ML20206S043
| ML20206S043 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 05/31/1999 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20206S038 | List: |
| References | |
| NUDOCS 9905210040 | |
| Download: ML20206S043 (79) | |
Text
{{#Wiki_filter:. TRIGA Reactors Facility TECl- \ CA_ S 3ECI: CAT 05 S "RIGA VARK REACTOR Facility License No. R-67 MAY 1999 i I i i Proposed Amendment 45 9905210040 990512 9 DR ADOCK 0500 j
I I TABLE OF CONTENTS i Page No. 1.0 D efinitio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 1. . . . . .. . . . . . . . l 2.0 Site ............................................................................... 2 { 3.0 Rea ctor B uilding . . . . . . . .. . . . . . . . . . . .. . . . . . . . . ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 Re a cto r Pool . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . .. .. .. .. ... .. .. .. .. . 2 5.0 Stored Fuel Description ........... .. . ..... .... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.0 Control a nd Safety Systems....... . .. ..... ........... . ... .......... . ... ..... . .... . . . . . . 4 6.1 Control Syste m s . .. .. . . . . . . . . ... .... . . ... .. . .... . . . .. .. . ..... . .. .. . . . . . . . .. . .... ....... . 4 6.2 Sa fety Syste m s . ... . . . . . .. . . .. .. .. . . . . . . ... . . ... ... .. .. . . . . .. . . .. . . . . . . . .. . . .. . .. . 5 6.3 Maintenance on Control and Safety Systems.... ................................. 5 7.0 Fu el S tora ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . .. . . . . ..
. . . . . . . 5 8.0 Administrative Requirements ...... ........ .. .. .................. .... ... . . .... ......... . .. . .... ... 5 8.1 Orga nizatio n . . . .. . . . . . . ... . .. .. . . . . ... ... . . . .. . .. . . . . .. . .. ... . . . . . . 5 8.2 Criticality and Radiation Safety Committee............. ......... .. ... ............ ...... 6 8.3 Written Proced u re s .. . ... . . . . .. .. . .. .. .... . ..... . ... . ......... .. .. . . . . . . ... . .. . . . ... . . . 7 8.4 Action to be Taken in the Event of an Abnormal Occurrence. .... ....... ....... 8 8.5 Fa cility Re cord s . .. .. .... . . . . . .. . ...... . . ... ... . .. ... .. . . . . ... . . .. . . .. . . . ... .. .. ... 8 8.6 Reporting Requirements......... .... ... ........ .... ... ............. ..... .. .. . ...... .... 9 9.0 Fa cility Ope ra tions ... .... . . ... ..... .. .. . . . . .. .. .... .. .. . . ... . .. . . . . . . . . . .. . . . . .. .. . . . . . . .. . ... .. ..... .. 10 i
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AMENDMENTNO.45 m
Appendix A l License No. R-67 l TECHNICAL SPECIFICATIONS for THE TORREY PINES TRIGA MARK F REACTOR l l Date: September 27,1968 The dimensions, measurements and other numerical values given in these specifications can differ from actual values owing to the normal construction and manufacturing tolerances or normal accuracy of instrumentation. 1.0 DEFINmONS 1.1 Facility Facility means the builoing housing and disassembled reactor plus systems, components, etc. associated with possession only of the reactor, including fuel storage. 1.2 Facility Secured Facility secured shall mean that condition where no work is in progress involving handling of fuel, or removal of activated or contaminated hardware or material from the facility. 1.3 Facility Operation { Facility operation shall mean any condition wherein the facility is not secured. 1.4 Decommissionino 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 activities willinvolve the handling, surveying, packaging, and dispositioning of radioactive materials in the facility. ; 1.5 Possession Only License Status l Possession Only License (POL) status means that the facility license has been amended to withdraw authorization to operate the reactor and authorize 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 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. AMENDMENT NO.45 1 L
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1.7 Abnormal Occurrence An abnormal occurrence is: (a) Any unanticipated or uncontrolled change in subcritical multiplication during fuel storage or handling, 4 (b) An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy could have caused the existence or the development of a condition which could result in possession of the reactor facility outside the requirements of the Technical Specifications; and (c) Release of fission products from a fuel element during fuel storage or handling. 2.0 SRE A minimum radius of 120 feet from the appropriate center of the TRIGA Reactor Facility building shall define the exclusion area. 3.0 REACTOR BUILDING Until such time as all fuel and activated / contaminated hardware are removed from the facility, 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. 3.4 The reactor room ventilation system shall be separate from the rest of the building ventilation. 3.5 During decommissioning activities and while fuel remains in the facility, air ventilation systems shall be operable to ensure the reactor room is maintained at a negative pressure with respect to the surrounding areas. 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 poolis drained as a part of decommissioning, the minimum level of the pool water shall be no less than 12 inches below the reference at the top of the pool. 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. AMENDMENT NO.45 2
r 5.0 STORED FUELDESCRIPTION 5.1 No reactor fuel elements or control elements with fuel followers shall be stored in the reactor portion of the 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 or Zircaloy 5.2.2 Standard Fuel Lifetime Improvement Program (FLIP) fuel (a) Maximum uranium content 9.0 wt% in unirradiated fuel (b) Nominal uranium enrichment 70 % in unirradiated fuel (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHo) (d) Natural erbium content 1.0 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 l 5.2.3 Standard low-enrichment fuel with high wt% uranium (a) Maximum uranium content 30 wt% l in unirradiated fuel i (b) Maximum uranium enrichment < 20% ' in unirradiated 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 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 critical loading of 2 50 fuel elements. AMENDMENT NO.45 3
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 j (b) Maximum uranium enrichment 95 % { in unirradiated fuel j (c) Cladding material and 0.020 inch 304 or 304L stainless steel, 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 1 5.3.2 Special fuel elements with high wt% uranium l (a) Maximum uranium content >30.0 to 45.0 wt% in unirradiated fuel (b) Maximum uranium enrichment <20% in unirradiated fuel (c) Cladding materialand 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800 or Hastelloy-X l or 0.030 inch Zircaloy for 1.5 inch nominal diameter, or 0.015 inch to 0.020 inct- 'tainless steel, Incoloy 800 or Hastelloy-X for 0.5 inch nominal diameter I (d) Construction is such that the calculated clad temperature does not i 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 dia.neter of 1.5 inches. 5.3 4 Any burnable poison used is an integral part of the as-manufactured fuel element. A burnable poison is defined as a material used for the specific purpose of compensating for fuel burn-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, B4C 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 AMENDMENT NO.45 4
