ML20247B990
| ML20247B990 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 09/04/1989 |
| From: | TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | |
| Shared Package | |
| ML20247B988 | List: |
| References | |
| NUDOCS 8909130201 | |
| Download: ML20247B990 (23) | |
Text
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6.0 Administrative Controls 6.1' organization 6.1.1. Structure (a) A line management organizational structure shall provide for 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 control.
(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 shif t operation and shall report to Level 2.
Level 4 - Reactor Operating Staff - Licensed reactor operators and s.enior 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 protection program at the NSCR. The individual shall report 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 1'of the reactor facility: shall be in accordance with the line organization
' established in 6.1.1.
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? - i l : 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 of 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) Meeting 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:
(a) Review and ev,aluation 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) ~deview of new experiments or classes of experiments that crold affect reactivity or result in the release of radioac tivi ty .
(d) Review of proposed changes in technical specification, 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 l instructions having safety significance. .
(g) Review of operating abnormalities having safety significance.
(h)- ' Review of reportable occurrences listed in 6.6.2.
f (1) Review of audit reports.
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: -
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.(a) Facility operations, including radiation protection, for conformance to the technical specifications, applicable license conditions, and standard operating procedures at least once per' calendar year (interval between audits not to exceed 15 months). l (b) The retraining and requalification program for. the .
operating staff at least once per calendar year (interval between audits not to exceed 15 months).
(c) The _ facility security plan and records at least once per calendar year (interval between audits not to exceed 15 months).
(d) The reactor facility emergency plan and impicmenting 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
, (excluding anyone whose normal job function is within the NSCR) shall conduct an audit of the reactor facility ALARA program at least once per calendar year (interval between audits not to exceed-15 months). The results of the audit shall be transmitted l t
by the licensee to the RSB at the next scheduled meeting.
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.(b) A written report'within 30 days of:
(1) Personnel changes in the facility organization involving Level 1 and Level 2. S (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 I 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 l
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.
(1) 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 Liretime of the Reactor Facility (a) Gaseous and liquid radioactive effluents released to the environs.
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6.1 Organization 7%s % ,4154 57, 5'7 -4 h
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6.1.1 - Structure W
- a. The facility shall be under the direct control of the Director )
(NSC) or a licensed senior operator designated by him to be in l direct control. The Director (NSC) shall be responsible to l the Director of the Texas Engineering Experiment Station
-l (TEES) for safe operation and maintenance of the reactor and i its associated equipment. The Director (NSC) shall report to -
the Director of TEES through the Director, Nuclear Research Reactor Programs. The Director (NSC) or his appointee shall review and approve all experiments.and experimental procedures i prior to their use in the reactor. He shall enforce rules for the protection of personnel against radiation.
- b. The safety of operation of the Nuclear Science Center Beactor
-shall be related to the reactor licensee as shown in the following chart.
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Experiment Station - - - - - - - - Heact r Safety O ice (T$ES) e Board l
Dire.ctor !
Nuclear Hesearch I Reactor Programs !
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Ser ior Director i
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Nuclear Sctence Center ---------J Physjicist (11SC)
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6.1.2 l
Responsibility - Responsibility for the' safe operation of the reactor facility shall be in accordance with the chain of consoand established in the organizational chart. individuals
~ 'at the various levels, in addition to having responsibility for tNo policies and operation of the reactor facility, shall be responsible for safeguarding the public and facility f
1 personnel from undue radiation exposures and for adhering "
to all requirements of.the operating license and technical specifications.
Individual responsibilities at the various '
levels are as follows:
(a) Director, Texas Engineering Experiment Station -
Aa.;. licensee has ultimate resp.onsibility for the safe and proper operation of the facility. . <
, (b) Director, Nuclear Science Center - Has overall responsibility for insuring nuclear safety and pro-
, viding administration of the Hucicar Science Center.
I(c) Reactor Operations - Responsible for,.thg_ day-to-day -
, operations of the reactor.
