ML20210Q866
ML20210Q866 | |
Person / Time | |
---|---|
Site: | General Atomics |
Issue date: | 08/12/1999 |
From: | Marsh L NRC (Affiliation Not Assigned) |
To: | |
Shared Package | |
ML20210Q861 | List: |
References | |
R-038-A-036, R-067-A-045, NUDOCS 9908160141 | |
Download: ML20210Q866 (29) | |
Text
e s a car o* 4 UNITED STATES
- f g NUCLEAR REGULATORY COMMISSION
't' WASHINGTON, D.C. 20066 4 001 l
4 9 . . . . . ,d GENERAL ATOMICS DOCKET NO. 50-89 AMENDMENT TO AMENDED FACILITY LICENSE Amendment No. 36 License No. R-38
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that A. The application for an amendment to Amended Facility License No. R-38 filed by General Atomics (the licensee) on April 18,1997, as supplemented on November 20,1998, and January 28 and 29, February 3, April 22, May 3 and 12, and June 15 and 22,1999, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of '
the Commission as stated in Chapter I of Title 10 of the Code of Federal Regulations (10 CFR);
B. The facility will be decommissioned in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of thi. oublic and (ii) such activities will be conducted in compliance with the regulations of tk.e Commission; D, The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. This amendment is issued in accordance with the regulations of the Commission as stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and
. F. Prior notice of this amendment was not required by 10 CFR 2.105, and publication of notice for this amendment is not reo.uired by 10 CFR 2.106.
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i f 2. Accordingly, the license is amended by changes to the following paragraphs which i are hereby amended to read as follows:
1.C. The facility will be decommissioned in conformity with the application as amended, the provisions of the Act, and the rules and regulations of the Commission; 1.D. There is reasonable assurance that the reactor facility can be decommissioned (i) without endangering the health and safety of the public and (ii) in compliance with the regulations in this chapter; 1.E. General Atomics is technically and financially qualified to decommission the facility in accordance with the regulations in this chapter;
- 3. Accordingly, the license is amended by deleting paragraph 2.B.(2) in its entirety.
- 4. Accordingly, the license is amended to approve the decommissioning plan described in the licensee's application dated April 18,1997, as supplemented on November 20, 1998, and January 28 and 29, February 3, April 22, May 3 and 12, and June 15 and 22,1999, and authorizes inclusion of the decommissioning plan as a supplement to the Safety Analysis Report pursuant to 10 CFR 50.82(b)(5). Also, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Amended Facility License No. R-38 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 36, are hereby incorporated in the license. The licensee shall decommission the facility in accordance with the Technical Specifications.
5, This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
%S Ledyard B. Marsh, Chief Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
Enclosure:
} Appendix A, Technical
! Specifications Changes i l
4 Date of issuance: August 12, 1999
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- t ENCLOSURE TO LICENSE AMENDMENT NO. 36 AMENDED FACILITY LICENSE NO. R-38 l DOCKET NO. 50-89 Replace the following pages of Appendix A, " Technical Specifications," with the enclosed pages. The revised pages are identified by amendment number.
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table of contents i 1 - 23 1-8 i
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TRIGA Reactors Facility TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility License No. R-38 AUGUST 12,1999
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TABLE OF CONTENTS Page No.
l_ 1.0 Definitions . . . . . . . . . . .... .. . . .. ... . . . . . . ... . . . . . . . . . . . . .. . .. .. . . . . .. . . . . . . . . . . . . . . . . 1 1
2.0 Site............................................................................................... 2 3.0 - Rea ctor B uilding .. . . .. . . . . . . . .. . . . . . . . .. . . . . . .. .. . . . . . . . .. . .. . . . . . . . . . . .. . . . . . . . . .. . . . . . . 2 4.0 Reactor Pool . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . 2
- 5.0 Reactor Fuel......... ... .......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.0 Control and Safety Systems .. .. .................. ....... . .... . . . . ... ..... .. .... 3 6.1 Control S yste m s . . . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . . . . . ... . .. .. . . . . . . . . . . . . . . . . . . . 3 6.2 Safety Systems ............................................................ 3 7.0 Administrative Requirements ... .. ...... . ..... ........ . . . . . ............. ... .... 3 7.1 Organization . .... . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7.2 Criticality and Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . . . . 4 7.3 Written Procedures ... ...... ... ........ ....... .. . .. . . . . . . . . . . . . . 5 7.4 Action to be Taken in the Event of a Reportable Occurrence . ..... 6 7.5 Facility Records . ... . . . . . . . . . . . . .. . . . . . . . . . . . . . 6 7.6 Reporting Requirements . .. ...... ... .. . .. .... .... . .. .. . ... ... ... 7 8.0 Facility Operations... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1
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Amendment No. 36 I l
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a . l APPENDIXA License No. R-38 TECHNICAL SPECIFICATIONS FOR 1 THE TORREY PINES TRIGA MARKIREACTOR DATE: JANUARY 21,1972 1.0 DEFINmONS I 1.1 Facility Facility means the building housing the disassembled reactor plus systems, components, etc. Associated with possession and decommissioning of the reactor.
