and maintenance, b) Reportable operational occurrences.

c) Tests, check, and measurements documenting compilance with surveillance regulroments, d) Records of experiments performed, e) Records of radloactive shipments.

6.6.2 The following records and logs shall be maintained at the Facility or at Rensselaer for the life of the Facility:

a) Gaseous and liquid radioactive releases from the facility.

b) TLD Environmental monitoring systems, c) Radiation exposures for all RPl Critical Facility personnel (students, experimenters).

d) Fuel Inventories, offsite transfers and Inhouse transfers if they are not returned to their original core or vault location during the experimental program in which the original transfer was made, e) Facility radiation and contamination surveys.

f) The present as-built facility drawings and new updated or corrected versions.

g) Minutes of Nuclear Safety Review Board meetings.

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RPI REAC'IOR CRITICAL FACILITY ORGANIZATIONAL STRUC'IURE PROVOST E

VICE PROVOST 5

RADIATION AND l NUCLEAR SAFETY COMMITIEE l

DIREC'IOR, OFFICE OF RADIATICN AND DEAN, SCHOOL OF ENGINEERING NUCLEAR, SAFETY CHAIRMAN, DEFT OF NUCLEAR ENGINEERING AND SCIENCE E

DIREC'IOR OF CRITICAL FACILITY E

SUPERVISOR OF CRITICAL FACILITY NUCLEAR SAFETY REVIEW BOARD LICINSED SENIOR REAC'IOR OPERATOR (SRO)

E LICINSED REACIOR OPERATOR (RO)

Solid line: Direct chain of authority Dashed line: Working relationship with Figure 6.1