(d) Radiological Safety Office - Responsible for providing '
., "on-site" advice, technical assistance, and review in all areas related to occupational and radiological 4
safety.- .
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,- (e) . Reactor Safety Board - Responsible for providing an
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independent review and audit of the safety aspects of s .
reactor' facility operations and for advising the 4 directors in these areas.
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6.1.3 . Staffing -
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(a) The minhum staffing when the reactor is not secured shall be as followst. -
.i ' (1)< ..At least two individuals will be present at the
- facility _ complex and will consist of a licensed.
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.....; . enior rpactor operator and 'either a licensed
. I , ..s. reactor operator or operator trainee. During periods
.. .f. of reactor innintenance as .specified in 1.27(b) the 1 . .'
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, '.h'!:. reactor operator <or the operator. trainee may be
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"'?.re,placed by maintenance personnel.*
s (2) : A licensed reactor operator or senior reactor operator I
,will be in the control room.
I (3) The Director (NSC) or his designated alternate will
'be readily available for emergencies (i.e., capable of getting to the reactor facility within a reasonable, time).,
(4). At least one member of the health physics support group will be. readily available to provide advice ,
and technical assistance in the area of radiation protection.
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- The licensed enidr reactor operator may be permitted as the only operations person present at the facility to perform a prestartup check of the reactor or perform l
,; general reactor maintenance not specified in 1.27(b).
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(b) SA' list of reactor facility personnel by nque a. nd
. telephone number shall be readily available for use -
,7 in the contro'1 room. The lise shn11 include: *
. (1) Administrative personnel .
(2) Radiation safety personnel..
(3) Other operations personnel '
(c) The following designated individuals shall direct the events listed (1) The Director (NSC) or his designated alternate shall direct any loading of fuel or control rods within the reactor core region.
(2) The Director (HSC) or his designated alternate
.shall direct any loading of an in-core experiment vith a reactivity worth greater than one. dollar.
(3) The senior reactor operator on duty shall direct the recovery from an unplanned or unscheduled shutdown otiier than a safety limit violation.
6.1.4 ,S. election and Training of Personnel - The selection and 4 training of operations personnel shall be in accordance with
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the following: .
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(a) Responsibility - The Director (NSC) or his designated alternate is responsible for the training and requalifi-e cation of the facility reactor operators and senior '
, reactor operators.
(b) Requalification Program
, (1) Purpose - To insure that ail operating personnel
, maintain proficiency at a level equal to or greater than that required for initial licensing. .
(2) ,
Scope - Scheduled lectures, written examinations and evaluated console manipulations will be used to insure operator proficiency is maintain'ed. I l
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L6.2.1 ' Reactor Safety Board - A Reactor Safety-Board (RSh) of at 2 least three (3)f members knowledgeable in fields which relate \
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to nuclear ~ safety shall review, evaluate, and approve safety ,
i standards associated with the operation and use of the-
- .- f acility. . The Director- (NSC) and the University Radiological j Safety Officer shall' be ex-officio members of the RSB.- An .y
- . audit group shall be composed 'of a minimum of one
- (1) member"--
or ex-officio member of the RSB. Qualified and approved g alternates may serve in the absence of regular members. The
~ jurisdiction of the- RSB shall include all nuclear operations in,the facility and general safety standards, i 6.2.2. RSB Charter and Rules - The operations of the RSB shall be in accordance with a written' charter, including provisions fort
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. (a)~ Meeting frequency - not less than once per calendar year and as. frequent as circumstances warrant consistent with.
effective monitoring of facility activities.
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-(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
- designated subcommittee thereof include, but are not limited to.
the following:-
o (a) Determination of whether a proposed change, test', or
,' experiment would constitute an unreviewed safety question
, , or a change in Technical Specifications. .
