ML20210P104
| ML20210P104 | |
| Person / Time | |
|---|---|
| Site: | 05000148 |
| Issue date: | 01/28/1987 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210P070 | List: |
| References | |
| R-078-A-015, R-78-A-15, NUDOCS 8702130298 | |
| Download: ML20210P104 (16) | |
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UNITED STATES
.[t %,j NUCLEAR REGULATORY COMMISSION ,
,. wasHWGTON, D. C. 20666 ,
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-THE UNIVERSITY OF KANSAS 'l DOCKET NO. 50-148
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 15 License No. R-78 '
- 1. The Nuclear Regulatory Commission (the Comission) has fo'und that:
A. The application for amendment to Facility Operating License No. R-78 filed by The University of Kansas (the licensee) dated September 23, 1986, as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. . Construction of the facility was completed in substantial con-formance with Construction Permit No. CPRR-52 dated April 7, 1960, the provisions of the Act, and the rules and regulations of the Commission; C. The facility will be maintained in conformity with the amended license, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (1) that the activities authorized by this amended license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;
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E.~ T5e"iicenseeistechnicallyandfinanciallyqualifiedtoengage in the activities authorized by this amended license in accord-ance with the rules and regulations of the Commission; F. The licensee is a nonprofit educational institution and has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this amended license will not be inimical to the common defense and security or to the health and safety of the public; H. The issuance of this license is in accordance with 10 CFR Part 51
, of the Comission's regulations and all applicable requirements have been satisfied; and 8702130298 870128 PDR ADOCK 05000148 P PDR
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. I. Publication of notice of this amended license is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
- 2. Accordingly, Facility Operating License No. R-78 is hereby amended in its entirety to read as follows:
A. This amended license applies to the light water-moderated and -cooled pool-type nuclear reactor (herein the facility or the reactor) which is owned by the University of Kansas and located on the University's campus in Lawrence, Kansas, and described in the University's application for license dated March 4, 1980, as supplemented.
B. Subject to the conditions and requirements incorporated herein, ,
the Commission hereby licenses The University of Kansas:
(1) Pursuant to Section 104c of the Act and 10 CFR Part 50,
" Domestic Licensing of Production and Utilization Facilities," to possess, but not to operate, the facility at the designated location in Lawrence, Kansas, in accordance with the procedures and limitations set forth in this license.
(2) Pursuant to the Act and 10 CFR Part 30 " Rules of General Applicability to Domestic Licensing of Byproduct Material,"
to possess, but not to separate, such byproduct materials as may have been produced by operation of the reactor.
, C. This license shall be deemed to contain and is subject to the conditions specified in Parts 20, 30, 50, 51, and 73 of 10 CFR Chapter I, to all applicable provisions of the Act, and to the rules, regulations and orders of the Commission now or hereafter in effect and to the additional conditions specified below:
(1) Operation The ifcensee shall not operate the reactor nor install fuel or experiments within the reactor core or core area.
(2) _ Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 15, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with the Technical Specifications.
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- 3. Yhis amended license is effective as of ~lts date of issuance and shall expire at midnight, April 7,1990.
1 FOR THE NUCLEAR REGULATORY COMMISSION s
i t FrankJhMirag a Director.
Division of PWR Licensing-B s
Office of Nuclear Reactor Regulation
Enclosure:
Appendit A Technical
- Specifications '
s Date of Issuance: January 28, 1987 s-4 L'
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ATTACHMENT TO LICENSE AMENDMENT NO. 15 FACILITY OPERATING LICENSE R-78 DOCKET NO. 50-148 Revise Appendix A Technical Specifications as follows:
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APPENDIX A I
! Technical Specifications ,
, for the Nuclear Reactor
. Facility License P-78 t
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- The University of Kansas j .- Department ,of Chemical'and Petroleum Engineering t Lawrence, Kansas January 1987 P
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TECHNICAL SPECIFICATIONS TABLE OF CONTENTS Page 1.0 Definitions. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 Safety Limits and Limiting Safety System Settings. . . . .. . . . .2 30 Limiting Conditions for operation. . . . . .. .. . . . . . . . . .2 4.0 Surveillance Requirements. . . . . . . . . . . . . . . . .. . . . .2 4.1 Safety Systen . . . . . . . . .. . . ..... . . .. .- . . .2.
