ML20214S631

Proposed Tech Specs,Changing Status of Facility to possession-only

ML20214S631
Person / Time
Site:	05000148
Issue date:	09/30/1986
From:	KANSAS, UNIV. OF, LAWRENCE, KS
To:
Shared Package
ML20214S617	List: ML20214S614 ML20214S618 ML20214S631
References
NUDOCS 8609300046
Download: ML20214S631 (11)

Text

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l PROPOSED APPENDIX A Technical Specifications for the Nuclear Reactor Facility License R-78 The University of Kansas Department of Chemical and Petroleum Engineering Lawrence, Kansas March, 1980 Revised September,1986 8609300046 860923 PDR ADOCK 05000143 P POR L

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1.0 DEFINITIONS Calibration - A calibration is a measurement of a known value or values of a parameter such that the measured value can be correlated within acceptable range and accuracy to true values of the parameter. Calibration shall encompass the entire measuring system.

Measured Value - The Measured Value of a parameter is as it appears on the output of a measuring channel.

Measuring System - A Measuring System is the combination of sensor, lines, amplifiers, and output devices which' are connected for the purpose of measuring the value of a parameter.

Operable - Operable means a component or system is capable of performing its intended function in its normal manner as demonstrated by continued normal functioning and satisfactory completion of checks, tests, calibrations according to the specified schedule.

Operating - Operating means a component or system is performing its intended function in its normal manner.

Reportable Occurrence - A Reportable Occurrence is any of those conditions described in Section 5.4.3 of this specification.

Shall, Should and May - Shall is used to require an action, should is used to recommend an action and may is used to permit an action.

True Value - The True Value of a parameter is its actual value at any instant.

2.0- LIMITING CONDITIONS 2.1 Radiation Monitoring

a. Applicability - This specification applies to the portable monitoring equipment used for measuring the radiation fields at the top of the reactor tank produced by in situ activation 1

products and from any remaining reactor components with activation products.

b. Objective - The objective of this specification is to assure exposure as low as reasonably achievable (ALARA).

c. Specification - The top of the reactor tank shall be checked at least once a year to determine the dose rates and the decrease in activity.

.d. Bases - The reactor cannot be operated; hence there are no limiting operating conditions. Monitoring is performed to insure that ALARA will be achieved such that any member of the public would receive a fraction of the radiation exposure specified in 10 CFR 20.

3.0 REACTOR DESIGN FEATURES All nuclear fuel has been removed and shipped to DOE facilities. The only special nuclear material remaining on site is 1 gram of uranium 235 in a fission chamber and 32 grams of plutonium contained in two plutonium-beryllium neutron sources.

The reactor tank has been drained and a cover bolted to the tank top t to prevent accidental entry.

All ion exchange resin has been disposed of.

f The control console has been disassembled.

! The graphite thermal column and four beam ports remain in place but

are locked to prevent unauthorized entry.

4.0 SURVEILLANCE REQUIREMENTS I

l 4.1 Radiation Monitoring Equipment

a. Applicability - This specification applies to the calibration of i

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the portable survey instruments used to perform radiation surveys at the top of the reactor tank and any remaining reactor components with activation products.

b. Objective - The objective is to assure proper calibrations of the portable survey instruments.

c. Specification - If instruments to be used in surveillance testing have not been calibrated within 7 months of the annual testing date, they shall be calibrated prior to use. Instruments shall be checked for proper operation before each use.

d. Bases - Operating experience indicates the need for routine calibration of instruments and for operational checks prior to each use. The requirements listed above generally prescribe tests or inspections to verify periodically that the performance of the radiation monitoring is in accordance with specifications given.

The interval between annual tests is not to exceed 14 months.

5.0 ADMINISTRATIVE CONTROLS 5.1 Organization 5.1.1 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 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 licence.

The Nuclear Reactor Committee shall report to Level 1.

