ML20127J198
| ML20127J198 | |
| Person / Time | |
|---|---|
| Site: | 05000538 |
| Issue date: | 06/17/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127J189 | List: |
| References | |
| NUDOCS 8506260505 | |
| Download: ML20127J198 (23) | |
Text
'o,,
UNITED STATES NUCLEAR REGULATORY COMMISSION o
O j
WASHINGTON, D. C. 20555
~s...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 5 TO FACILITY OPERATING LICENSE NO. R-127 MEMPHIS STATE UNIVERSITY DOCKET NO. 50-538
Background
On March 15, 1985, Memphis State University (MSU) submitted an application, pursuant to 10 CFR 50.90, for a change of status from operating to possession-only for their 0.1 W AGN-201 Research and Training Reactor.
The application included descriptians of current status and proposed facility modifications, revised t2chnical specifications compatible with the possession-only status and a safety analysis of the facility modifications.
Facility Status All fuel discs, including the small fuel discs inside the control rod fuel capsules, will be removed from the reactor in the presence of an NRC licensed Senior Operator and the MSU Radiation Safety Officer. The fuel discs will be placed into their original shipping / storage containers, sealed and stored in room 010 of the facility with area radiation monitors and alarms remaining operational. Less than 200 grams of U-235 will be stored in any one container to preclude criticality. The 10 mg radium-beryllium sealed neutron source will be removed from the reactor, placed into a shield container and stored in a shipping container in the reactor room. The aluminum core tank and control rod assemblies will be removed from the reactor and stored with covers and I
gaskets in place in the reactor room.
The reactor configuration during the possession-only status will be as follows:
the thermal column tank, access port liner tubes, glory hole liner
. tube, control rod cover plate, graphite reflector cylinder, lead shielding, j
access port filler pluas and neutron detectors with interconnecting instrument cables will remain installed. The control rod cover plate will have a gasket to keep the reactor vessel sealed. The power cable to the reactor console control power circuits will be disconnected and removed. The radiation nonitor and alarm in the reactor room will remain operational.
i e O[r-W P
P
. The shield tank and thermal column tank water will be sampled for radioactivity and drained according to apornved precedures in the MSU AGN-201 Maintenance and Storage Manual.
Prior to storepp, the reactor vessel intertor including the core tank and fuel capsules will be thorouchly surveyed for residual radioactivity and loosa surfree contamination.
Surface contamination in excess of acceptable concentrations will be clearly identified and documented for future reference. The reactor rnon and control room will remain locked at all times when authorized personnel are not present.
The technical speci#icetiens and the administrative organization will be modified to reflect the possession-only status. Technicel specifications addressing performance, safety, surveillance and reporting related to reactor operation will be deleted. Technical specifications addressing fuel storace, monitoring and surveillance, staff and public safety, and related reporting requirements will be retained.
Evaluation Fuel removal will be supervised and will conform with the defueling precedures approved by both the Reactor Safety Committee and the Radiation Safety Subcommittee of MSH. The fuel storage scheme provides for prevention of criticality, roectivity changes and radioactivity releases.
Removal of fuel and rod control assemblies assures that the reactor and centrol systems cannot be operated.
Removal of all liouids from the shield tank and thermal column tank will minimize long-term corrosion of tie reactor structures. As fuel is still on site, the area radiation monitors and alarms will renain operational in the reactor room and in the 'uel storage area.
Radiatier surveys will identify surface contamination levels that are greater than acceptable for unrestricted access end such areas will be properly documented and rcsted.
Restoration of the reactor vessel, core tank ano fuel capsules to their designed liquid-tipht integrity will assure contair.nent of any trace residual radioactivity. Physical barriers housing these components will not be open 'cr urrestricted access and shall remain locked at any time authorized personnel are not present. The revised technical specifications reflect the ressessinn-only status of the reactor facility and will continue to assure the health and safety of the reactor staff and the public.
Envirnerental Consideration This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in irspection and surveillance requirements. The staff has
. determined that the amendment involves no significant hazards consideration (as discussed belowl, there is no significant change in the types or signifi-cant increase in the amounts of any effluents that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this amendment meets the eligibility criteria for categ)orical exclusion set forth in 10 CFR 51.?2(c)(9).
Pursuant to 10 CFP, 51.FP(b, no environmental inpact statement or environmental assessment need be prepared in connection with the issuance of this ercrdnent.