- (b) Review of new procedur'es, major revisions o.f procedures, and proposed changes in reactor facility equipment or
- f systems having safety significance. -
, (c) Review of new experiments or classes of experiments that could affect reactivity or result in the release of I radioactivity.
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(d) Proposed changes in technical specifications, license, or charter. .~ ~
(c) Violations of technical specifications, license, or l
charter. Violations of internal procedures or instructions having safety significance. .
, "(f) Operating abnormalities having safety significance.
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'(g) Reportable occurrences listed in.6.6.2.
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(h) Audit reports.
6.2.4 ;RSB Audit Function - The RSB or a subcommittee thereof shall
. c audit reactor operations at least quarterly, but at intervals 1 not to exceed four. months. Audits shall include but are not limited to the following:
(a) Facility operations for conformance to the technical specifications and applicable license condi-tions at least once per calendar year (interval between audits not to exceed 15 months).
(b) The retraining and requalification program for the e operating staff, at least once per calendar year (iriterval between audits not to exceed 15 conths).
(c) The f'a cility security plan and records . at least once per I calendar year (interval between audits not to exceed 15 mon ths) . s
, (d) The reactor f acility emergency plan and implementing
', , procedures at least once per enlendar year (interval between audita net to exceed 15 months).
, . 2,. 5 Audit of ALARA Program - The Director. (NSC) or his designated
- 41 ternate, shall conduct an dudit of the reactor facility ALARA program at least once per calendar year (interval betweentaudits not' to exceed 15 months). The results of the audit shall be presented to the RSB at the next scheduled meeting.
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6.' 3 '
Op7rttink Procadurcs. - Written operating proceduras shall be pr::parad,-
, revievsd, and epproved prior to initiating any of the activities
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listed in this section.- The procedures shall be reviewed and approved by the Director (USC) or 'nis ' designated alternate and the Reactor Safety
, Board and shall be documented in a timely manher, Procedures shall bc adequa'te to assure the safe operation of the reactor but shall not pre-cibde the use of independent judgment and action should the situation I require such... Operating procedures shall be in effect for the .
following items-l-
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(a) 'Startup,' operation, and shutdown of the reactor.
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- e (b) ' ' l Fuel 1 ading; unloading, and movement within the reactor.
(c)~ Cotitrol rod removal or replacement. ,
i (d)' i Routine maintenance of the control rod drives and reactor l safety;andinterlocksystemserotherroutinemaintenancethat s .. :
could have'an effect on reactor safety. !
(e). Testing and calibration of reactor instrumentation and controls, control rod drives, crea radiation monitors, and facility air monitors. -
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(f) ' Administrative controls for operations, maintenance, and conduct -
of irradiations and experiments that could affect reactor safety or core reactivity.
(g) Implementation of required plans such as emergency or security plans. ~
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(h) Actions to be taken to correct specific and foreseen potentia'l malfunctions of systems, including responses to alarms and l
,, abnormal reactivity changes.
Substantive changes to the above procedures shall be made effective only after documented review and approval by the Director (NSC) and !
the Reactor Safety Board. Minor modifications or temporary changes to , !
the original procedures which do not change their original intent may be made by the Director (NSC) or his designated alternate. All such .
l temporary changes shall be documented and subsequently reviewed by 4
the Reactor Safety Board.
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M. . 6' 4 '! Experiments Review and Approval - Approved experime ts shall $e carried g ,
_out in accor' dance with establishedfand ' approve,d pr'ocedures.
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All new experiments or class of experiments shal'1 be reviewed by the' RSB (Section 6.2.3) and implementation approved in wr'i ting -
- by.- the Director ' (NSC) or,his designated alternate. .
., (b). ;Substantivechangestopreviously)approvedexperimentsshallbe
'fmadeonlyafterreviewbytheRSBandimplementationapprovedin
. I writ 1Eg 'by',the'Di. sector (NSC) or his designated alternate.