4.2 Reactoa Area. . . . . . . . . . . . . . . . . . . ... . . . .2-30 Design Features. . . . . . . . . . . . . . . . . . . . . . . . . . 3 5.'1 Reactor ...........................3
-6.0 ' Administrative Controls. . . . . . . . . . . . . . . . . . . ... . 3 6.1 Or ga n i za t i o n . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.2 Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . 6 ,
6.3 Required Actions. . . . . . . . . . . . . . . . . . . . . . . 7 6.0 Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 6.5 Records . . . . . . . . . . . . . . . . . . ... . . . . . . . 9 e %
7.0 References . . . . . ......................10
1.0 DEFINITIONS Channel. A channel is the combination of sensor, line, amplifier, and output devices which are connected for the purpose of measuring the value of a parameter.
Channel calibration. A channel calibration is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall'be deemed to include a channel test.
Channel check. A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include comparison of the channel with other independent channels or systems measuring.the same variable.
Channel test. A channel test is the introduction of a signal into the channel for verification that it is operable.
Measured value. The measured value is the value of a parameter as it appears on the output of a channel.
Operable. Operable means a component or system is capable of performing its intended function.
Operating. Operating means a component or system is performing its intended function.
Reactor secured. The reactor is secured when 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. It is the present status of the reactor. ,
Shall, should, and may. The word "shall" is used to denote a requirement; the word "should" to denote a recommendation; and the word "may" to denote permission, neither a requirement nor a recommendation.
Surveillance intervals. Allowable surveillance intervals shall not exceed the following:
- a. Five year (interval not to exceed six years)
- b. Two year (interval not to exceed two and one-half years)
- c. Annual (interval not to exceed 15 months)
- d. Semiannual (interval not to exceed seven and one-half months)
- e. Quarterly (interval not to exceed four months)
True value. The true value is the actual value of a parameter.
2.0 SAFETY LIMITS AND ~ LIMITING SAFETY SYSTEM SETTINGS Not applicable. The reactor shall remain secured.
3.0 LIMITING CONDITIONS FOR OPERATION Not applicable. The reactor shall remain secured.
4.0 SURVEILLANCE REQUIREMENTS Actions specified in this section are required to be performed during the specified surveillance period.
4.1 Safety System
- a. Applicability. This specification applies to the surveillance -
requirements of the reactor safety system.
b., Objective. The objective is to assure that the reactor safety system is operable.
'c . Specification.
- 1. A channel check of the portable radiation survey instruments shall be performed semiannually.
- 2. The portable radiation survey instruments shall be calibrated annually.
- d. Bases. The periodic surveillance and calibration of the radiation survey instrumentation will assure that the radiation survey equipment is operable.
4.2 Reactor Area
- a. Applicability. This specification applies to surveillance requirements for the reactor area.
- b. Objective. To assure the radiation safety of the reactor area.
- c. Specifications
- 1. The operational condition of the fire alarm shall be tested on an annual basis.
- 2. The physical barriers (locks on doors, thermal column, beam ports, and tank cover) shall be inspected quarterly.
3 A radiation survey of the reactor area includinE the top of the reactor tank shall be made semiannually.
- d. Bases. Monitoring is performed to insure that ALARA will be achieved such that any member of the public or staff would receive below the radiation exposure limits specified in 10 CFR 20.
5.0 DESIGN FEATURES 5.1 Reactor The reactor is described in the Safety Evaluation Report dated May, 1984 (NUREG-1051). -
The reactor has been modified by removing the fuel so as to render the reactor incapable of achieving criticality. The control rods, the bottom' grid plate assembly, and the neutron detection chambers have been removed from the tank. The tank has been drained and a cover locked to the tank top to prevent unauthorized access. All ion ,
exchange resin has been disposed of. The control console has been
.. disconnected from the reactor. The graphite thermal column and four beam ports are locked to prevent unauthorized access.
6.0 ADMINISTRATIVE CONTROLS 6.1 Organization 6.1.1 Structure The organization for the management and maintenance of the reactor facility shall be as a minimum the structure shown in Figure 1.
