ML20028B283
| ML20028B283 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 11/24/1982 |
| From: | Rickard D DEFENSE, DEPT. OF, DEFENSE NUCLEAR AGENCY |
| To: | Eva Hill, Hoyt H, Schink D Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8211300241 | |
| Download: ML20028B283 (3) | |
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,,y- DEFENSE NUCLEAR AGENCY c m nxom . Cg yp-WASHINGTON, D.C. 20305 g-
'82 tiDV 29 A8 29 NOV 2 41982 Vf,v.m" u
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- . . _l Helen Hoyt, Esq. Chairman Mr.' Ernest E. Hill Administrative Judge Administrative Juda?
Atomic Safety and Licensing Board Lawrence Livermore Laboratory U.S. Nuclear Regulatory Commission University of California Washington, DC 20555 P.O. Box 808, L-123 Livermore, CA 94550 Dr. David R. Schink Administrative Judge Department of Oceanography Texas A&M University College Station, TX 77840 In the Matter of Armed Forces Radiobiology Research Institute (TRIGA-Type Research Reactor) Renewal of Facility License No. R-84 Docket No. 50-170
Dear Administrative Judges:
Enclosed is a copy of AFRRI's Emergency Plan for its TRIGA Reactor Facility. This plan was filed with the NRC on November 3, 1982. Service was delayed as a result of a communications mix-up with the NRC Staff as well as a need to print additional copies of the plan. I trust the delay will pose no serious problems. Sincerely, DAVID C. RICKARD Deputy General Counsel cc (w/ encl): Service List 8211300241 821124 PDR ADOCK 05000170 0 PDR <
00LKETED 09RC UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSgN O 29 A8:29 BEFORETHEATOMICSAFETYANDLICENSINGBOARDyjk[ 00;n:- 9/$.itlCI In the Matter of ARMED FORCES RADIOBIOLOGY Docket No. 50-170 RESEARCH INSTITUTE (Renewal of Facility (TRIGA-Type Research Reactor) License No. R-84) CERTIFICATE OF SERVICE OF AFRRI'S 3 NOVEMBER 1982 FILING I hereby certify that true and correct copies of the foregoing "AFRRI EMERGENCY PLAN FOR TRIGA REACTOR FACILITY" were mailed this 24th day of November, 1982, by United > States Mail, First Class, to the following: Judge Helen Hoyt Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Ernest E. Hill Administrative Judge Lawrence Livermore Laboratory University of California P.O. Box 808, L-123 Livermore, CA 94550 Dr. David R. Schink Administrative Judge Department of Oceanography Texas A&M University College Station, TX 77840 Mr. Richard G. Bachmann, Esq. Counsel for NRC Staff U.S. Nuclear Regulatory Commission Washington, D.C. 20555
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Laura W. S. Macklin, Esq. . s Institute for Public Representation , Georgetown University Law Center i'
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600 New Jersey Avenue, N.W. Washington, D.C. 20001 Elizabeth B. Entwisle, Esq. - 237 Hunt Road Pittsburgh, PA 15215 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission 3 Washington, D.C. 20555 Atomic Safety and Licensing Appeal Panel (5) U.S. Nuclear Regulatory Commission. Washington, D.C. 20555 , Secretary (3) U.S. Nuclear Regulatory Commission ATTN: Chief, Docketing and Service Section Washington, D.C. 20555 . 4 DAVID C. RICKARD , Counsel for Licensee 3 P t