Conclusion Accordingly, the staff concludes that amendnent o# this license to a possession-only status is appropriate. We have further concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a sianificant increase in the probability or consequences of accidents previously evaluated, does not create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a safety maroin, the amendment does notinvolve.asignificanthazardsconsideration,(2)thereisreasonable assurance that the hea1th and safety of the public will not be endangered by the proposed activities, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the the health and safety of the public.
Principal Contributor: Angela Chu Dated: May 23, 1985
(
l l
l
ATTACHMENT TO LICENSE AMENDMENT NO. 5 FACILITY LICENSE NO. R-127 DOCKET NO. 50-538 Revised Appendix A technical specifications are as follows:
Remove Pages Insert Pages All pages New pages I
i l
i
,,-v----
-,,,--,--------.n,,,
,,,,,y a-vn-,m,-,
.,,,,, +
4y-
-. - - -wm,
, - - - - - - - - ~
m-,
= _ _
J APPENDIX A LICENSE NO. R-127 TECHNICAL SPECIFICATIONS FOR MEMPHIS STATE UNIVERSITY AGN-201 (SERIAL 108)
DOCKET NO. 50-538 DATE: MAY 1985 4
e I.
6 l
i i
TABLE OF CONTENTS PAGE 1.0 DEFINITIONS.........................................
1 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS..'.
2
~
~
3.0 LIMITING CONDITIONS FOR OPERATION...................
3 4.0 SURVEILLANCE REQUIREMENTS...........................
3 4.1 Facility Support and Protection System..........
3 5.0 D ES I Gt.' F E ATUP ES.....................................
4 5.1 Mothball Status.................................
4 5. 2 Fu e l S to ra ge....................................
5 6.0 ADMINISTRATIVE CONTR0LS.............................
6 6.1 Organization, Responsibilities and Authority....
6 6.1.1 President.................................
6
~ 6.1.2 Vice President for Advancement and Continuing Education................
7 6.1.3 Radiation Safety Subcommittee.............
7 6.1.4 Radiation Sa fe ty Officer..................
8 6.1.5 Director, Security, and Safety Services...
8 6.2 Radiation Safety Subcommittee Meetings, Reviews, Audits, and Records..................
9 6.2.1 Qualifications............................
9 6.2.2 Meetings and Quorum.......................
9 6.2.3 Reviews...................................
10 6.2.4 Audits....................................
10 6.2. 5 Records a nd Reports.......................
11 6.3 Procedures ard Procedure Approva1...............
12 6.3.1 Procedures................................
12 6.3.2 Procedure Approvals.......................
13 6.4 Reporting Requirements..........................
13 6.4.1 Annual Report.............................
13 6.4.2 Reportable Occurences.....................
13 6.4.3 Special Reports...........................
14 6.5 Record Retention................................
14 6.5.1 Mothball Status Records...................
14 6.5.2 Prior Facil i ty Opera tion..................
15 Figure 1.
Reactor Facility Organization for Possession-Only Status...............
17 c
1.0 DEFINITIONS 1.1 Measuring Channel - A measuring channel is the combination of of sensors, lines, amplifiers, and output devices which are connected for the purpose of measuring or responding to the value of a process variable.
1.2 Safety Channel - A safety channel is a measuring channel in the reactor safety systen.
1.3 Reactor Safety System - The reactor safety system is that combination of safety channels and associated circuitry which foms the automatic protective system for the reactor l
or provides infomation which requires manual protective action be initiated.
1.4 Reactor Component - A reactor component is any apparatus, device, or material that is a normal part of the reactor assembly.
1.5 Operable - Operable means a component or system is perfoming l
its intended function in its normal manner, i
l 1.6 Operating - Operating means a component or system is perfoming its intended function in its nomal manner.
l 1.7 Channel Check - A channel check is a qualitative verification of acceptaole performance by observation of channel behavior.
This verification may include comparison of the channel with other independent channels or methods measuring the same variable.
l 1.8 Channel Test - A channel test is the introduction of a signal l
{
into the channel to verify that it is operable.
I i
1
1.9 Channel Calibration - A channel calibration is an adjustment of the channel such that its output responds, within acceptable range and accuracy, to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment, actuation, alarm, or trip.
1.10 Reactor Secured - The reactor shall be considered secured when:
(1)
It contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality under optimum available conditions of moderation and reflection, or (2) No work is in progress involvino core fuel, control rods or control rod drives unless they are physically decoupled from the reactor, and (3) The console key switch is in the off position and the key is renoved from the lock.