1.2 Facility Secured Facility secured shall mean that condition where no decommissioning activities are in progress in the facility.
1.3 Facility Operation Facility operation shall mean any condition wherein the facility is not secured.
1.4 Decommissioning Activities Decommissioning activities shall mean those activities required to remove the facility safely from service and reduce residual radioactivity to a level that permits the release of the facility to unrestricted use and termination of the license. These l activities will involve the handling, surveying, packaging, and dispositioning of j radioactive materials in the facility.
1.5 Decommissioning Status Decommissioning status means that the facility license has been amendeo to withdraw authorization to operate the reactor and authorizes possession only of the reactor, and that the fuel has been removed from the reactor and is maintained in a safe and secure manner in an approved location outside the Mark I facility.
1.6 Operable A system or device shall be considered operable when it is capable of performing its intended functions in a normal manner.
1.7 Operating Operating means a component or system is performing its intended function.
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f 1.8 Abnormal Occurrence l
l An abnormal occurrence is an observed inadequacy in the implementation of ei'.her l administrative or procedural controls, such that the inadequacy caused, or could have caused, the existence or development of a condition which resulted, or could have resulted, in a facility condition outside the requirements of the Technical Specifications.
1.9 Measured Value The measured value is the magnitude of that variable as it appears on the output of a measuring channel.
1.10 Measuring Channel A measuring channel is the combination of sensor, interconnecting cables or lines, amplifiers, and output device which is connected for the purpose of measuring the value of a variable.
1.11 Channel Calibration A channel calibration consists of comparing a measured value from the measuring channel with a corresponding known value of the parameter so that the measuring channel output can be adjusted to respond, with acceptable accuracy, to known '
values of the measured variable.
2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIGA Reactor Facility building shall define the exclusion area.
3.0 REACTOR BUILDING .
Until such time as all decommissioning activities have been completed in the facility, the following ventilation requirements shall apply:
3.1 Controls for the ventilating system shall be located in the facility.
3.2 The reactor room ventilation shall be separate from the rest of the building ventilation.
3.3 During decommissioning activities, tenting or an equivalent confinement barrier shall be placed around the work area and an associated air ventilation HEPA system shall be operating to ensure the work area is maintained at a negative pressure with respect to the surrounding areas and the exhaust pathway to the environment is concolled and mor.hored.
4.0 REACTORPOOL -
4.1 Until drained as a part of decommissioning, the minimum level of the pool water shall be 12 inches below the reference point at the top of the pool. The reference point is marked on a straight edge affixed to the liner at the top of the pool. This point is located 91/2 inches from the top flange of the poolliner.
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l 4.2 Until such time as the pool water is drained as a part of decommissioning, the pool water shall be sampled for conductivity at least weekly. The conductivity of the coolant shall not exceed 5 micro-mhos per centimeter averaged over any one calendar month.
5.0 REACTORFUEL No reactor fuel elements or control elements with fuel followers shall be located in, stored in, or moved into, the reactor core structure or reactor facility.
6.0 CONTROL AND SAFETY SYSTEMS 6.1 Control Systems The poison section of the control rods which may remain in the facility contains borated graphite or stainless steel, B4 C powder or boron or its compounds in solid form, cadmium, or the rare earth poisons in solid form clad with the materials authorized for fuel-element cladding. The control rods may contain flux traps and may be equipped with non-fuel followers.
6.2 Safety Systems Until such time as decommissioning activities are completed in the facility, radiation monitoring systems shall be operating as follows:
- a. An area radiation monitoring system capable of activating an evacuation alarm.
- b. When the facility is not secured, a continuous monitoring system for airborne activity having a readout and audible alarm which can be heard in the facility.