Minor *
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,- changes,that do not'significantly alter the experiment may bc
[approv'ed by. the Director (NSC) or his designated alternate. - *
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6.5; Required Actions -
- 6. 5.1. t._ Action'to be Taken in the Event a Safety Limit is~ Exceeded .
In the event a safety' limit is exceeded:-
(a) The. reactor shall'be shut-down and reactor operation shall-not be' resumed until authorized by the NRC. ,
-(b) An immediate report of the occurrence shall be made to the Chairman, R'eactor Safety Board, and reports shall be
- made to the NRC in accordance with Section 6.6.2 of these specifications, and .
(c) A report shall be prepared which shall include an analysis of'the cause and extent of possible resultant damage, efficacy of coriective action, and recominendations for measures to prevent or reduce the probability of recur-rence. This report shall be submitted to the Reactor
. . Safety Board for review and then submitted to the NRC when authorization is sought to resume operation of the reactor.
6.5'.2 Action to be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, the following action shall be.taken:
(a) Reactor conditions shall be returned to normal or the 4 reactor shall be shut down. If it is necessary to shut down the reactor to -correct the occurrence, operations shall not be resumed unless authorized by the Director (NSC) or' his designated alternate. ,
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(b) ~ ~ The Director (HSC) or his designated alternate shall be notified and corrective action taken with respect to the operations involved.
7 (c) ~ The Director (NSC) or' his designated alternate shall -
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! notify.the Chairman of the Reactor Safety Board. ,
- , - ;(d) ^ JA report shall be made to the Reactor. Safety \Board which.
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'shall.' include. an analysis of the cause' of the occurrence,
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eff'icacy of corrective action,' and. recommendations for
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measures
' to prevent or reduce the' probability of recur-
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. a. . . ' .. . . . e , : -,.rence,;and 4 3.f (e) ~ A' repo'rt shall be made to the NRC in accordance with Section
. . h" 6.6.2.of these specifications.
(f)' Occurrence shall be reviewed by the RSB at their next 1 scheduled meeting.
- 6. 6 ' . Reporting Requirements
- 6. 6.1 : Annual Report An annual report covering the operation of th'e reactor facility
'during the previous calendar year shall be submitted to the NRC
. prior to March 31 of each year providing the following information:
(a)
A brief narrative summary of (1) operating esperience (including experiments performed), (2) changes in facility -
design,. performance characteristics, and operating pro-cedures related to reactor safety and occurring during b
,- the reporting period, and (3) results of surveillance tests and inspections;
,( b) Tabulation of the energy output (in megawatt. days) of the
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reactor, hours reactor was critical, and the cumulative total energy output since initial criticality; (c) The number of emergency shutdowns and inadvertent scrams,
, including reasons therefor;
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'(d) - h)iscussion of the major maintenance operations performed
. during the period, including the effect,' if any, on the .
, : safety of the~ operation of the rea'ctor and the. reasons for '
'any corrective maintenance required, (e) A brief description, including a summary of the safety l evaluations of changes in the facility or in procedures and of testu and experiments carried out pursuant to Section 50.59 of 10 CFR'Part 50; (f) A summary of the nature and amount of radioactive effluents 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. If the' estimated average .
release af ter dilution or diffusion is .less than 25% of the concentration allowed or recommended, a statement to this:effect is sufficient.
. 1... Liquid Waste (summarized on a monthly basis)
(a) Radioactivity discharged during the reporting period. ,
. (1) Total radioactivity released (in curies).
(2) The MPC used and the isotopic composition if greater than'1 x'10~7 microcuries/cc for fission and activation products.
(3) ' Total radioactivity (in curies), released
. by nuclide, during the reporting period based on representative isotopic analysis.
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, (4) Average concentration at point of release
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, , , (in microcuries/cc) during the reporting
. period.
, (b) Total volume (in gallons) of effluent water (including diluent) during periods 01 release.
. 2. Caseous Waste (summarized on a monthly basis) {
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(a) Radioactivity discharged during the reporting .
period (in curies) for:
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es . (1) Argon-4I (2) Particulate with half-lives greater than l , ,
eight days.