1.11 Mothball - The reactor facility is considered to be in a mothballed condition when the facility is in a state of protective storage. The facility may be left intact except that all fissionable materials, radioactive wastes, and radioactive fluids shall be removed frcn the reactor room.
The reactor fuel shall be in storage containers and located in a remote fuel storage area in accordance with an approved fuel storage plan. Appropriate surveillance, radiation monitoring, and security procedures are established under a possession-only license to ensure that the health and safety of the public is not endangered.
2.0 SAFETY LIMITS AND LIMITING SAFFTY SYSTEM SETTINGS Not Applicable. The reactor shall remain secured and the facility shall be in mothball status.
2
t 3.0 LIMITING CONDITIONS FOR OPERATION Not Applicable. The reactor shall remain secured.and the facility shall be in mothball status.
if 4.0 SURVEILLANCE REQUIREMENTS
/
Actions specified in this section are applicable to the
' mothballed condition of the facility and shall be performed within the specified surveillance period.
4.1 Facility Support and Protection Systems Applicability l
This specification applies,to the facility support and protection systems such as, physical barriers, fire protection systems, and radiation monitoring activities.
1 l -
Objective To assure that the public health and safety are not
[
endangered as a result of physical degradation of the facility during the term of the possession-only license pericd.
l Specification a.
Physical barriers fo unauthorized entrance into the reactor facility and fuel stor' age area, e.g., building, roons, doors, and access openings, shall be visually inspected at least once each tcalendar quarter (intervals not to exceed four months).
b.
Fuel storage containers, container locking rings, and seals shall be visually. inspected at least once each calendar quarter (intervals not to exceed four months).
3
c.
A radiation survey of the reactor facility and fuel storage area shall be performed at least once each calendar quarter (intervals not to exceed four months),
d.
The reactor building fire alarm system, area fixed radiation monitors and Pierms, and reactor room smoke detector, shall be tested annually (intervals not to exceed fifteen months).
Bases The physical barriers, e.g. building, rooms doors, and access openings are inspected to assure that these barriers have not deteriorated and that locks and locking apparatus are intact.
Storage containers, container locking rings, and seals are inspected to assure it.tegrity of the containers. This inspection, in conjunction with radiation surveys of the reactor facility and fuel storage area, verifies that radioactive material has not been removed from the conteiners or is not escaping or being transported through the containment barriers.
In addition, the radiation surveys and continued operational radiation monitors and alarms provide assurance that radiation doses to facility personnel and to the public are maintained at a level below 10 CFR 20 limits.
l l
Tests of the reactor building fire alarm system, area fixed radiation monitors and alarms, and reactor room smoke detector verify that these systems are operable.
l I
[
5.0 DESIGN FEATURES 5.1 Mothball Status of the Reactor During a nothballed state of protective storage:
l 4
l, The reactor is defueiled and assembled with the Thermal a.
Column Tank, Access Port Liner Tubes, Glory Hole Liner Tube, and Rod Drive Area Cover Plate installed and
+
gasketed to maintain the design fluid-tight integrity.
'The graphite reflector cylinder, lead shielding, and access port filler plugs are in place. The Shield Tank and Thermal Column Tank are empty of fluids and dry.
b) The'defuelled aluminum core tank and safety and control rod fuel capsules are removed from the reactor assembly and are sealed to maintain design fluid-tight integrity.
c.
All fissionable material used in connection with operation of the reactor is stored in 6J drums, containing less than 200 grams of U-235 each, and is located in a designated, controlled fuel storage area in accordance with paragraph 5,2 of these technical specifications.
t d2 Fixed radiation monitors and alarms Iin the reactor room
- and fuel storage area will remain funct(anal.
5.2 Fuel Storage s
Fuel,includinofueledexpe;imentsandfu() devices,nokin the reactor sha'll be stored in locked rooms in the reactor building. The ~ storage array shall be sLc.h 'that K,ff is no greater than 0.8 for all conditions of moderation and reflection.
i 1
t 5
6.0 ADMINISTRATIVE CONTROLS 6.1 Organization, Responsibilities and Authority. Respon-sibility for protective storage of the reactor facil-ity shall be with the organization shown in Figure 1 of this section.
Individuals at the various manage-ment levels shall be responsible for safeguarding the public and facility personnel from undue radia-tion exposures and for adherence to all requirer.ents of the facility license.