rods may contain flux traps and may be equipped with fuel or non-fuel followers. 6.2 Safety Systems Until such time as all fuel elements, control rods, and major activated components of the reactor have been removed from the facility, radiation monitoring systems shall be operable 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 airborne activity having a readout and audible alarm which can be heard in the facility. 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 alternative or portable radiation monitors. Following maintenance or mooification of the radiation monitoring systems, the affected system shall be verified to be operable before returning it to routine operation. 4 7.0 FUEL STORAGE 7.1 All fuel elements or fueled devices shall be stored in a safe geometry (kg less than 0.8 under all conditions of moderation). 7.2 Irradiated fuel elements 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 Until such time as decommissioning activities are completed to the extent that all fuel and major activated hardware has been removed from the facility, the following administrative requirements shall apply. 8.1 Organization i The facility shall be under the supervision of the Physicist-in-Charge or his I designated alternate, both of whom shall be licensed senior operators of the : facility. The minimum qualification for the Physicist-in-Charge shall include a j Bachelor's degree or equivalent academic education and three years experience in activities related to reactor operations. He shall be responsible j to a Vice President whose duties include responsibility for research and ! development, or his designated alternate, 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 i structure as shown in the following chart: 1 i AMENDMENT NO.45 l
F I Vice President or Cognizant Vice President Vice Designated Alternate President Director Licensing, Safety
& Nuclear Compliance Criticality Health Physics --- Physicist-in-Charge ---
Saf t Committee Facility Staff Direct Reporting
--- Functional Support / Oversight 8.2 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 accordance with a written charter including provisions for.
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- 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. AMENDMENT NO.45 6
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- 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 would constitute an unreviewed safety question or a change in the Technical Specifications; i
- 3. Review of Facility records; l
- 4. Review of abnormal performance of plant equipment and other anomalies; and
- 5. Review abnormal occurrences which are Reportable Occurrences under 10 CFR Part 20 and 10 CFR Part 50.
8.3 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 use of independent judgment and action should the situation require such:
- a. Testing and calibration of instrumentation, controls, radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications.
- b. Emergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support.
- c. Fuel element handling. '
- d. Maintenance of systems necessary for assuring the integrity of the fuel or otherwise maintaining the reactor in POL status.
- e. Actions to be taken to correct specific and foreseen potential i malfunctions of systems or components, including responses to alarms and abnormal reactivity changes.
AMENDMENT NO.45 7
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- f. Decommissioning activities (consistent with an approved Decommissioning Plan).
Changes which alter the originalintent 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 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 1.7 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 8 shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, 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.
8.5 Facility Records in addition to the requirements of applicable regulations, and in no way i 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 POL status; i
- b. Principal maintenance activities; I
- c. Abnormal 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; I
- g. Fuelinventories and transfers;
- h. Facility radiation and contamination surveys;
- i. Radiation exposures for all personnel; AMENDMENTNO.45 8
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- j. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility);
- k. Decommissioning / dismantlement activities.
8.6 Reporting 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 hours 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; 1
- 2. Any abnormal occurrences as defined in Section 1.7 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 l 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 1.7 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 during possession of the reactor;
- 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 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:
AMENDMENT NO.45 9
- 1. A brief narrative summary of: (1) possession and storage and (2) changes in facility storage design.
- 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.
9.0 FACILITY OPERATIONS-The following activities shall be conducted in the facility: a) Maintenance, monitoring, control, protection of personnel and security activities as defined in approved procedures (see Section 8.3). b) Decommissioning (consistent with an approved Decommissioning Plan). c) Fuel storage, handling, packaging and removal in accordance with approved procedures. I I i l l I l AMENDMENT NO.45 10
l TRIGA Reactors Facility I (" REDLINED" VERSION - FOR INFORMATION ONLY)
"EC 4hlCA_ S 3EC : CAT O\ S TRIGA VARK REACTOR Facility License No. R-67 l l
MAY1999 Proposed Amendment 45 s
r TABLE OF CONTENTS Page No. 1.0 D e finitio ns . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. . . . . . . . . . . . . . . . . . 2.0 Site ........................................................................ . . . 3 3.0 Rea ctor B uild ing .. . .. . .... ... . .... ..... . .. . .. .. . . .. . . . .. . . . . . .. . . .... . . . . . .. . . . . .. . . . . .. ... . . . . . . 3 4.0 Re actor Pool . . . . .. . . . . . . . . . . . . .. . . . .. . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .3. . . . . . . . . . . . . . . . . . . 5.0 Stored Rccctor Fuel Description-Gors . ..... .... .. . .. .. ......... ....... . ...... ..... . . .. . 3 6.0 Control and S afety Systems...... ........... . . ... ............ ...... ...... ....... .. .... .... . .. . 6 6.1 Control Syste ms...... .. .. .. . . .. ... .. . . . .. . .. . . . . . . . .. . . . . . . . . . . . .. . . . . . . .. . . . . .. . . . . 6 6.2 S afety Syste ms . .... ... ... ....... ..... .... . .. . . . .. ... ... . . . .. . .. .. . . ..... . . . .. .. . .. . . 6 7.0 FuelStorage................................................................................................. 7 8.0 Administrative Requirements ............. . . . . . ....... ....... ............. ..... . ........ ...... ...... 7(a) 8.1 Orga niza tion. . ..... ....... .... .. . .... ... . . . . . . . . .. .. . . . . .. . . .. . . . . . . . . . . .. . . . . . . . . . . . . . . 7(a) 8.2 Criticality and Radiation Safety Committee......... .. ..... .............. ............ 7(a) 8.3 Written Procedures... .... .... .... ... . .. .. . ... . .. . . . . . .. . . ... . . . . . . . . . . . . . . .... .8. . . . . . . . . 8.4 Action to be Taken in the Event of an Abnormal Occurrence. ................. 8(a) 8.5 Facility Re cords. ........ ........... .. ... . . . . . . . . . . . .. . . .. . . . . . . .. . . . . . . ... . . . . . .. . . . . . .. . . . . ... . . . 8(a) 8.6 Reporting Requirements................ ..... ........ ... ... .. . ............... . ............ .... 8(b) 9.0 Fa cifity Opera t10n s. ... ............ ...... . .... . . .... .. . . .. . .. . . . . .. .. . . . . . . . . . . . . . .. . .. . . . . . . . . . . . ... . .. . . .. . 10 Q_A D a nne.n, Anne. w.w . www wi wyw .m.6.:nn. .. w .e . . . . . . . . . . . . . . . . . . . O v d v . 4, R.-.Am u.t.m. . .. .wyv.