- 3. Solid Waste (a). The total saount of solid waste transferred j (in cubic feet).
(b) The total activity involved (in curies).
(c) The datas of shipment and disposition (if ,
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shipped off site).
,(g) A summa'ry of radiation exposures received by facility personnel and visitors,. including dates and time where such exposures are greater than 25% of that allowed or re. commended .
(h) A description and summary of any environmental surveys performed outside the facility.
6.6.2 Special Reports - In addition to the requirements of applicable regulations, and in'no way substituting therefor, reports shall -
'be made to the NRC. Region IV, Office of Inspection and Enforce-ment as follows:
(a) There shall be a report not later the.n the following working day by telephone and confirmed in writing by -
, telegraph or sidilar conveyance to be followed by a written report that describes the circumstances of the '
, event- within 14 days of any of the following:
, (1) Violation of safety limits. (See 6.5.1).
(2) Any accidental release of radioactivity above per-missible limits in unrestricted areas whether or n'ot the release resulted in property damage, personal injury, or expos ce;
.- . (3) Any reportable occurrences as defined in Section 1.28 of-these specifications. The written report (and, 4 to the extent possible, the preliminary telephone or telegraph report) shall describe,. analyze, and evaluate
, safety implications, and outline the corrective measures
, taken or planned to'preveot reoccurrence of the event; o t
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(b) A written report'within 30 days of: ,'
.(1): Personneb changes in the 'facil'ity organization in-volving the Director of the~ Texas Engineering ,
Experiment Station (license'e)l or the Director (NSC).
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(2)' Significant changes in the transient or accident 1
analysis as described in the Safety' Analysis Report.:
I1 L 6.7~ Records - Record's of facility operations in the form of logs, data sheets or other shitable 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
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(a) Normal reactor facility operation.
(b) Principal maintenance operations.
(c) Reportable occurrences. -
' (d) -Surveillance activities required by the Technical Specifications. -
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(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 chankes in operating procedures. .
, (1) ' 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 per-sonnel: Records of the most recent complete cycle shall be
, maintained at all tim &s the individual is employed.
6.7.3 Records to be Retained for the Lifetime of the Reactor Facility.
- (a) ' Gaseous and li' quid radioactive effluents released to the 4
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s A.wicin Nztion21 bindsrd ANS'11ANS-15.11982 5.4 Fissionable Material Storage. Fuel in- tor facility operation (i.e., Facility Director or cluding fueled experiments and fuel devices nA Administrator).
In the reactor shall be stored in a geometrical (3) Level 3 - Individual responsible for day-array where keft is no greater than 0.9 for all to-day operation or shift (i.e., Reactor or Shift i
conditions of modcration and reflection using Supervisor).
light water.
(4; Level 4 -Operating Staff (Class A and B React.or Operators and trainees). As indicated in
& h .d.strative Controls Figure 1, the review and audit group shall report to Level 1. Radiation safety personnel shall report to Level 2 or higher.
Administrative contrals are those organiza*
tional and procedural requirements which are 6.1.2 Responsibility. Responsibility for the established by chartering / licensing agencies and safe operation of the reactor facility shall be facility management. with the chain of command established in Figure 1. Individuals at the various manage-ment levels, in addition to having responsibility 6.1 Organization. Functions, assignments, re- for the policies and operation of the reactor sponsibilities, and the associated training and facility, shall be responsible for safeguarding requalification requirements, where applicable, the public and facility personnel from undue shall be specified.
radiation exposures and for adhering to all re-6.1.1 Structure. The organization for the quirements of the operating license or charter management and operation of the reactor fa- and technical specifications.
cility shall include the structure indicated in Figure 1 except that Level 3 is conditional and is in allinstances responsibilities of one 1evel may ;
intended for facilities with routine multi-shift be assumed by designated alternates or by operations. Other organizational levels / staffing higher levels, conditional upon appropriate may be added to meet spc< !!ic facility needs. Ad- qualifications.
ditional description of levels follows:
(1) Level 1 Individual responsible for the 6.1.3 Staffing (1) The minimum staffing when the reactor g
reactor facility's licenses or charter (i.e., Unit or is not secured shall be:
Organizational IIcad). a. A certified reactor operator in the con-(2) Level 2 - Individual responsible for reac- trol room.