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Chancellor Executive Vice Chancellor I

I L Vice Chancellor of Vice Chancellor Research, Graduate Studies of and Public Service Academic Affairs Director, Research Dean Health and Safety School of Engineering i

Level 1 I

t Level 2 Radiation Safety Committee on ___________7 Reactor C,__, Radiation Sources e Committee Officer

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Radiation Reactor Director Safety Service d

Figure 1. Organization Structure 4

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5.1.2 Responsibility Responsibility for the safe maintenance of the reactor facility shall te 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 operating license and technical specifica-tions. In all instances responsibilities of one level may be assumed by designated alternates or by higher levels, conditional upon appropriate qualifications.

5.1.3 Nuclear Reactor Committee 5.1.3.1 Composition and Qualifications The Nuclear Reactor Committee shall be composed of a minimum of 3 members. The members shall collectively provide a broad spectrum of expertise in science and engineering. Members and alternates shall be i

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.

5.1.3.2 Charter and Rules The committee shall function under the following operating rules:

a. Meetings shall be held not less than annually or more frequently

.as circumstances warrant consistent with effective monitoring of facility activities.

b. A quorum shall consist of not less than two.

c. Sub groups may be appointed to review specific items.

d. Minutes shall be kept, and shall be disseminated to members and to the Level 1 authority within one month after the meeting.

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I 5.1.4 Review and Audit The independent review and audit of facility operations shall be performed by a qualified person designated by the Nuclear Reactor Committee.

5.1.4.1 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 there to 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.

Violations of internal procedures or instructions having safety significance.

e. Operating abnormalities having safety significance.

f. Reportable occurrences listed in section 5.4.3.

4 5.1.4.2 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. The following. items shall be audited:

a. The conformance of facility operations to the technical specifications and applicable license or charter conditions, at least once per calendar year (interval not to exceed 15 months).

b. The results of actions taken to correct deficiencies occurring in facility equipment,- systems, structures, or methods of operations 6

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that affect safety, at least once per year (interval not to exceed 15 months).

Deficiencies uncovered that affect safety shall immediately be reported to the 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

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been completed.

! 5.2 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 I 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 anecifications.

b. Personnel radiation protection, consistent with' applicable regulations.

j 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 l

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 Level 2 or designated alternate.

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5.3 Required Actions

5. 3 .'1 Action to be taken in the event of an occurrence as defined in section 5.4.3:

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 where applicable shall be reported to the Commission in accordance with section 5.4.2.

d. All such occurrences including action taken to prevent or reduce the probability of a recurrence shall be reviewed by the Nuclear Reactor Committee.

5.4 Reports In addition to tne requirements of applicable regulations, reports shall be made to the Commission as follows:

5.4.1 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 3 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.

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c. The results of any environmental surveys performed outside the facility.

d. A summary of significant (above 500 mrem) radiation exposures received bf facility personnel and visitors in any one year including the dates and times of significant exposures.

5.4.2 Special Reports Special reports which may be required by the NRC shall be submitted to the Director of the appropriate NRC office within the time period specified 1a each report.

5.4.3 Reportable Occurrene,qs, 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 No tification 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 radioactivity to the environment.

(2) Unanticipated exposure of personnel.

5.5 Records Records of the following activities shall be maintained and retained for the periods specified below. The records may be in the form of 9

' logs, data sheets, or other suitable forms. The required information may be contained in single, o multiple records, or a combination thereof.

5.5.1 Records to be Retained for a Period of at least Five Years

a. Principal maintenance operations.

b. Reportable occurrences.

c. Surveillance activities required by the Technical Specifications.

d. Reactor facility radiation and contamination surveys where required by-applicable regulations.

e. .Special Nuclear Materials (SNM) inventories, receipts, and-shipments.

f. Approved changes in operating procedures.

g. . Records of meeting and audit reports of the Nuclear Reactor Committee.

5.5.2 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.

6.0 REFERENCES

1. Hazards Summary Report (July, 1959) 10

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