Job titles shown are for illustration only and may vary. Two levels of authority are provided, as follows:
Level 1: Individual responsible for site administratiog including licensing.
Level 2: Individual responsible for the reactor facility maintenance.
6.1. 2 Responsibility Responsibility for the safe maintenance of the reactor facility shall be within the chain of command shown in Figure 1. .
Management levels in addition to having responsibility for the policies and maintenance of the reactor facility shall be responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to all requirements of the possession-only license and. Technical S pecifications. In all instances responsibility of one level may be assumed by designating alternates or by higher levels, conditional upon appropriate qualifications for positions, such as those described in Sections 6.1.3 and 6.1.4.1.
Chancellor Level 1 Executive Vice Chancellor Vice Chancellor of Vice Chancellor of Research, Graduate Studies and Public Service Academic Affairs Director Dean Research, Health School of and Safety Engineering Nuclear Radiation Safety ---
Committee on -----
Reactor Officer Radiation Sources Committee
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Radiation \------------------------- ea$kor Safety Service Director line of responsibility
communication only Figure 1 Organization Structure
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6.1 3 Training for Radiation Safety Officer The Radiation Safety Officer heads the University-wide Radiation
. Safety Service and supervises a professional staff. This person is a qualified health physicist who maintains proficiency in -
radiation safety through constant on-the-job activity. The Radiation Safety Officer shall advise the Reactor Director about' all matters regarding radiation monitoring and radiation safety, and shall provide any special training as necessary.
6.1.4 Nuclear Reactor Committee 6.141 Composition and Qualifications The Nuclear Reactor Committee shall be composed of a minimum of 5 members. The members shall collectively provide a broad spectrum of expertise in science and engineering. Members and alternates shall be appointed by and report to the Level 1 authority. They .
may include the Reactor Director and Radiation Safety Officer.
Qualified and approved alternates may serve in the absence of {
regular members.
6.1.'4 .2 Charter and Rules The committee shall function under the following operating rules:
- a. Meetings shall be held as circumstances warrant consistent with effective monitoring of facility activities but not less ,
than annually.
- b. A quorum shall consist of not less than three.
- c. Sub-groups may be appointed to review specific items.
- d. . Minutes shall be kept.,and shall be disseminated to members and to Level 1 authority within one month"after the meeting.
6.1.5 Review and Audit
. The independent review and audit of facility operations shall be performed by a qualified person designated by the Nuclear Reactor Committee.
6.1.5 .1 Review Function The following items shall be reviewed by the Nuclear Reactor Committee or a subgroup thereof:
- a. Determinations that proposed changes in equipment, systems, tests, or procedures do not involve an unreviewed safety question.
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- b. All new procedures and major revisions thereto having safety significance, proposed changes in reactor facility equipment,
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or systems having safety significance.
.c. ' Proposed changes in technical specifications, license, or charter.
- d. Violations of technical specifications, license, or charter.
- e. Operating abnormalities having safety significance,
- f. Reportable occurrences listed in section 6.4 3
- g. Audit reports.
6.1 5 2 Audit Function The audit function shall include selective but comprehensive
. examination of records, logs, and other documents. Where necessary, discussions with responsible personnel shall take place. In no case shall the individual 'r individuals conducting the audit be immediately responsible for the area being audited.
The following items shall be audited:
- a. The conformance of facility operations to the technical specifications and applicable license or charter conditions, at least annually. .
- b. The results of actions taken to correct deficiencies occurring in facility equipment, systems, structures, or methods of operations that affect safety, at least annually.
Deficiencies uncovered that affect safety shall immediately be reported to Level 2 authority. A written report of the findings of the audit shall be submitted to the Level 2 authority and the Nuclear Reactor Committee members within 90 days after the audit has been completed.
6.2 Procedures There shall be written procedures for, and prior to, initiating any of the activities listed in this section. The procedures shall be reviewed by the Nuclear Reactor Committee and approved by Level 2 or designated alternates, and such reviews and approvals shall be docunented. Several of the following activities may be included in a single manual or set of procedures or divided among various manuals or procedures,
- a. Surveillance tests and calibrations required by the technical specifications.