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3 1 Appendix A License No. R 67 TECHNICAL SPECIFICATIONS for THE TORREY PINES TRIGA MARK F REACTOR Date: September 27,1968 The dimensions, measurements and other numerical values given in these specifications can differ from actual values owing to the normal construction and manufacturing tolerances or normal accuracy of instrumentation. 1.0 DEFINITIONS 1.1 Facility Reccter Shutdc=- Facility means the building housing and disassembled reactor plus systems, components, etc. associated with possession only of the reactor, including fuel storage. Reacter chutdcwn chc!! mean that the rcccter i; cuberiticc! ci c" !!me; by at !cc;t On dc!!ct of rccctivity-1.2 FacilityResetor Secured Facility Reactor secured shall mean that condition whereimno workisin progress involving handling of fuel, or removal of activated or contaminated hardware or material from the facility. (a) The recctcr i: chut dcwn, and (b) nc work i; in progrc : invc!ving hand!!ng Of fuc!, experiment; cr rcccicr cccc rc!cted mcintencnce Operations er removc! cf activated compononic from the pooh 1.3 Facility Rcccict Operation Facility Resetor operation shall mean any condition wherein the facility reactor is not recured chutdown 1.4 Decommissioning Activities Standard Contrc! Rod S!cndard centre! red chc!! =cen :ny contro! red having rack and pinica, - c!cctric motcr dr;ve and scrcm capab!!:tica-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 activities willinvolve the handling, surveying, packaging, and dispositioning of radioactive materials in the facility.
- 1. 5 Possession Only License Status
. Possession Only License (POL) status means that the facility license has been amended to withdraw authorization to operate the reactor and authorize 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 the facility.
Amendment No. 453
1 l l l 1.5 T+ ancient Ocntrel-Rod T+an !cnt control-red-shc!! mecn any centro! red Operated pneumatiea#y-and with+ cram-capabilities-l 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 Abnormal Occurrence-Guperiment An abnormal occurrence isany of the fc!!cwing which Occur; during rccctor possessient Experiment cha!! mcon any device Or matenc! /;hich i: cxposed4e signifkant-radiation from the reactor-endss-net a normc! pcr4-ef4he-+ easter- {a) Any unanticipated or uncontroIIed change in subcritical multiplication during fuel storage or handling.-Routirc E pcrimcnM chclf-mean4hese experiment which have been previcu !y performed in this feastar- I 1 (b) An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy could have caused the existence or the development of a condition which could result in possession of the reactor facility outside the requirements of the 1 Technical Specifications; and-Modified-Routinc Euperiments-sha#-mean j those-experiment; not prewously-performed 4n4his-reacter //hc;c hazards-arc ncither cignificantly-different nor grectcr then tho: for c similar routinc cxpenment-performed at the OcncrabAtomic: TR!GA Reactors-facility-l 1 (c) Release of fission products from a fuel element during fuel storage i l handling. Special-Experiments-shalh+nearbell-experiments-which-ere { not-reutine-er-modified-routine-expenments-4.8 9ecctor-Safety Systems Reaetor-safety-systems + half-mean-thc;c systcras-4nc4uding-thew-associated input-circuits, Ishich crc designcd 10 IFticic c rcccter scram for the primary purpose-ef-pretecting the reac4er: 1.0 Experiment-Sciety Systems Experiment Ocfety-system; chc!! mcen the c cy;tems, including their coccciated input-circuitsr-whictFare-designed-te-mitiate-a-sc+am-for-the-primary-purpose-of proteeteg an experirnent= 1 10--Standard-Thermocouple l A tandctd4hermeeoup!c chcl! mean a checthed chrome! clumc! cr equ: valent thermocoupleambedded in the fuc! nect the fuc! c!cmentsLvertical-midplane-et a-pomt4ess-than-ene-half-the-radial-distance-measured-from-the-eenter-ef-the fuef-body-Amendment No. 45 29 2 i j
I
- 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 fuel and activated / contaminated hardware are removed from the facility, 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-controt4oom 3.3 All air or other gas exhausted from the reactor room during4eector operation shall be released to the environment at a minirnum of 20 feet above ground level. 5 3.4 The reactor room ventilation system shall be separate from the rest of the building ventilation. 3.5 Adequate 4esistence te !eekege of !r from the4eacter reem the!! be ver!!!ed by measurement ennua!!y, (intervaLnot-to-exed 15 months) and anytima4he-roof 4atch has-beenopenedand4eclosed, ror-when a4harcoaLfilter4s4equiredJor4eactor operationsr-Ths4esistance4o air 4eakage-shall-beat 4 east 4/$mheree-6&x40* m sec%, 3.5 During decommissioning activities and while fuel remains in the facility, air ventilation systems shall be operable to ensure the reactor room is maintained at a negative pressure with respect to the surrounding areas. 4.0 REACTOR POOL 1 4.1 The stored reactor fuel-core shall be cooled by natural convective water flow. e rept 2 provided4or-in-Section40Acovering-experiments, 4.2 During reacter e7 ret!cn, Until such time as all fuel has been removed from the pool and the poolis drained as a part of decommissioning, the minimum level of the pool water shall be no less than12 inches at-least 46 feet below the reference at the top of the pool. abeve the top grid-plate, j 4.3 The-pec' efeter ce!!et p!p sha!! not er!end more then " feet be!ce/ 'he top-of4he4eactor poc! v: hen fue! !: being :!ared. !n the more, 4.34 Until such time as all fuel has been removed from the pool and the poolis 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 j over any one calendar month. 1 4,5 The4eactor4ha!Lnotte4perated -while4t+ bulk-poot4emperaturs exceed s 45*C, l 5.0 STORED REACTOR FUEL DESCRIPTION CORE 5.1 No reactor fuel elements or control elements with fuel followers shall be stored in the reactor portion of the pool. The4 ore 4 hall-be-an-assembly-of-uranium zirconiumAydride fue! e!emente p'ered in !!ght ?>ater except ~0 edjacent er non-edjacent pocitione ecupied by-startup40urces rvertice! thimb!es, ve!de, centro!4 oder in-core-experiment &randaabbit facilities, Amendment No. 450 3 L _