Assignment of specific re-sponsibilities shall be as described in the following paragraphs.
6.1.1 President. The President of Memphis State University is the Chief Administrative Officer ultimately responsible to the Tennessee State Board of R,egents for the university and its activities. The P, resident is responsible for the reactor facility license.
- 6.1.2 Vice President for Advancement and Continuing Educa-tion. The Vice President for Advancement and Contin-uing Education is the Administrative Officer directly responsible to the President for maintenance, security and access control, administration, and safety of the reactor facility and fuel storage area. The Vice President may, in this capacity, represent the Presi-dent in matters pertaining to the facility license and, within limitations set forth by the license, have final approval authority and responsibility for decisions, policies, procedures, and events that would affect the facility, the reactor, reactor com-ponents, and reactor fuel. The Vice President for 5
Advancement and Continuing Education shall be respon-sible for official communications concerning the reactor facility and fuel storage area including all required reports and retention of facility records.
6
1 The Vice President for Advancement and Continuing Ed-ucation shall be advised by the Radiation Safety Sub-committee in all facility matters involving risks to personnel health and safety from ionizing radiation and shall be advised by the Director, MSU Safety and Security Services, in all matters involving physical security of the facility and reactor fuel. The Vice President may appoint personnel having the appropri-ate qualifications, as necessary, to positions re-porting directly to hiv for purposes of executing re-quirements of tne facility license and assuring safe storage of the facility.
6.1.3 Radiation Safety Subcommittee. The Radiation Safety
~
Subcommittee (RSSC) is a subcommittee of the Univer-
~
sity Standing Committee on Safety (University Safety Committee) whose members are appointed by the,Presi-dent. The RSSC is formed to administer the Radiation Safety Program for the university.
In this capacity, the RSSC shall be responsible and have approval au-thority for all procedures, policies, and activities which involve risks to the health and safety of per-sonnel from ionizing radiation. The RSSC shall advise the Vice Presidenti for Advancement and Continuing Ed-ucation in radiation control and safety matters re-I lated to the reactor facility and fuel storage area and shall be informed by the Office of the Vice Pres-ident of the status and locations of radioactive j
materials and of any activities involving personnel exposure to ionizing radiation within these facili-l ties.
l The Radiation Safety Subcommittee shall hold meetings and shall be responsible for independent reviews and l
audits of surveillance and maintenance activities in-ciuding radiation surveys. Based upon these reviews and audits, the RSSC shall make appropriate recommen-l 7
dations to the Vice President for Advancement and Continuing Education to assure that the state of the f acility does not endanger the health and safety of the public.
6.1.4 Radiation Safety Officer. The Radiation Safety Offi-cer (RS0) is a member of the Radiation Sa'fety -Subcom-mittee and is empowered to enforce regulations and regulatory procedures established by the university, federal agencies, and state agencies for the control of radioactive materials and protection of personnel f roa ionizing radiation. The RS0 shall be responsible for the performance of radiation surveys and shall maintain survey records in connection with the reac-tor facility and fuel storage area.
In addition to routine surveillance activities delineated in these Technical Specifications, the RSO shall maintain ma-terials inventory records and records of persynnel exposures to ionizing radiation. The R50 shall inform the Vice President for Advancement and Continuing Ed-ucation, in writing, of surveillance and in=pection results within 14 days of canpleting such activities.
The Radiation Safety Officer shall be responsible for and shall supervis'e activities involving the movement of radioactive materials within the facility and/or the packaging and shipment of radioactive materials off-campus. The RSO shall be directly responsible for the proper identification and posting of re-stricted areas within the reactor facility and fuel storage area.
6.1.5 Director, Security and Safety Services. The Director of Security and Safety Services is the management of-ficial directly responsible for the physical security of university property and the enforcement of univer-sity security and safety regulations on the MSU South 8
c Campus.
In this capacity, the Director of Security and Safety Services shall provide the services and trained security officers necessary to implement the facility security plan approved as psft of this li-cense to asgure protective storage of the reactor and fuel. He shall advise the Vice President for Idvance-ment and Continuing Education in matters involving physical security and access control of the reactor f acility and fuel storage area and shall be informed of personnel authorized for access by the Office of tne Vice President.