- b. Personnel radiation protection, consistent with applicable regulations.
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- c. Routine maintenance of major components of systems that could have an effect on reactor safety.
Substantive changes to the above procedures shall be made only after documented review by the Nuclear Reactor Committee and approval by Level 2 or designated alternates. Minor modifications to the original procedures which do not change their original intent may be made by the Level 2 authority. . Temporary changes to the procedures that do not affect reactor safety may be made by the Reactor Director and are valid for a period of one month. Such temporary changes shall be documented and reported to the Nuclear Reactor Committee.
6.3 Required Actions 6.3.1 Action to be taken in the event of an occurrence as defined in Section 6.4.3
- a. Corrective action shall be taken to return conditions to normal..
- b. All such occurrences shall be promptly reported to the Level 2 authority or designated alternates. .
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- c. All such occurrences including action taken to prevent or reduce the probability of a recurrence shall be reviewed by the Nuclear Reactor Committee.
6.4 Reports All written reports shall be sent within the prescribed interval to the NRC, Washington, D.C. 20555. Attention: Document Control Desk, with a copy to the Regional Administrator, Region IV.
6.4.1 Operating Reports Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the appropriate NRC office within three months following the end of each prescribed year. Each annual operating report shall include the following informations
- a. Tabulation of major preventive and corrective maintenance operations having safety significance,
- b. Tabulation of major changes in the reactor facility procedures, and new tests and/or experiments significantly different from those performed previously and which are not described in the Hazards Summary Report, including conclusions that no unreviewed safety questions were involved.
- c. The results of any environmental surveys performed outside the facility.
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- d. A summary of radiation exposures received by facility personnel and visitors in any one year including the dates and times of significant exposures (above 500 mrem).
- e. Reportable occurrences.
6.4.2 special Reports Special reports which may be required by the NRC shall be subnitted within the time period specified for each report.
6.4.3 -Reportable Occurren'ces y
Reportable occurrences such as increases in radiation levels or physical degradation of the facility, including causes, probable consequences, corrective actions, and measures to prevent recurrence, shall be reported to the NRC. .
- a. Prompt Notification with Written Followup The types of events listed below shall be reported as expeditiously as possible by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of NRC Region IV or his designated representative no later than the first work day following the event, with a written followup report within two weeks. Information provided shall contain narrative material to provide complete explanation of the circumstances surrounding the event.
(1) Unanticipated releases of radicactivity to the environment.
(2) Unsnticipated exposure of personnel.
(3) An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could cause an unsafe condition ,
with regard to facility maintenance. ,
- b. Reports Within 30 Days The types of events listed below shall be reported to the Director of NRC Region IV or his designated representative within 30 days of their occurrence.
(1) Permanent changes in the facility organization structure.
(2) An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused an unsafe condition with reguards to reactor maintenance.
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6.5 Records 1 Records of the following activities shall be maintained and retained for the periods specified below. The records may be in the form of logs, data sheets, or other suitable forms. The required information may be contained in single, or multiple records, or a combination thereof.
6.5.1 Records to be Retained for a Period of at least Five Years
- a. Normal reactor facility operations (including scheduled and unscheduled shutdowns).
- 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. ~Special Nuclear Materials (SNM) inventories, receipts, and shipments.
- h. Approved changes in operating procedures.
- 1. Records of meeting and audit reports of the Nuclear Reactor Committee.
J. Sealed source leak test results.
6.5.2 Records to be Retained for Five Years or for the Lifetime of the Reactor Facility whichever is Greater (Note: Annual reports may be used where applicable as records in this section.)
- a. Gaseous and liquid radioactive effluents released to the environs.
- b. Off-site environmental monitoring surveys required by the Technical Specifications.
- c. Radiation exposure for all personnel monitored.
- d. Updated drawings of the reactor facility.
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-7.0. REFERENCES
- 1. Hazards Summary Report (July,I1959)
.2. Safety Evaluation Report (NUREG-1051) related to the renewal of
' the operating ' license for the research reactor.at the University of Kansas,. Docket No. 50-148,' U.S. Nuclear. Regulatory Commission, Office of Nuclear Reactor Regulation '(May,1984) s 4
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