These systems shall be calibrated annually and their setpoints verified monthly. For periods of time for maintenance or repair to the above systems, or during oeriods of other forced outages, the intent of this specification shall be satisfied if the inctalled system (s) is replaced with appropriate alternate or portabic radiation monitoring system (s).
Following maintenance or modification of the radiation monitoring systems, the affected system shall be verified to be operable before returning it to routine operation.
7.0 ADMINISTRATIVE REQUIRENENTS 7.1 Organization The facility shall be under the supervision of the Physicist-in-Charge or his designated alternate, both of whom shall be licensed senior operators of the facility.
The minimum qualification for the Physicist-in-Charge shall include a Bachelor's degree or equivalent academic education and three years experience in activities related to reactor operations. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated 3
Amendment No. 36
l alternate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive material. The reactor l shall be related to the Corporate structure as shown in the following chart:
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-**^ % ___1______I man n.uw Direct Reporting g Functional Support / Oversight 7.2 Criticality and Radiation Safety Committee
- a. There shall be a Criticality and Radiation Safety Committee (CRSC). The CRSC or a subcommittee thereof shall review activities of the facility to assure criticality and radiation safety. This Committee shall be composed of at least four members selected by the Cognizant Vice President, or a designee, considering their experience and education with regard to the various aspects of nuclear physics, chemistry, radiological health and statistics, as well as appropriate experience in other disciplines such as metallurgy and engineering.
Subcommittees shall be appointed by the Chairman of the CRSC. The subcommittee assigned the responsibility for reviewing facility operations shall not have thereon person (s) who are directly involved with the facility.
- b. The Criticality and Radiation Safety Committee shall be in accordanca ?a written charter including provisions for:
4 Amendment No. 36
- 1. Holding meetings or audits at least annually; special meetings may be called by subcommittees of the CRSC or by the Chairman of the CRSC at times ;
when such meetings are deemed appropriate. j l
- 2. Having a quorum when a majority of the members attend.
- 3. Preparing minutes or audit findings of the CRSC meetings by the Chairman or his designee. Evidence of approvalof the participating members of the CRSC shall be obtained before distribution.
- c. The Criticality and Radiation Safety Committee, or subcommittee, shall review t
and approve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereof shall audit the Facility annually, but at intervals not to exceed fifteen (15) months.
- d. The responsibilities of the Committee or designated subcommittee thereof include, but are not limited to, the following:
- 1. Review and approval of all proposod changes to the facility, procedures, and Technical Specifications;
- 2. Determination of whether a proposed -hange, test, or experiment would constitute an unreviewed safety questice or a change in the Technical Specifications;
- 3. Review of Facility records;
- 4. Review of abnormal performance of plant equipment and other anomalies; and
- 5. Review of unusual or abnormal occurrences and incidents which are Reportable Occurrences under 10 CFR 20 and 10 CFR 50.
7.3 Written Procedures Written instructions shall be in effect for the following items. The instructions shall be adequate to assure the safe possession of the reactor but shall not preclude the i use of independent judgment and action should the situation require such: 1
- a. Testing and calibration of instrumentation, controls, radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications.
F i!mergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support.
- c. Maintenance of systems necessary for maintaining the reactor in accordance with the license.
- d. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal changes.
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- e. Decommissioning activities (consistent with an approved Decommissioning Plan).
f Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safety Committee (CRSC). I Temporary changes to the procedures that do not change their original intent and do I not constitute an unreviewed safety question (as defined in 10CFR50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed and approved by the CRSC.
7.4 Action to be Taken in the Event of an Abnormal Occurrence In the event of an abnormal occurrence, as defined in Section 1.8 of the Specifications, the following action shall be taken:
- a. The Physicist-in-Charge or designated alternate shall be notified and corrective action taken with respect to the operation involved.
- b. The Physicist-in-Charge or other person notified under Section 7.4a shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, identified in Section 7.1.
- c. A report shall be made to the CRSC which shallinclude an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence.
- d. A report shall be made to the NRC in accordance with Section 7.6 of these Specifications.
7.5 Facility Records in addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared of at least the following items and retained for a period of at least five (5) years:
- a. Normal reactor operation and facility status;
- b. Principal maintenance activities;
- c. Abnormal or reportable occurrences; i
- d. Equipment and component survei! lance activities required by the Technical Specifications;
- e. Gaseous and liquid radioactive effluents released to the environs;
- f. Off-site environmental monitoring surveys;
- g. Fuelinventories and transfers;
- h. Facility radiation and contamination surveys; 6
Amendment No. 36
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- 1. Experiments performed with the reactor or in support of decommissioning;
- j. Radiation exposures for all personnel;
- k. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility).
