ML20214K823

Proposed Tech Specs for Change to possession-only License

ML20214K823
Person / Time
Site:	05000148
Issue date:	11/30/1986
From:	KANSAS, UNIV. OF, LAWRENCE, KS
To:
Shared Package
ML20214K803	List: ML20214K802 ML20214K823
References
NUDOCS 8612020479
Download: ML20214K823 (12)

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APPENDIX A Technical Specifications for the Nuclear Reactor.

Facility License R-78 The University of Kansas l Department of Chemical-and Petroleum Engineering l~ Lawrence, Kansas March, 1980 Revised November, 1986 LY 9612020479$h$48 PDR ADOCK PDR4 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 System . . . . . . . . . . . . . . . . . . . . . . . . .2 4.2. Reactor Area . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5.0 Design Features. . . . . . . . . . . . . . . . . . . . . . . . . . 3 5.1 Reactor . . . . . . . . . . . . . . . . . . . . . . . . . . . .3 6.0 Administrative Controls . . . . . . . . . . . . . . . . . . . . . . 3 6.1 Or ga ni za t i on . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.2- Pro ce d ur es . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1

6.3 Required Actions. .. . . . . . . . . . . . .. . . . . . . . .7 i 6.4 Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . .7 6.5 Records . . . . . . . . . . . . . . . . . . . . . . . . . . . .9 7.0 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

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~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.

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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. Obj ective . 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. ,A_pplicab ility. 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 including the top of the reactor tank shall be made semiannually.

d. Bases. ' Monitoring is performed.to. insure that ALARA will bc-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 fReactor

'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 administration.

Level 2: Individual responsible for the reactor facility maintenance. The Nuclear Reactor Committee shall report to Level 1.

6.1.2 Responsibility Responsibility for the safe maintenance of the reactor f acility shall be_ within the chain of command shown in Figura 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 operating license and technical specifications. In all instances responsibility of one level may

' be assumed by designating alternates or by higher levels, conditional upon appropriate qualifications.

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4 Chancellor 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 l Level 1{ l

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Level 2l Radiation Safety ---

Committee on -

Reactor Officer Radiation Sources Committee

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Radiation \-

Reector Safety Service Director Figure 1. Organization Structure a

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~6.113 Nuclear Reactor Committee 6.1 3 1: 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 includeLthe Reactor Director and Radiation Safety Officer.

Qualified and approved alternates may serve in the absence of regular members.

6.1 3.2 Training for Reactor Director and 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. t 6.1.3.3 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.

6.1.4 Review and Audit The independent review and audit of facility operations shall be performed by a qualified person designated by the Nuclear Reactor Committee.

6.1.4.1 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.

b. All new procedures and major revisions thereto having safety significance, proposed changes in reactor facility equipment, 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.

6.1.4.2 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 or 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 af ter 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 documented. 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 changesLto the abcVe 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 1which 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,

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 information:

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 timesiof significant exposures. (above 500' mrem).

e.- Reportable occurrences.  ;

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6.4.2 Special Reports ~r Special reports which 'may be requ' ired by the 'NRC shall be I submitted within the time period specified for each report.

16.4.3 Reportable Occurrences 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 Follcwup 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 radioactivity to the environment.

(2) Unanticipated 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) Significant changes in the transient or accident analysis as described in the Hazards Summary Report.

r 6.5 Records :j 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 or for the Life of the Component Involved whichever is Smaller

a. Normal reactor facility operations (including scheduled and unscheduled shutdowns).

b. Principal maintenance operations.

c. Reportable occurrences.

a. 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,

i. Rec 3rds 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,1959)

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)