(a) Standard corce chc!! bc 0:,00mb!!cc wherein cil49ebelements-are ctandard fact c!cmentc. (b) CpeciaLocrec chat! beelkores-which-aremot-standard-cores: 5.2 Standard fuel elements shalthave 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 1.8H atoms to 1.0 Zr atom (high hyride) (d) Cladding material and cluminum 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800, Hastelloy X, or 0.030 inch aluminum or Zircaloy 5.2.2 Standard Fuel Lifetime Improvement Program (FLIP) fuel (a) Maximum uranium content 9.0 wt% in unirradiated fuel (b) Nominal uranium enrichment 70 % in unirradiated fuel ' (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in ZrHn) (d) Natural erbium content 1.0 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 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-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHn) l l Amendment No. 4539 4 l I
(d) Natural erbium content 0.4 to 1.8 wt%' (homogeneous distribution) (e) Cladding material and 0.020 inch 304 or 304L stainless steel, j minimum thickness Incoloy 800, or Hastelloy-X 1 5.3 Special fuel elements are shalkbe uranium zirconium hydride fuel elements, which are not standard fuel elements, having 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, minimum thickness Incoloy 800, or Hastelloy-X l or 0.030 inch Zircaloy ! (d) Construction shall be such that ! calculated clad temperature j shall not exceed 500 C at the planned operating level 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 enrichment <20% in unirradiated 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 l Hastelloy-X for 0.5 inch nominal diameter
' Scaled according to maximum U-235 content such that a core containing only these elements would require a criticalloading of 2 50 fuel elements.
4(a) l Amendment No. 4539 1 1
'; (d) ' Construction is chc!! be such that the calculated clad temperature does shan not excesd 500 C at planned operating level.
(e) - Special fuel elements with 0.5 inch nominal diameter are cha!! be enclosed in a 0.020 inch metal shroud. The shroud, constructed from one of the above listed cladding materials, has cha!! h0ve a nominal diameter of 1.5 inches. 5.3.4 Any burnable poison used is che!! bo an integral part of the as-manufactured fuel element. A burnable poison is defined as a material used for the specific purpose of compensating for fuel burn-up and/or other long-term reactivity adjustments. J i l 4(b) Amendment No. 4539 l l
4 S O i l ClICI El CB ACAfT 1hte,FT 5.%rC I hsFh k h pyThgiy gygg 00!cted in its entirety
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l i 4 Amendment No. 43 5
r o. 6.0 CONTROL AND SAFETY SYSTEMS l ! 6.1 Control Systems l 64 4 The poison section of the control rods which may remain in the facility sha41 contains borated graphite or stainless steel,84C 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. e,,. 4. .o v. w~m .~~,,~. . w.~m.. . . ~ .,. m a ,~. ,. ,. :~ ., . : m,. ~,, <~. . m i. .m.~. i m m. ~m ,m. ._- . .a
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Amendment No. 454 6
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6 24 Until such time as all fuel elements, control rods, and major ( activated components of the reactor have been removed from the facility, radiation monitoring systems shall be operable as follows: (a) An area radiation monitoring system capable of activating the } evacuation alarm. { (b) When the facilityreaster is not secured, a continuous monitoring system for airborne activity having a readout and audible alarm which can be heard in both the facility-reaster and contro! recmc. 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 alternative or portable radiation monitors.
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6.2.' The-reastor-safety 4ystemc cha!! be ver!Scd to bc Operab!c at ! cast once cach day the reacter ic Operated, un!ccc the Operatiort-extends continucuc!y beyond one day, in which cacc the operability +f4he reactor-safety-system need only be verified-prior 40-theextended operatiork S.2.5 Deleted 6.2.6 Oc!cted When On activated-charosal4ilter ic required for the tccting of i thermionic deviccc, !!c b!cwcr cha!! 50 veri' icd to bc Operable-at4 east i ence cach wcck (intervc! not to excccd ten dayc). A camp!c of4he activated chcrocal shall be tected ccmicnnuallyfat4nter/c!c not to excccd 71/2 months}-to-confirm-acceptab!c !cw !cyc!c of water / humidity content The 'i!!cr f!cw rate chc!! 50 verified-annually to be at !cact460 cfm (interval not to exceed 15 rncaths) 1 ---6-B- Following maintenance or modification of the radiation monitoring control-or reastor-safety systems, the affected system shall be verified to be operable before retuming it to routine ecmmencing-reactor operation. 7.0 FUEL STORAGE 7.1 All fuel elements or fueled devices shall be stored in a safe geometry (k.a less than 0.8 under all conditions of moderation). 7.2 Irradiated fuel elements and fuc!cd experimente 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 or fuc!cd device will not exceed design values. Amendment No. 453 r- 7 1
e l 8.0 ADMINISTRATIVE REQUIREMENTS Until such time as decommissioning activities are completed to the extent that all fuel and major y
' activated hardware has been removed from the facility, the following administrative requirements shall apply, 8.1 Organization The facility shall be under the supervision of the Physicist-in-Charge or his designated alternate, both of whom shall be a licensad senior operators of the facility. The minimum qualification for the Physicist-in-Charge shallinclude 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 alternate, 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: Vice President or Cognizant Vice President Vice Designated Alternate President Director Licensing, Safety
& Nuclear Compliance Criticality Health Physics ---
Physicist-in-Charge --- R Sa Committee Facility Staff ; l Direct Reporting Functional Support / Oversight 8.2 Criticality and Radiation Safety Committee
- a. There shall be a Criticality and Radiation Safety Committee (CRSC). The CRSC or a subcommittee thereof which 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 the4 hat facility.