- 1. Decommissioning / dismantlement activities. 1 7.6 Reporting Requirements in addition to the requirements of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC as follows:
- a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or facsimile to the NRC Operations l Center:
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure;
- 2. Any abnormal occurrences as defined in Section 1.8 of these Specifications.
- b. A report within 10 days in writing to the Document Control Desk, USNRC , l Washington, D.C. 20555:
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure; the written report (and, to the extent possible, the preliminary telephone or facsimile report) shall describe, analyze and evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event.
- 2. Any abnormal occurrence as defined in Section 1.8 of these Specifications.
- c. A report within 30 days in writing to the Document Control Desk, USNRC ,
Washington, D.C. 20555:
- 1. Any significant changes in facility organization or personnel for which minimum qualifications are specified in these specifications.
- d. Commencing in 2000, a routine report in writing to the Document Control Desk, U.S. Nuclear Regulatory Commission by April 15 of each year, providing the following information:
- 1. A brief narrative summary of: (1) actions taken for decommissioning of the facility, (2) current facility status, (3) any changes to the decommissioning schedule, and (4) a summary of radioactive material shipments.
7 Amendment No. 36
- 2. Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe possession of the reactor, and the reasons for any corrective maintenance required.
- 3. A summary of each change, if such changes have been made, to the facility, or procedures, tests, and experiments carried out under the conditions of Section 50.59 of CFR Part 50.
- 4. 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. ,
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- 5. A description of any environmental surveys performed outside the .
facility.
- 6. A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility.
8.0 FACILITY OPERATIONS The following activities shall be conducted in the facility:
i a) Mainterance, monitoring, control of radioactive material, protection of personnel, and security ac+ivities as defined in approved procedures (see Section 7.3).
b) Decommissioning in accordance with the facility license and consistent with an approved Decommissioning Plan.
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[ t UNITED STATES
- " } NUCLEAR REOULATORY COMMISSION
- WASHINGTON, D.C. 2006H001 4
9 . . . . . ,o GENERAL ATOMICS DOCKET NO. 50-163 AMENDMENT TO FACILITY LICENSE Amendment No. 45 License No. R-67
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that A. The application for an amendment to Facility License No. R-67 filed by General Atomics (the licensee) on April 18,1997, as supplemented on November 20, 1998, and January 28 and 29, February 3, April 22, May 3 and 12, and June 16 and 22,1999, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in Chapter I of Title 10 of the Code of Federa/ Regulations (10 CFR);
B. The facility will be decommissioned in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:
C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) such activities will be conducted in compliance with the regulations of the Commission- ,
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D. The issuance of this amendment will not be inimical to the common defense and !
security or to the health and safety of the public; l
E. This amendment is issued in accordance with the regulations of the Commission l as stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105, and j publication of notice for this amendment is not required by 10 CFR 2.106.
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- 2. Accordingly, the license is amended by changes to the following paragraphs which are hereby amended to read as follows:
1.B. The reactor has been constructed la conformity with Construct;en Permit No.
CPRR 59 and will be decommissioned in conformity with tN appiication, as amended, and in conformity with the Act and the rules and regulations of the Commission:
1.C. There is reasonable assurance that the reactor can be decommissioned at the designated location without endangering the health and safety of the public:
1.D. General Atomics is technically and financially qualified to decommission the reactor; i
1.E. The decommissioning of the reactor in the manner proposed in the application will not be inimical to the common defense and secority or to the health and safety of the public;
- 3. Accordingly, the license is amended by deleting paragraphs 3 and 4 in their entirety.
- 4. Accordingly, the license is amended to approve the decommissioning plan described in the licer.see's application dated April 18,1997, es supplemented on November 20, 1998, ond January 28 and 29, February 3, April 22, May 3 cnd 12, and June 1 0 and 22,1999, and authorizes inclusion of the decommissioning plan as a supplement to the Safety Analysis Report pursuant to 10 CFR 50.82(b){5). Also, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.2. of Facility License No. R-67 is hereby amended to read as follows:
(2) Tgr hnigal Soecifications The Techt,! cal Specifications contained in Appendix A, as revised through Amendment Na,45, are hereby incorporated in the license. The licensee shall decommission the facility in accordance wi'.h the Technical ,
Specifications.