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N 4 PREFACE
! This Emergency Plan was prepared in accordance with proposed Revision 1 to USNRC Regulatory Guide 2.6 " Emergency Planning for Research and Test Reactors,"
dated March 1982(1) specifically employing the implementing guidance and criteria set forth in American National Standard ANSI /ANS 15.16, " Emergency Planning for Research Reactors," Draft 2, dated 29 November 1981(2) and NUREG 0849, " Standard Review Plan
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for the Review and Evaluation of Emergency Plans for Research and Test Reactors," dated May 1982(3), 3 O e
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CONTENTS ' Page
1.0 INTRODUCTION
1 1.1 SCOPE 1 1.2 PURPOSE 2
= 1.3 GENERAL FACILITY AND SITE DESCRIPTION 2 1.3.1 STTE DESCRIPTION 2 1.3.2 FACILITY DESCRIPTION 5 1.4 CREDIBLE ACCIDENTS FOR THE AFRRI TRIGA REACTOR 7 2.0 DEFINITIONS - 9 3.0 ORGANIZATION AND RESPONSIBILITIES 19 3.1 INTERACTIONS WITH OFFSITE GOVERNMENTAL ORGANIZATIONS 20 3.2 REACTOR EMERGENCY ORGANIZATION 21 3.3 AGREEMENTS WITH OFFSITE AGENCIES 25 3.4 REACTOR EMERGENCY RESPONSE ORGANIZATION AND EXTENSIONS 25 3.5 PROLONGED EMERGENCIES AND MANAGEMENT ENDURANCE 27 3.6 REACTOR EMERGENCY DIRECTOR: AUTHORITY AND RESPONSIBILITY 27 3.7 EMERGENCY IMPLEMENTATION POSITIONS: AUTHORITY AND RESPONSIBILITY 28 3.7.1 EMERGENCY ACTION STATION (EAS) COMMANDER: AUTHORITY AND RESPONSIBILITY 28 3.7.2 SPECIAL ADVISOR ON EMERGENCY CONDITIONS (SAOEC): AUTHORITY AND RESPONSIBILITY 30 3.8 EMERGENCY COORDINATOR 30 3.9 INFORMATION RELEASES TO THE NEWS MEDIA AND PUBLIC 31 3.10 RADIATION / RADIOLOGICAL ASSESSMENT 31 3.11 DOWNGRADING OF EMERGENCY CLASSIFICATION, TERMINATION j OF EMERGENCY, AND RECOVERY DECISIONS 32 3.12 RECOVERY OPERATIONS 32 l
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l Page 1 3.13 AUTIIORIZATION OF PERSONNEL EXPOSURES BEYOND OCCUPATIONAL LIMITS 33 4.0 EMERGENCY CLASSIFICATION SYSTEM 34 - - 4.1 EVENTS LESS SEVERE THAN THE LOWEST CATEGORY (CLASS 8) 34 4.2 NOTIFICATION OF UNUSUAL EVENT (CLASS 1) 35 4.3 ALERT (CLASS 2) 36 4.4 SITE AREA EMERGENCY (CLASS 3) 36 4.5 GENERAL EMERGENCY (CLASS 4) 36 4.6 IMPLEMENTING PROCEDURES 37 5.0 EMERGENCY ACTION LEVELS (EALs) 38 6.0 EMERGENCY PLANNING ZONE (EPZ) 42 7.0 EMERGENCY RESPONSE 43 7.1 EVENTS LESS SEVERE THAN THE LOWEST CATEGORY (CLASS #) 43 7.1.1 ACTIVATION OF THE EMERGENCY ORGANIZATION 43 7.1.2 ASSESSMENT ACTIONS 44 7.1.3 CORRECTIVE ACTIONS 45 7.1.4 PROTECTIVE ACTIONS 46 7.2 NOTIFICATION OF UNUSUAL EVENT (CLASS 1) 46 7.2.1 ACTIVATION OF THE EMERGENCY ORGANIZATION 46 7.2.2 ASSESSMENT ACTIONS 46 7.2.3 CORRECTIVE ACTIONS 47 , 7.2.4 PROTECTIVE ACTIONS 48 7.3 ALERT (CLASS 2) 50 7.3.1 ACTIVATION OF THE EMERGENCY ORGANIZATION 50 7.3.2 ASSESSMENT ACTIONS 51 7.3.3 CORRECTIVE ACTIONS 51 7.3.4 PROTECTIVE ACTIONS 52 8.0 EMERGENCY FACILITIES AND EQUIPMENT 53 w
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8.1 EMERGENCY SUPPORT CENTER (ESC) 53 8.2 RADIATION / RADIOLOGICAL ASSESSMENT EQUIPMENT 57 8.3 DECONTAMINATION, FIRST AID, AND MEDICAL FACILITIES 58