6.2 Radiation Safety Subcommittee Meetings, Reviews, Audits, and Records
~
6.2.1 Qualifications. The Radiation Safety Subcommjttee is established as a subcommittee of the University Safety Committee. Members of the University Safety Committee are appointed by the President. The Subcommittee is appointed by the Chairperson of the University Safety Committee and includes a chairperson, the University Safety Director, the Radiation Safety Officer and several members selected on the basis of their exper-tise in radiation safety and related matters. The Subcommittee is empowered to meet and keep minutes independently of the University Safety Canmittee and with the authority to administer the university's radiation safety program.
6.2.2 Meetings and Quorum. The Radiation Safety Subcommit-tee shall meet as necessary but at least once each calendar quarter (intervals not to exceed four months). A quorum for review and approval functions shall consist of the chairperson, or designated al-ternate, and two other members.
r t
L 9
L
6.2.3 Reviews. The Radiation Safety Subcommittee shall review:
a.
All procedures and major revisions thereto per-taining to the reactor facility and fuel storage area and which have radiological safety signifi-
~
cance, or include changes to facility equipment or systems, or affect authorized personnel access to the facility.
b.
Proposed changes to the facility license, techni-cal specifications, or charter.
c.
Violations of the license, technical specifica-tions, or charter.
d.
Reportable occurrences listed in 6.4.
e.
Abnormalities in, or deviations from, the normal and expected status of facility equipment and protective barriers.
6.2.4 Audits. The Radiation Safety Subcommittee shall con-duct audits that include _ selective (but comprehensive) examination of fac'ility and fuel storage area records, logs, and other documents. Discussions with cognizant personnel and observation of activities ~should also be conducted as appropriate.
In no case shall the individual immediately responsible for an area per-form the audit in that area. The following items r
shall be audited:
a.
Facility surveillance, and maintenance for confonnance to the Technical Specifications and applicable license conditions, at least once per calendar year (intervals between audits not to exceed fifteen months).
10 l
b.
The results of actions taken to correct deficien-cies that may occur in reactor facility and fuel storage area equipment, systems, structures, and radioactive materials storage containers, at least once per calendar year (intervals between audits not to exceed fif teen months),
c.
The reactor facility and fuel storage area secu-rity plan and implementing procedures, at least once every other calendar year (intervals between audits not to exceed 30 months).
d.
The reactor facility and fuel storage area emer-gency plan and implementing procedures, at least once every other calendar year (intervals between audits not to exceed 30 months).
6.2.5 Records and Reports. The Chairperson of the Radia-tion Safety Subcommittee shall ensure that records of the committee's activities are prepared, distributed, and retained as follows:
a.
Minutes of each Radiation Safety Subcommittee meeting shall 'be prepared and retained on file in the University Radiation Safety Office. A copy of these minutes shall be forwarded to the Vice President for Advancement and Continuing Educa-tion within 30 days following each meeting.
b.
A written report or minutes of the findings and recommendations of each review group shall be prepared and submitted to the Vice President for Advancement and Continuing Education and all Radiation Safety Subcommittee Members in a timely manner af ter the review has been completed. A copy of each report shall be retained on file in the University Radiation Safety Office.
l 11 i
c.
Deficiencies uncovered that affect radiation safety or protective storage of tne reactor or reactor fuel shall be immediately reported to the Vice President for Advancement and Continuing Ed-ucation. A written report of the--findings of each audit shall be submitted to the Vice President
~
and all Radiation Safety Subcommittee Members within three months after the audit has been con-pleted. A copy of all audit reports shall be re-tained on file in the University Radiation Safety
- Office, d.
Tne Cnairperson of the Radiation Safety Subcom-mittee shall submit an annual report to the Pres-ident prior to March 31, of each calendar year.
The report shall contain an assessment of the fa-cility's suitability for continued protective storage of radioactive materials, includi,ng the reactor fuel, and any appropriate recommendations.
Copies of this report shall be submitted to the Vice President for Advancement and Continuing Ed-ucation and retained on file in the University Radiation Safety Office.
6.3 Procedures and Pro'cedure Approvals.
6.3.1 Procedures. There shall be written procedures for the following.
a.
Surveillance and testing of equipment and systems required for protective storage of the reactor and reactor fuel.
b.
Personnel radiation protection consistent with 10 CFR 20.
c.
Access control to the reactor facility and fuel storage area.
/
12
d.
Implementation of the security plan and emergency plan.
e.
Notification of the proper authorities in the event of unauthorized entries of personnel into the facility and significant changes.in the radi-ation or contamination levels within the facility.