5, This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
% b-gledyard B. Marsh, Chief f Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation
Enclosure:
Appendix A, Technica.
Specifications Changes Date of Issuance: August 12, 1999
f ENCLOSURE TO LICENSE AMENDMENT NO. 41 FACILITY LICENSE NO. R-67 QQCKFT ivo. 50-163 Replace the following pages of Appendix A, " Technical Specifications," with the enclosed pags The revised pages are identified by amendment number.
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l TRIGA Reactors Facility TECHNICAL SPECIFICATIONS TPdGA MARK F REACTOR Facility License No. R-67 l
AUGUST 12,1999
TABLE OF CONTENTS Page No.
1.0 Definitions . . . . . . . . . . . . . . . . . . . .. . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 Site . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2 3.0 - Reactor Building... ............ .... ............. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 Reactor Pool . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 3 5.0 Stored Fuel Description .. . . . . . . . . . . . . . . . .. . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.0 Control and Safety Systems........... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 6.1 C ontrol S ystems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 6.2 Safety Systems .. .. . ....... . .. ... . . . ... . ... . . . . . . . . . . . . . . . . . . . . 5 7.0 Fuel Storage . . . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8.0 Administrative Requirements. .. ..... . . . . . . . . . . . . . . ..... . . 6 8.1 Org anization. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8.2 Criticality and Radiation Safety Committee.. .. . .......... . ....... .. .. ...... . . . 7 8.3 Written Procedures... ....... .. . . ...... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 ,
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Action to be Taken in the Event of an Abnormal Occurrence. .... ....
8.4 . . . . 8 8.5 Facility Records..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 8.6 Reporting Requirements. .......... .. ...... .. . . . ...... . ..... .. . .... ... . . . .. . 9 9.0 Facility Operations... ...... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 I.
AMENDMENT NO.45
l Appendix A License No. R-67 TECHNICAL SPECIFICATK)NS for THE TORREY PINES TRIGA MARK F REACTOR 1.0 DEFINmONS 1.1 Facility Facility means the building housing the disassembled reactor plus systems, components, etc. associated with possession and decommissioning of the reactor, including fuel storage.
1.2 Facility Secured Facility secured shall mean that condition where no decommissioning activities or handling of fuel are in progress at the facility.
1.3 Facility Operation Facility operation shall mean any condition wherein the facilityis not secured.
1.4 Decommissioning Activities Decommissioning activities shall mean those activitiet required to remove the ,
facility safely from service and reduce residual radicwAvity to a level that )
permits the release of the facility to unrestricted use nr.d termination of the '
license. These activities willinvolve the handling, surveying, packaging, and dispositioning of radioactive materials in the facility. l l
1.5 Decommissioning Status Decommissioning status means that the facility license has been amended to withdraw authorization to operate the reactor and authorizes possession j only of the reactor, and that the fuel has been removed from the reactor and is maintained in a safe and secure manner in an approved location in the facility.
1.6 Operable A system or device shall be considered operable when it is capable of performing its intended functions in a normal manner.
1.7 Operating Operating means a component or system is performing its intended function.
AMENDMENTNO.45 1
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1.8 Abnormal Occurrence An abnormal occurrence is:
(a) Any unanticipated or uncontrolled change in subcritical multiplication during fuel storage or handling, (b) An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy caused or could have caused the existence or the development of a condition which resulted or could have resulted in a facility condition outside the requirements of the Technical Specifications; and i
(c) Release of fission products from a fuel element or fuel follower j control rod during fuel storage or handling. 1 1.9 Measured Value i
The measured value is the magnitude of that variable as it appears on the output of a measuring channel.
1.10 Measuring Channel A measuring channelis the combination of sensor, interconnecting cables or lines, amplifiers, and output device which is connected for the purpose of measuring the value of a variable.
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1.11 Channel Calibration A channel calibration consists of comparing a measured value from the measuring channel with a corresponding known value of the parameter so that the measuring channel output can be adjusted to respond, with acceptable accuracy, to known values of the measured variable.
l 2.0 SITE l A minimum radius of 120 feet from the appropriate center of the TRIGA Reactor Facility building shall define the exclusion area.
3.0 REACTOR Bull. DING Until such time as all fuel is removed from the facility and all decommissioning activities have been completed, the following ventilation requirements shall apply.