- b. The Criticality and Radiation 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 deemed 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. Deleted ReviewandapprovaLofexperiments-utilizing 4he4eactor facilities-inaccordance-with-Section404 1-2. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications; I
l 9 l j
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- 24. Determination of whether a proposed change,- tect, or t
exper ment would constitute an unreviewed safety question or a change in the Technical Specifications;
- 34. Review of Facility records:
- 44. Review of abnormal performance of plant equipment and other anomalies; and
- 54. Review of unuouc' or abnormal occurrences and incidents which are Reportable Occurrences under 10 CFR Part 20 and 10 CFR Part 50.
8.3 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 use of independent judgment and action should the situation require such:
- a. Testing and calibration of instrumentation, controls, end radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications.
- b. Emergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support.
- c. Fuel element handling. and experiment !cading er un!ccding,
- d. Maintenance of systems necessary for assuring the integrity of the fuel or otherwise maintaining the reactor in POL status.
- e. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal reactivity 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 by the CRSC. Inserts of 8.4 through 8.6 on the following pages 8(a) and B(b). 9.0 FACit/TY RE.^ CTOR OPERATIONS The following activities shall be conducted in the facility: a) Maintenance, monitoring, control, potection of personnel and security activities as defined in approved procedures (see Section 8.3). 8 f
r: e O. l b) ^ Decommissioning (consistent with an approved Decommissioning Plan). c) Fuel storage, handling, packaging and removalin accordance with approved procedures. l l- n.4 w
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[ . 8.4 Action to be Taken in the Event of an Abnormal Occurrence in the event of an abnormal occurrence, as definedin Section 1.7 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 otherperson notified under Section 8 shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, identified in Section 8.1.
- 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 8.6 of these Specifications.
l 8.5 Facility Opcrcting Records in addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared of at Icast the following items and retained for a period of at least five (5) years: l l
- a. Normal reactor operation and pool status;
- b. Principal maintenance activities;
- c. Abnormal 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 enviromental monitoring surveys;
- g. Fuelinventories and transfers; l h. Facility radiation and contamination surveys; I. Radiation exposures for all personnel; J. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility);
- k. Decommissioning / dismantlement activities.
8(a) Amendment No. 45
8.6 Reporting 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 hours 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, personalinjury, or exposure; 2, Any abnormal occurrences as defined in Section 1.7 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, personalinjury, 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 1.7 of these Specificutions.
- 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 measued value of safety-connected operating charactenstics occurring during possession of the reactor;
- 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 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) possession and storage and (2) changes in facility storage design.
- 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.
8(b) Amendment No. 45 i
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(c) The maximumevailable-excess-reactivity-shall-not-exceedt (1) N4imits-set forth in Sec-tion 0.4.2 when the4otal worth of the experiment (c) docc not-exceed 4he combmed worth of4he-operational-controkedsr disregarding 4he-most-reactiveentrekodrer (2) $1.00 determmed-without4he-experiment (shi-place when the totabwedh of the experiment (c) cxceeds4he combined 'vedh of-the-operationabsentrokeds-disregardmg4he-most-reactive sontrokod: ) (f) Not moro than enc pad of an experiment cha!! be manipulated simultanccus!y. 0.' Special-Gores ! 9.A 1 Spestal-coreeperatione cha!! be carriedeut within the !!mitationseet fodh in Section 0.1 cad 4h3: 0.4.2 Except ac provided in Section 9. A A cpecia! corcs;-with-fuek!cccribed in4estion 5.3, expected to have c temperature-dependent chutdown soef'icient cha!! not be-operated un!ccc the roastivity-shutdown l mechanicn' ic demonctrated40tc !crge enough 'O rcquirc c pu!ced tota! reactivity incedicn of-atleast $2.50 to produce a mcacured fuc! temperature of 700*C cc meccured by c clandard thermoccup!c in the hottect fuc! c!cment Pulcc tectc conducted 0c pad of this demonctration cha!! begin with a reestivity-inccdion of-not-more4han
$4-25-Ond cha!! increccc in incrcment not to excccd $0.25. .^c c condition for operation-alLc'hcr Opcc!c! cores-shaltbe-requ4 red 40 havespulsing-parameter <p that hac been-previcuc!y chown to be 4
greater 4han $1.323 x 10 (AWk)/-por MW O!cment: 0.4.3 Prior 4o-pulsing-a-speciaLcore-whichtassenerated-more4han40 MW-brs-of-energy-since-the4ast-inspectionef-the-speciaf-fuel elements <ontained4hereincthosespeciabfuc! c!cments-havmges instrumentation-shaltbe-measured-for4engthend-bend-Specialfuel elements-found4e-be-damagedes-defined 4n-Section444{d}r&5-2fb) or-644(o)-shalbnot-be-used4neny-further-reactor-operation: t 0.4.A Up4e40speciaLfuetelementc, cc cct-forthan-Section-5.3.2 may be added40 a-corerstandarder-spesiatrif4he4emperature-shutdown-co-efficient 4s-demonstrateckbyt $ (c) The-core-shalltave-previouslyrwithout4ho4nsertedelementsr 1 i been-demonstrated 4esatisfy4he-requirementsef-Section O. A. . *.) . _= d (b) Thecereshallrwith4he-speciatelements4nsertedrbe demonstrated 40-have-a-power-coefficient 4 reactivity 40ss-with l increasing-power}4 hat-is4argeenough4o-reasonably-assure that4he-shutdown-coefficient 4s-atleast-a.rlarge-as4 hat specified4n-Sestion 0. A.2. Amendment No. 29 10
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explosives + 1 The radiography of explosivesprecent in the beam (s) ateny-cnc time chalkbe !!mited40squantityeft o i (a) ve poundsef-explosive-(equivc!cnt TNT) if the l individual-devices-containeo-more4han 0 25 . pounds (114 gramstror , (b) up404Wo-pounds-ofexplccive (cquiva!cnt TNT) - - prm,, ~.. .,iama. . .u. ~ . ,~,.,.i. , ,., ,,,.e,i. ,gle-device 4s n
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1 1 Amendment No. 16
TRIGA Reactors Facility TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility License No. R-38 MAY 1999 Proposed Amendment 36