6.3.2 Procedure Approvals. The Vice President for Advance-ment and Continuing Education shall have final ap-proval authority for all procedures in connection with the reactor facility and fuel storage area. The Radiation Safety Subcommittee shall review and have approval authority for those procedures which may in-clude risks to the health and safety to personnel from fonizing radiation in addition to those, reviews specified in 6.2.3.
The Director of Security,and Safety Services shall review and have approval authority for procedures written to implement the security plan and emergency plan.
6.4 Reporting Requirements 6.4.1 Annual Report. An annual report describing the sta-tus of the facility, the results of environmental and facility radiation surveys, an evaluation of the per-formance of security and surveillance measures, per-sonnel exposures to radiation, and any abnormal occurrences during the previous calendar year shall be submitted to the Director of Nuclear Reactor Regu-lation, ATTN: Document Control Desk, with a copy of the Regional Administrator, Region II, prior to March 31, of each calendar year.
6.4.2 Reportable Occurrences. Reportable occurrences shall be reported as expeditiously as possible by telephone and confirmed by telegraph, mailgram or facsimile transmission to the Administrator of NRC Region II, or his representative, no later than 13
tha first work' day following the event. A written followup report discribing the reportabic occurrence including causes, probable consequences, corrective actions, and measures to prevent recurrence shall be submitted within 14 days.
Information provided shall contain rarrative material for a complete explanation of circumstances surrounding the event., The following events shall be reported:
a.
Discovery of significant, unexplained increase in radiation or contamination levels within or around the reactor facility or fuel storage area.
b.
Abnormal degradation discovered in protective barriers for the reactor facility or fuel storage area which would compromise the physical security e'stablished for protective storage of the reactor and reactor fuel.
6.4.3 Special Reports. Special reports which may be required by the Fuclear Regulatory Commission shall be subriitted to the Director of Nuclear Reactor Regulation, ATTN: Document Control Desk, with a copy to the Administrator, Region II, within the time period for each report.
6.5 Records Retention.
6.5.1 Records. Records or logs relative to the following items shall be kept and retained until the license is terminated, unless otherwise specified by the NRC:
a.
Environmental surveys.
b.
Facility radiation surveys.
c.
Inspections of physical barriers.
l c.
Abnormal occurrences.
e.
Records of meetings of the Radiation Safety I
Subcomittee.
l 14 l
i
E 6.5.2 Prior Facility Operation.
6.5.2.1 Records or logs relative to the following items shall be retained for a period of at least five years:
a.
Operating logs or data which shall identify:
1.
Canpletion of pre-startup checkout, start-up, power changes, and shutdown of the re-actor.
2.
Installation or removal of fuel elements,
~
control rods, or experiments that could affect core reactivity.
3.
Installation or removal of jumpers,' special tags or notices, or other temporary changes to reactor safety circuitry.
4.
Rod worth measurements and other reactivity measurements.
b.
Principal a'intenance operations.
c.
Reportable occurrences.
l L
d.
Surveillance activities required by technical l
l specifications.
e.
Facility radiation and contamination surveys.
f.
Experiments performed with the reactor.
T.
g.
Changes to operating procedures.
e.'
15 L
6.5.2.2 Records or logs relative to the following items shall be retained for the life of the facility, unless otherwise specified by the NRC:
a.
Gaseous and liquid radioactive eff,luents re-leased to the environs.
b.
Appropriate off-site environmental monitoring surveys.
Fuelinventohiesandfueltransfers.
c.
d.
Radiation exposures for all personnel.
e.
Updated as-built drawings of the facility.
f.
Records of transient or operational cyc"les for those components designed for a limited number of transients or cycles.
g.
Records of training and geslifications for mem-bers of the facility staff, h.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
1.
Records of meetings of the Reactor Safety Com-mittee.
D e
9 9
e 16 i.--
PRESIDENT MEMPHIS STATE UNIVERSITY I
I':!-T!3N SAFETY VICE PRESIDENT DIRECTOR
..i:0MITTEE AD',' ANCEME.T AND SECURITY AND CONTINUING EDUCATION SAFETY SERVICES RADIATION SAFETY REACTOR FACILITY SOUTH CA" PUS OFFICER AND
~ SECURITY FUEL ST;;', AGE ARE A 0FFICERS Direct Line of Authority
Advi so ry/ Assistance Capaci ty FIGURE 1.
REACTOR FACILITY ORGANIZATION F0k " POSSESSION-ONLY" STATUS e
D 17
_