3.1 The reactor shall be housed in a closed room built to restrict leakage. The minimum free volume in the reactor room shall be 11,700 cubic feet.
3.2 Controls for the ventilating system shall be located in the facility.
3.3 All air or other gas exhausted from the reactor room shall be released to the environment at a minimum of 20 feet above ground level.
AMENDMENTNO.45 2
l 3,4 The reactor room ventilation system shall be separate from the rest of the building ventdabon l 4
3.5 During decommissioning activities and while fuel remains in the facility, air ventilation systems shall be operating to ensure the reactor room is maintained at a negative prei,sure with respect to the surrounding areas and the exhaust pathway to the environment is controlled and monitored.
4.0 REACTOR POOL 4.1 The stored reactor fuel shall be cooled by natural convective water flow.
4.2 Until such time as all fuel has been removed from the pool and the pool is drained as a part of decommissioning, the minimum level of the pool water shall be 12 inches below the reference mark near the top of the pool. The reference mark is locat:,d on the west wall of the north-south canal at a level 181/2 inches below floor grade level.
4.3 Until such time as all fuel has been removed from the pool and the pool is drained as a part of decommissioning, the pool water shall be sampled for conductivity at least weekly. The conductivity of the coolant shall not exceed 5 micro-mhos per centimeter averaged over any one calendar month.
44 Until such time as all fuel has been removed from the pool, on a quarterly basis the pool water shall be sampled and analyzed for the presence of fission products et a level indicating potential fuel leakage.
5.0 STORED FUELDESCRIPTION 5.1 No reactor fuel elements or control eleme us with fuel followers shall be stored in the reactor portion (round area) of the pool. Reactor fuel elements i and control elements with fuel followers chall only be stored in the Fuel l Storage Area of the Mark F reactor pool.
5.2 Standard fuel elements have the characteristics listed below:
5.2.1 Standard low-enrichment fuel (a) Maximum uranium content 9.0 wt%
in unirradiated fuel (b) Maximum uranium enrichment <20%
in unirradiated fuel (c) Hydrogen to zirconium ratio 0.9 to 1.54 H atoms to 1.0 Zr atom (in the ZrHn) (Iow hydride) 1.55 to 1.8 H atoms to 1.0 Zr atom (high hydride) '
(d) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800, Hastelloy X, or 0.030 inch aluminum orZircaloy L
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5.2.2 Standard Fuel Lifettne improvement Program (FLIP) fuel (a) Maximum uranium content 9.0 wt%
in unirradiated fuel (b) Nominal uranium enrichment 70%
in unitradiated fuel (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHn)
(d) Natural erbium content 1.0 to 1.8 wt.%
(homogeneous distribution)
(e) Cladding materialand 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800, or Hastelloy-X 5.2.3 Standard low-enrichment fuel with high wt% uranium (a) Maximum uranium content 30 wt%
in unirradiated fuel '
(b) Maximum uranium enrichment < 20%
in unirradiated fuel (c) Hydrogen-to-rirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHo)
(d) Natural erbium content 0.4 to 1.8 wt%'
(homogeneous distribution)
(e) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800, or Hastelloy-X
' Scaled according to maximum U-235 content such that a core containing only these elements would require a criticalloading of 2 50 fuel elements.
5.3 Special fuel elements are uranium zirconium hydride fuel elements, which are not standard fuel elements, have the characteristics listed below.
5.3.1 Special fuel elements with high-enrichment uranium.
(a) Maximum uranium content 12.0 wt%
in unirradiated fuel (b) Maximum uranium enrichment 95 %
in unirradiated fuel (c) Cladding material and 0.020 inch 304 or 304L stainless steel, I minimum thickness incoloy 800, or Hastelloy-X or 0.030 inch Zircaloy (d) Construction shall be such that calculated clad temperature shall not exceed 500 C at the planned operating level AMENDMENTNO.45 4
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5.3.2 Special fuel elements with high wt% uranium (a) Maximum uranium content >30.0 to 45.0 wt%
in unirradiated fuel (b) Maximum uranium ennchment <20%
in unitradiated fuel (c) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800 or Hastelloy-X or 0.030 inch Zircaloy for 1.5 inch nominal diameter, or 0.015 inch to 0.020 inch stainless steel, incoloy 800 or Hastelloy-X for 0.5 inch nominal diameter (d) Construction is such that the calculated clad temperature does not exceed 500 C at planned operating level.