. TABLE OF CONTENTS Page No. 1.0 D e fi nitio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. . .1 . . .. . . . . . . . . . . . . . . . . . . . . . 2.0 Site.................................................................................... 2 3.0 Reactor Building.......... ..... ........... ..................................... 2 4.0 Re actor Pool . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .2. . . . . . . . . . . . . . . . . . . . . . . . . 5.0 Re actor Fu el . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2. . . . . . . . . . . . . . . . . . . . . . 6.0 - Control and Safety Systems ....... . .... ..... ......... . .... ... ....... .. ... ... 2 6.1 Control Systems . .. .. . . . .. . . . . ... . . .... . . . . . . . . . .... ... .. . . .. . . .. .. . . . ... .. . . .. . ... . . . 2 6.2 Safety System s . . . .. . . .... . .. . . . .... . .... . ... . . . . . . ... .. . ...... . . .. . . . . . . . . . . . . . . .. ... . . 3 7.0 Administrative Requirements ........... ....................................... .......... .... 3 7.1 Organization ...... ....... ....... .. . .. ... . . ... .. .. . . ...... . . .. . . . .... . .. . .. . ... . .. . . . .. 3 7.2 Criticality and Radiation Safety Committee ............ ......... . . ...... .... 4
' 7.3 Written Procedu res . . . ... .. .. .. . . . . . .. . . .. .. . ..... .. .. . . .. ....... . .. . ... ... . .. .... 5. . .. . .
. 7.4 Action to be Taken in the Event of a Reportable Occurrence .......... 6 7.5 Facility Record s ... ...... . . ..... . .. ...... . . .. . ... . .. . . . . .. . .. . . . . .. . . .. . .. . . . ..... . . . . . . .. 6 7.6 Reporting Requirements ..... ....... .. ............. .. .. ... ........... ..... ....... 7 8.0 Facility Operations....... ..... ........... ..... ...... . . ... ..... .. ...... .. . . . . . ... .. . . . ... .. ... . . 8 l
s i Amendment No. 36 ;
APPENDIXA License No. R-38 TECHNICALSPECIFICATIONS FOR THE TORREY PINESTRIGAMARK1 REACTOR DATE: JANUARY 21,1972 1.0 DEFINmONS 1.1 Facility Facility means the building housing and disassembled reactor plus systems, components, etc. associated with possession only of the reactor. 1.2 Facility Secured Facility secured shall mean that condition where no work is in progress involving removal of activated or contaminated hardware or material from the facility. 1.3 Facility Operation Facility operation sha!! 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 activities willinvolve the handling, surveying, packaging, and dispositioning of radioactive materials in the facility. 1.5 Possession Only License Status Possession Only License (POL) status means that the facility license has been amended to withdraw authorization to operate the reactor and authorize 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 Amendment No. 36 e
r . j i 1.7 AbnormalOccurrence An abnormal occurrence is an observed inadequacy in the implementation of either l 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 possession of the reactor facility outside the requirements of the Technical Specifications. l 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 REACTORBUILDING Until such time as all activated / contaminated hardware has been removed from 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. l l 3.3 During decommissioning activities, air ventilation systems shall be operable to ensure the reactor room is maintained at a negative pressure with respect to the surrounding areas. 4.0 REACTORPOOL 4.1 Until drained as a part of decommissioning, the minimum level of the pool water shall be no less than 12 inches below the reference at the top of the pool. 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 5.1 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 SAFE'iY 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. 2 Amendment No. 36
6.2 Safety Systems Until such time as all major activated components of the reactor have been removed from the facility, radiation monitoring systems shall be operable 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 periods of other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate alternate or portable 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 REQUIREMENTS Until such time as decommissioning activities are completed to the extent that all major activated hardware has been removed from the facility, the following administrative requirements shall apply. 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 alternate, 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: 3 Amendment No. 36
4 Vice President or Cognizant Vice President Vice Designated Alternate President Director Licensing, Safety
& Nuclear Compliance Criticality Health Physics - - -
Physicist-in-Charge --- ad on gay l Committee Facility Staff Direct Reporting
-- Functional Support / Oversight l l
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, l considering their experience and education with regard to the various aspects l 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 accordance with a i 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 deemed appropriate.
- 2. Having a quorum when a majority of the members attend.
4 Amendment No. 36
- 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 would constitute an j unreviewed safety question or a change in the Technical Specifications; i
- 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 use of independent judgment and action should the situation require such: I
- a. Testing and calibration of instrumentation, 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 evacuation, reentry, recovery, and medical support.
- c. Maintenance of systems necessary maintaining the reactor in POL status.
- d. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal changes.
- e. 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 10CFR50.59) may be 5 Amendment No. 36
t I made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed by the CRSC. I 7.4 Action to be Taken in the Event of a Reportable Occurrence i 1 in the event of an abnormal occurrence, as defined in Section 1.7 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 j 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 l 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 POL status; i
- b. Principal maintenance activities;
)
i
- c. Abnornial occurrences
- d. Equipment and component surveillance activities required by the Technical ,
Specifications; I
- e. Gaseous and liquid radioactive effluents released to the environs;
- f. Off-site environmental monitoring surveys; !
l
- g. Facility radiation and contamination surveys;
- h. Radiation exposures for all personnel;
- i. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility).
- j. Decommissioning / dismantlement activities.
i 6 Amendment No. 36
t 7.6 Reporting Requirements In addition to the requiremenfs of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC as follows:
- a. A report within 24 hours 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, personalinjury, or exposure;
- 2. Any abnormal occurrences as defined in Section 1.7 of these Specifications.