1 Level 1 Unit or Organization llead I
Level 2 !
h Facility Director or Administrator lleview l i
Audit I
fladiation Safety 3
Iterm er er Shift Supervisor I
Level 4 Operating Staff Class A and B Operators Fig.1 Organization Chart Titles are given as examples only.
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,, as
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- Amer!can National Standard ANSI /ANS 15.1 1982 l y b. A second person present at the facility established to advise management. The tyco
)
Q complex able to carry out prescribed written functions may be performed by a single group or
- Instructions. The instructions may, for more , separate groupc. The following information i
. complex and higher power reactors, require ini- shall be shown:
, tlating the first stages of the emergency plan 6.2.1 Composition and Qualifications. The including evacuation and initial notification pro- review and audit group shall be compooed of a c:dures. Unexpected absence for as lang as two minimum of three members if a single group is hours to accommodate a personal emergency used. If separate groups are used, then there may be acceptabio provided immediate action is shall be a minimum of three persons for review taken to obtain a replacement, and one fer auditing,
- c. A designated Class A Reactor Operator shall be readily ' available on call. The members shall collectively represent a "Readily Available on Call" means an in. broad spectrum of expertise in the appropriate dividual who (1) has been specifically designated reaccor technology. Members and alternates
. and the designation known to the operator on shall be appointed by and report to Level 1 duty, (2) keeps the operator on duty informed of management. Individuals may be either from where he may be rapidly contacted and the within or outside the operating organization.
phone number and (3)is capable of getting to the Qualified and approved alternates may serve in reactor facility within a reasonable time under the absence of regular members. i normal conditions (e.g., 30 minutes or within a 6.2.2 Charter and Rules.The review and audit f 15 mile radius).
functions shall be conducted in accordance with
- d. A member of the operating shift may an established charter or directive including pro-be required for more complex and higher power vision for:
reactors, to be designated by facility manage. (1) Meeting frequency - not less than once
. ment as knowledgeable in radiation control pro- per calendar year and more frequently as cir-cedures.
cumstances warrant, consistent with effective 3 12) A list of reactor facility personnel by monitoring of facility activities 4
name and telephone number shall be readily (2) Quorums - not less than one-half of the available in the control room for use by the membership where the operating staff does not operator. The list shallinclude: constitute a majority
- a. Management personnel (3) Use of subgroups
- b. Radiation safety personnel (4) Dissemination, review, and approval of
- c. Other operations personnel. minutes in a timely manner.