(e) Special fuel elements with 0.5 inch nominal diameter are enclosed in a 0.020 inch metal shroud. The shroud, constructed from one of the above listed cladding materials, has a nominal diameter of 1.5 inches. i 5.3 4 Any bumable poison used is an integral part of the as-manufactured fuel element. A bumable poison is defined as a material used for the specific purpose of compensating for fuel bum-up and/or other long-term reactivity adjustments.
6.0 CONTROL AND SAFETY SYSTEMS 6.1 Control Systems The poison section of the control rods which may remain in the facility contains borated graphite or stainless steel, B4 C powder or boron or its compounds in solid form, cadmium, or the rare earth poisons in solid form, clad with the materials authorized for fuel element cladding. The control rods may contain flux traps and may be equipped with fuel or non-fuel followers.
6.2 Safety Systems Until such time as decommissioning activities are completed in the facility, radiation monitoring systems shall be operating as follows:
(a) An area radiation monitoring system capable of activating the evacuation alarm.
(b) When the facility is not secured, a continuous monitoring system for airbome activity having a readout end audible alarm which can be heard in the facility.
AMENDMENTNO.45 !
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- o These systems shall be calibrated annually and their set points verified monthly. For periods of time for maintenance or repair to the above systems, or during periods of other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate attemative or portable radiation monitors.
Folk.:.ing maintenance or modification of the radiation monitoring systems, the affected system shall be verified to be operable before retuming it to routine operation.
7.0 FUEL STORAGE 7.1 All fuel elements or control elements with fuel followers shall be stored in a safe geometry (ken less than 0.8 under ti conditions of moderation).
7.2 Irradiated fuel elements and control elements with fuel followers shall be stored in an array which will permit sufficient natural convection cooling by water or air such that the temperature of the fuel element will not exceed design values.
8.0 ADMINISTRATIVE REQUIREMENTS i 8.1 Organization i The facility shall be under the supervision of the Physicist-in-Charge or his !
designated alternate, both of whom shall be licensed senior operators of the )
facility. The minimum qualification for the Physicist-in-Charge shallinclude a j Bachelor's degree or equivalent academic education and three years '
experience in activities related to reactor operations. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated attemate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive material. The reactor shall be related to the Corporate structure as shown in the following chart:
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AMENDMENT NO.45 6
8.2 Criticality and Radiabon Safety Cwm.C
- a. There shall be a Cnbcality and Radiabon Safety Comr,$ittee (CRSC).
The CRSC or a subcommittee thereof shall review activibes of the facility to assure =ttkality and redistion safety. This Committee shall be composrA of at least igur members selected by the Cognizant Vice Pres: dent, or a designee, considering their experience and education with regard to the various aspects of nuclear physics, i chemistry, radiological health and statistics, as well as appropriate !
experience in other disciplines such as metallurgy and engineering. l Subcommittees shall be appointed by the Chairman of the CRSC. The subcommittee assigned the responsibility for reviewing facility i operations shall not have thereon person (s) who are directly involved !
with the facility.
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- b. The Criticality and Radiabon Safety Committee shall be in accordance with a written charter including provisions for:
- 1. Holding meetings or audits at least annually; special meetings may be called by subcommittees of the CRSC or by the Chairman of the CRSC at times when such meetings are deemod appropriate.
- 2. Having a quorum when a majority of the members attend.
- 3. Preparing minutes or audit findings of the CRSC meetings by the Chairman or his designee. Evidence of approval of the participating members of the CRSC shall be obtained before distribution.
- c. The Criticality and Radiation Safety Committee, or subcommittee, shall review and approve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereof shall audit the '
Facility annually, but at intervals not to exceed fifteen (15) months.
- d. The responsibilities of the Committee or designated subcommittee thereof include, but are not limited to, the following:
- 1. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications;
- 2. Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question or a change in the Technical Specifications;
- 3. Review of Facility records;
- 4. Review of abnormal performance of plant equipment and other anomalies; and
- 5. Review of unusual or abnormal occurrences and incidents which are Reportable Occurrences under 10 CFR Part 20 and 10 CFR Part 50.
AMENDMENTNO.45 7
i i1 8.3 Written Procedures j
Written instructions shall be in effect for the following items. The instructions shall be adequate to assure the safe possession of the reactor but shall not preclude the use ofindependentjudgment and action should the situation j require such:
- a. Testing and calibrabon of instrumentabon, controls, radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications.