- b. A report within 10 days in writing to the Document Control Desk, USNRC ,
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 1.7 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) possession and (2) changes in facility design.
I 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 7
Amendment No. 36
r' . 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.
8.0 FACILIT(OPERATIONS The following activities shall be conducted in the facility: a) Maintenance, monitoring, control, protection of personnel and security activities as defined in approved procedures (see Section 7.3). b) Decommissioning in accordance with approved procedures (consistent with an i approved Decommissioning Plan). l l 8 Amendment No. 36
TRIGA Reactors Facility (" REDLINED" VERSION - FOR INFORMATION ONLY) TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility License No. R-38 MAY1999 Proposed Amendment 36
e
.' TABLE OF CONTENTS Page No.
1.0 D e fi ni tio n s . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .1. . . . . . . . 2.0 Site............................................................... . . . . . . . . . . . . . . . . 65 3.0 - Reactar Bullding-Peet . .................................... . . . . . . . . . . . . 65 4.0 R e a ctor Pool-Gore .. . .. .... . . . . . . . .. ... . . . .. .. . . . . . . .... . . .. . .. ... ... . . . . . . 65 5.0 Reactor Fuel. . . . . . . . . . . . .. . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . .. .. . . . . . . . . . 65 6-6.0- Control and Safety Systems . . .... .. .............. .... .. ... . ...... .. .. ..... .... 87 66.1 Control Systems ..... ........ ........... ............................... 87
- 66. 2 S afe ty S yste m s . .. . ... . . .. . .. .. . . . . . . . . . .. . . ... .. . . . . . .. . . . . . . . . . . . . . . 87 e, . o, .a.n
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. 4.O 79.0 Ad ministrative Controls ... ..... . .. . ..... . . . . .... . ...... ..... .. ...... . .... .. . 176 79.1 Org a nization ... ... .. . .. . . . ... . . .. . . . .. .. . . .... .. .. ....... .. ... . ... .. .. ... . . .. . . . 176 79.2 Criticality and Radiation Safety Rcvic':: ',.',ommittee ....... . .. . .. . . 187
' 79.3 Written Proced u res ... . .... . .... ... .. .. ...... ... ...... ........ ..... . . . . 198 79.4 Action to be Taken in the Event of a Reportable Occurrence ... . . 2049 79.5 Plant Operating Records ... ..... ....... . ... ..................... . .... ... ....... 2049 79.6 Reporting Requirements ................. ........ .... ...... . . .. ..... ... . ..... 2120
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f
- APPENDIX A LICENSE NO. R-38 TECHNICAL SPECIFICATIONS FOR THE TORREY PINES TRIGA MARK l REACTOR DATE: JANUARY 21,1972 i 1.0 DEFINITIONS .
l 1.1 Facility Rcactcr Shutdc=- Facility means the building housing and disassembled reactor plus systems, components, etc. associated with possession only of the reactor. Rcactor chutd = ; ch \f mean that the rcactor i; Ouberi'ical ci :ll t:m;; by at lca t One dO!!ct Of 7000tivity. 1.2 Facility Rc00tcr Secured Facility R ctcr secured shall mean that condition where no work is in progress involving removal of activated or contaminated hardware or material from the facility. (c) The rcccier i; hut dcwn, cad
-(b) nc wc-h !; in progre;; i ve!v:ng handling of fue! experiment; Or reccier 00r0 related main'; nan;; cparatica;, or :mov ! cf::!!v ::d hardwar from the p0:!.
1.3 FacilityReester Operation Facility Rc:010 operation shall mean any condition wherein the facility rc;;ter is not secured chutscw-1.4 Dccommissioning Activities Decommissioning activities shall meanthose activities required to remove the facility safaly 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 activities willinvolve the handling, i surveying, packaging, and dispositioning of radioactive materials in the facility. \
- 1. 5 Possession Only License Status i i
1 Possession Only License (POL) status means that the facility license has been i amended to withdraw authorization to operate the reactor and authorize possession only of the reactor, and that the fuel has been removed from the reactor and is maintained in ; a safe and secure manner inan approved location outside the Mark I facility. i 1
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l I 1 , i 1 1 1 \ l 5 l Amendment No. 365 4 I I
( ) - l : 2.0 SITE i A minimum radius of 120 feet from the approximate center of the TRIGA Reactor Facility building shall define the exclusion area. l 3.0 REACTOR BUILDING Until such time as all activated / contaminated hardware has been removed from 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 ^dequate rec!:tance to !cakage of c!r from the reactor reem chc!! be-ver4fied i annua!!y, (intervc! not to excccd 15 months)-and-anytime-the-reef-hatch-has i beeupened and rec!cced. 3.3 During decommissioning activities, air ventilation systems shall be operable to ensure the reactor room is maintained at a negative pressure with respect to l the surrounding areas. 43.0 REACTORPOOL i 43.1 Until drained as a part of decommissioning, the minimum level of the pool water shall be no less than 12 inches below the reference at the top of the pool. The reactor core cha!! be coc!cd by natura! cervcctive water-4 Tow Obove the top of grid plate. l 43.23 The poc! water cut!ct pipe chc!! not extend more than 8 fcci bc!cw the top of the reacter poc!'vhen fuc! ic in the cerc. 4.2 Until such time as the pool wateris drained as a part of decommissioning, ell fuc! c!cmontc, contro! rode--and mcjor cctivc!cd componcntc cf the rccctor havc bocn removcd from the rocciarpoc! cnd, 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, j 3.5 The reacter cha'! not be-operated vti!c the bulk-poc! temperature-exeeeds 65eg_ 5.0 REACTOR FUEL 1 l 5.1 No reactor fuel elements or control elements with fuel followers sheII be located in, stored in, or moved into, the reactor core structure or reactor facility. l l l 6 Amendment No. 365 I 1 l
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1 7 Amendment No. 365
y 65.0 CONTROL AND SAFETY SYSTEMS 65.1 Control Systems l The poison section of the control rods which may remain in the facility shan contains L borated graphite or stainless steet, 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 fueler non-fuel followers. 5.1.2 Ne reactor fuc! O!cmente or centrc! c!cment: with fuc! fc!!cv/ crc cha!! bc
!cccted in, ctored !n, er mcycd into, the reactor core ctructure.-
5.1.3 dc!ctc 5.4 A dc!cic 5.1.5 dc!ctc 1 65.2 Safety Systems 1 6:2.4 Se reacter cafety cycteme and the acccciated inctrumente neccccorj to provide the ceram: !!cted !r Tcb!c ' cha!! bc Operab!c during reacter Operatice 5.2.2 During reacter Operation, the app!!ceb!c Ster!cck: chever 5 Tab!c ! che!! be o pcr b!c. 5-24 Until such time as all fuc! c!cmcntc, con!rc! rodc, and major activated l components of the reactor have been removed from the facility, radiation monitoring systems shall be operable as follows: i
- a. An area radiation monitoring system capable of activating an evacuation alarm.