(3) Events requiring the direction of Class 6.2.3 Review Function. The following items A Reactor Operator: shall be reviewed:
- a. All fuel or cor. trol. rod relocations (1) Determinations that proposed changes within the reactor core region in equipment, systems, test, experiments, or
- b. Relocation or any in core experiment procedures do not involve an unreviewed safety
,, with a reactivity worth greater than one dollar question
- c. Recovery from unplanned or un. (2) All new procedures and major revisions a
scheduled shutdown (in this instance, thereto having safety significance, proposed documented verbal concurrence from Class A changes in reactor facility equipment, or Operator is required). systems having safety significance 6.1.4 Selection and Training of Personnel. (3) All new experiments or classes of ex-The selection,L training, and requnlification of periments that could affect reactivity or result operutions personnel shall meet or exceed the re. In the release of radioactivity
. quirements of American National Standard for (4) Proposed changes in technical specifica-
- Selection and Training of Personnel for ~
tions, license, or charter
' Research Reactors, ANSI /MS-15.4-1977, Sec. (5) Violations of technical specifications, l
- tions 4-6. [2] license, or charter. Violations of internal po-cedures or instructions having safety 6.2 Review and Audit. A method for the in- dgnificance dependent review and audit of the safety (6) Operating abnormalities having safety
- aspects of reactor facility operations shall be significance 9
o ___ i
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(!nericin National Sund:rd ANSilANS 15.11982 l
(7) Reportable occurrences listed in 6.6.2 of procedures or divided r.mong vNous manuals (8) Audit reports. or procedures. 3 ;
(1) Startup, operation, and shutdown of the ;
A written report or minutes of the findings and reactor recommendations of the review group shall be (2) Fuel loading, unloading, and movement id nitted to Level 1 and the review and audit within the reactor group members in a timely :nanner after the (3) lloutine maintenance of major com-review has been completed. ponents of systems that could have an effect on 6.2.4 Audit Function.The audit function shall reactor safety incha.ie selective (but comprehensive) examina-(4) Surveillance tests and calibrations re-tion of operating records, logs, and other quired by the technical specifications or those documente. Discussions with cognizant person- that may have an effect. on reactor safety nel and obervation of operations should also be (5) Personnel radiation protect. ion, consistent used as appropriate. In no case shall the in- with applicable regulations dividual immediately responsible for the area, (6) Administrative controls for operations audit in that area. The followi ig items shall be nnd maintenance and for the conduct of irradia-audited: tions and experiments that could affect reactor (1) Facility operations for conformance to safety or core reactivity I the t.echnical specifications and applicable (7) Implementation of required plans such as license or charter conditions, at least once per emergency or security plans.
calcadar year (interval between audits not to ex-ceed 15 months) Substantive changes to the above procedures (2) The retraining and requalificati m pro. shall be made effective only after documented gram fu the eperating staff, at least once every review by the review group and approval by other calendar year (interve) between audits not Level 2 or designated alternates. Minor to exceed 30 months) modifications to the original procedures which (3) The results of act. ion taken to correct do not change their originalintent may be made those deficiencies that may occur in the reactor facility (quipment, systems, structures, or by Level 3 or higher but the modifications must be approved by Level 2 or designated alternates h
met. hods of operations that affect reactor safety, within 14 days. Temporary deviations from the at least once per calendar year (interval between procedures may be made by the responsible audits not to exceol 15 months) Class A operator or higher individual present,in (4) The ieactor facility emergency plan, and order to deal with special or unusual cir-Implementing procedures at least oce every cumstances or conditions. Such deviations shall other calendar year iinter ' betweer audits not be documented and reported to Level 2 or t.o exceed 30 months). designated alternates.
.. . 6.4 Experiments Iteview and Approval. Approved Deficiencies uncovered that affect reactor safety experiments shall be carried out in accordance shall immediately be reported to Level I
, with established and approved procedures. The management. A written report of the findings of following provisions shall be stated:
the aud!t shall be submitted to Level 1 manage-(1) All new experiments or class of ex- -
ment ard the review and audit group members periments shall be reviewed by the review group withm three months after the audit has been (6.2.3) and approved in writing by Level 2 or completed.
designated alternates prior to initiation -
6.3 Procedures. Written procedures shall be (2) Substantive changes to previously ap-prepared, .eviewed and approved prior to ini- P' .ved exp riments shall be made only after tiating any of the activities listed in this section. '*".iew by the review group and approved m The procedures shall be reviewed by the review "'.2tmg by Level 2 or designated alternates.
Mmor changes that do not sigmficantly alter gro' up, (see G.2.3) and approsed by Level 2 the experiment may be approved by Level 3 or management or designated alternates and such higher.
reviews and approvals shall be documented in a timely manner. Several of the following ac-tivities may be included in a single manual or set 6.5 Itequired Actions. Actions relating t.o the following types of events shall be listed:
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