I
- b. Emergency and abnormal conditions including provisions for I evacuation, reentry, recovery, and medical support.
- c. Fuel element or control element with fuel follower handling.
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- d. Maintenance of systems necessary for assuring the integrity of the fuel and for maintaining the reactor in accordance with the license.
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- e. Actions to be taken to correct specific and foreseen potential l
malfunctions of systems or components, including responses to alarms and abnormal changes,
- f. Decommissioning activities (consistent with an approved -
Decommissioning Plan).
Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safety Committee (CRSC). Temporary changes to the procedures that do not change their original intent and do not constitute an unreviewed safety question (as defined in 10 CFR 50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed and approved by the CRSC.
8.4 Action to be Taken in the Event of an Abnormal Occurrence In the event of an abnormal occurrence, as defined in Section 1.8 of the Specifications, the following action shall be taken:
- a. The Physicist-in-Charge or designated attemate shall be notified and corrective action taken with respect to the operation involved,
- b. The Physicist-in-Charge or other person notified under Section 8 shall notify the Chairman of the CRSC and the Vice President, or his designated attemate, identified in Section 8.1.
- c. A report shall be made to the CRSC which shall include an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence,
- d. A report shall be made to the NRC in accordance with Section 8.6 of these Specifications.
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8.5 Facility Records in addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared of at least the following items and retained for a period of at least five (5) years:
- a. Normal reactor operation and facility status;
- b. Principal maintenance activrbes;
- c. Abnormal or reportable occurrences;
- d. Equipment and component surveillance activities required by the Technical Specifications;
- e. Gaseous and liquid radioactive effluents released to the environs;
- f. Off-site environmental monitoring surveys;
- g. Fuelinventories and transfers;
- h. Facility radiation and contamination surveys; )
- i. Experiments performed with the reactor or in support of decommissioning;
- j. Radiation exposures for all personnel;
- k. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility);
- l. Decommissioning / dismantlement activities.
8.6 Reportina Requirements in addition to the requirements of applicable regulations, and in no way substituting therefore, reports shall be made to the NRC as follows:
- a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or facsimile to the NRC Operations Center:
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in ,
property damage, personal injury, or exposure;
- 2. Any abnormal occurrences as defined in Section 1.8 of these Specifications.
- b. A report within 10 days in writing to the Document Control Desk, USNRC, Washington, DC 20555: -
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure; the written
. report (and, to the extent possible, the preliminary telephone or AMENDMENTNO.45 9
facsimile report) shall describe, analyze and evaluate safety implicabons, and outline the corrective measures taken or
- planned to prevent reoccurrence of the event.
- 2. Any abnormal occurrence as defined in Section 1.8 of these Specifications.
- c. A report within 30 days in writing to the Document Control Desk, USNRC, Washington, DC 20555:
- 1. Any significant variation of measured values from a corresponding predicted or previously measured value of safety-connected operating characteristics occurring for the reactor or fuel;
- 2. Any significant changes in the transient or accident analyses as described in all Safety Analysis Reports; and
- 3. Any significant changes in facility organization or personnel 4 for which minimum qualifications are specified in these specifications.
4
- d. Commencing in 2000, a routine report in writing to the Document Control Desk, U.S. Nuclear Regulatory Commission by April 15 of each year, providing the following information:
- 1. A brief narrative summary of: (1) actions taken for decommissioning of the facility, (2) current status of the facility and fuel, (3) any changes to the decommissioning I schedule, and (4) a summary of radioactive material shipments.
- 2. Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe possession of the reactor, and the reasons for any corrective maintenance required.
- 3. A summary of each change, if such changes have been made, to the facility, or procedures, tests, and experiments carried out under the conditions of Section 50.59 of CFR Part 50.
- 4. 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.
- 5. A description of any environmental surveys performed outside the facility.
- 6. A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility.
AMENDMENT NO.45 10
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g.0 FACILITY OPERATIONS The following activities shall be conducted in the facility:
a) Maintenance, monitoring, control of radioactive material, protection of personnel and security activities as defined in approved procedures (see Section 8.3).
b) Decommissioning in accordance with the facility license and consistent with ,
an approved Decommissioning Plan. l c) Fuel storage, handling, packaging and removal in accordance with approved l procedures. l l
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