I b. When the facility--reaeter is 'not secured, a continuous monitoring i system for airbome activity having a readout and audible alarm which can ce heard in the facility reacter and centro! recmc.
- c. dc!:tc 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 periods of other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate alternate or portable radiation monitoring system (s).
l l l 8 Amendment No. 365
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6.0 FUE4: STORAGE i 6.4 ,
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16 Amendment No. 365
4 79.0 ADMINISTRATIVEREQUIREMENTSCONrrgots Until such time as decommissioning activities are completed to the extent that all major activated hardware has have been removed from the facility, the following administrative requirements shall apply. 79.1 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 alternate, 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: Vice President Cognizant Vice President Vice Desi nated Alternate President Director I Licensing, Safety
& Nuclear Compliance Criticality a "
Health Physics - - -- Physicist-in-Charge --- ga t Committee Facility Staff Direct Reporting
--- Functional Support / Oversight 17 Amendment No. 365
i 79.2 Criticality and Radiation Safety Committee
- a. There shall be a Criticality and Radiation Safety-Safeguards Committee (CRSC).
The CRSC or a subcommittee thereof -which shall review activities of the i 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 that facility,
- b. The Criticality and Radiation 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 deemed 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.
4-delete
- 5. dc!cto E. dc!cte '
- 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:
-b Review and-epproval-of-experiments-utdizing the reaster-facirh asocidence with-Section 8.1.
18 Amendment No. 365
- 12. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications;
- 23. Determination of whether a proposed change;-tect, er experiment would constitute an unreviewed safety question or a change in the Technical Specifications;
- 34. Review of Facility records;
- 45. Review of abnormal performance of plant equipment and other anomalies; and
- 56. Review of unusual or abnormal occurrences andancadents which are Reportable Occurrances under 10 CFR 20 and 10 CFR 50.
79.3 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 use of independent judgment and action should the situation require such:
- a. Testing and calibration of instrumentation, controls, and radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications,
- b. dc!ctc be. Emergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support.
---d. Fuel c!cment and-experiment loading or unloadir+
- c. dc!cto l
of. Maintenance of systems necessary for assuring the integrity- cf the fuc!-or I etherwise maintaining the reactor in POL status. l l dg. Actions to be taken to correct specific and foreseen potential malfunctions of l systems or components, including responses to alarms and abnormal-reasttvity changes.
- e. Decommissioning activities (consistent with an approved Decommissioning Plan).
19 l Amendment No. 365 1
r 1 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 10CFR50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed by the CRSC. 79.4 Action to be Taken in the Event of a Reportable Occurrence in the event of a abnormaf rcpedebb occurrence, as defined in Section 1.740 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 79.4a shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, identified in Section 79.1.
- 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 79.6 of these Specifications.
79.5 Facility P!cnt Opercting 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 I retained for a period of at least five (5) years:
- a. Normal reactor plant operation and POL status;
- b. Principal maintenance activities;
- c. Abnorma/ Repedeb!c occurrences;
- d. Equipment and component surveillance activities required by the Technical l Specifications;
- e. Gaseous and liquid radioactive effluents released to the environs; 20 Amendment No. 365
P
- f. Off site environmental monitoring surveys;
- g. Nc! !~/cnterice and trencfers gh. Facility radiation and contamination surveys; h I. Radiation exposures for all personnel;
-h Experimente pedermed with the rcccter; i
l ik. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility). J. Decommissioning / dismantlement activities. 79.6 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 hours 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, personalinjury, or exposure;
- 2. Any abnormal occurrences as defined in Section 1.740 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 i damage, personal injury, or exposure; the written report (and, to the extent possible, the preliminary telephone or facsiml/e report) shall describe, 1 analyze and evaluate safety implications, and outline the corrective ! measures taken or planned to prevent reoccurrence of the event. i
- 2. Any abnormal occurrence as defined in Section 1.740 of these Specifications, j
1 1 21 Amendment No. 365
e
- c. A report within 30 days in writing to the Document Control Desk, USNRC ,
Washington, D.C. 20555: 4, .A.m.
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S. . curnmarj of4he-nature-end-amount-of-rad +oactive efflucat" ^'^~^d I cr diccharged to the environc beyond the effective control of the licenccc Oc meccured at er prict to the point-of-such re!cccc or diccharge.
- 7. ^ deccription of any environmentc! cuvcyc performedeutsde4he fasd+ty-
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- 8. . , cummarj of radiction expecurec rcccived by the facility pere ^^^^' ^^d vic!! crc, including the datcc and timo Of cign"icant expecurc, and a brief ;
cummarj cf the rece!!c cf rad:ction and contam!nction cur /cy performed v?Si^ the faci!!!y. df. Commencing in 20004999, a routine report in writing to the Document Control i Desk, U.S. Nuclear Regulatory Comrnission by April 15 of each year, providing the following information:
- 1. A brief narrative summary of: (1) possession and-sterage and (2) changes in facility sterage design.
- 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 experimonts 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.
1
- 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 conductedin the facility: a) Maintenance, monitoring, control, protection of personnel, and security activities as definedin approvedprocedures (see Section 7.3). b) Decommissioning in accordancae with approved procedures (consistent with an approved Decommissioning Plan). 23 Amendment No. 365
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