~ . 8.3.1 DECONTAMINATION FACILITIES 58 8.3.2 FIRST AID 59 8.3.3 AMBULANCE SERVICE 60 8.3.4 NNMC HOSPITAL 60 8.3.5 OTHER MEDICAL AND RADIOLOGICAL SUPPORT 61 8.4 EMERGENCY COMMUNICATIONS 61 8.5 EMERGENCY MESSAGE FORM (EMF) 62 8.6 ONSITE EMERGENCY CACHES 64 9.0 RECOVERY 67 10.0 MAINTAINING EMERGENCY PREPAREDNESS 68 10.1 TRAINING AND DRILLS 68 10.1.1 PERSOFNEL TRAINING AND RETRAINING 68 10.1.2 DRILLS 09 10.1.3 EVALUATION OF DRILLS 69 10.2 EMERGENCY PLAN REVIEW AND UPDATE 70 -
10.3 MAINTENANCE AND SURVEILLANCE OF EMERGENCY EQUIPMENT 71 11.0 WRITTEN PROCEDURES 73 11.1 ESTABLISHMENT OF WRITTEN PROCEDURES 73 11.2 REVIEW AND UPDATE OF PROCEDURES 74
12.0 REFERENCES
75 APPENDIX A APPENDIX B iv
LIST OF FIGURES Page(s) Figure 1.1 AFRRI Site Plan, Showing Annull and Sectors Relative to the AFRR1 Stack 3 Figure 1.2 AFRRI Site Plan, Showing the AFRRI Complex and Environmental Monitor Locations 4 Figure 2.1 AFRRI Floor Plan, Third Level, Showing the Reactor Operations Boundary 12 Figure 2.2 AFRRI Floor Plan, Second Level, Showing the Reactor Operations Boundary 13 Figure 2.3 AFRRI Floor Plan, First Level, Showing the Reactor Operations Boundary 14 Figure 3.1 Configuration and Augmentation of the AFRRI Reactor Emergency Organization 25a Figure A.1 Example of the Potential Full-Scale AFRRI Emergency Organization'(from enclosure 4 to AFRRI Instruction 3020.2G, "AFRRI Emergency Evacuation and Fire Plan," dated 30 September 1982) App A LIST OF TABLES Table 5.1 Emergency Classification Guide 39-41 Table 10.1 Maintenance and Calibration Schedule for Reactor Facility Safety and Radiation Detection / Measuring Equipment 72 1 v
EMERGENCY PLAN FOR THE AFRRI TRIGA REACTOR FACILITY, LICENSE R-84
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DOCKET NO.: 50-170
1.0 INTRODUCTION
1.1 SCOPE This Emergency Plan is designed to ensure adequate respo,nse capabilities to emergency situations involving the Armed Forces Radiobiology Research Institute (AFRRI) TRIGA Mark-F Reactor Facility. It is an integral component part of a larger AFRRI Emergency Plan (AFRRI Instruction 3020.2, "AFRRI Emergency Evacuation and Fire Plan") and utilizes, where possible, the emergency organization and procedures that are widely practiced and understood by AFRRI and National Naval Medical Center (NNMC) emergency response teams. It should be pointed out that this Plan deals cxelusively with emergency situations involving the AFRRI TRIGI. Reactor Facility and tlie attendant emergency responses that are required due to the u..ique nature of the l rtactor facility and the credible accidents that might arise within the reactor facility. This Emergency Plan has been reviewed by the AFRRI management and will be cppropriately activated and Implemented, in lieu of any other emergency plan, for any and all emergency situations involving the AFRRI Reactor Facility. It should be pointed out, however, that the AFRRI Emergency Director (Emergency Command Post Commander) l has the authority to deviate from the generally outlined assessment, corrective, and protective actions specified in Section 7.0 of this Plan as well as the detailed internal implementation procedures at AFRRI, as necessary, based on the actual emergency situation that exists. l l R
1.2 PURPOSE This Emergency Plan establishes provisions for coping with emergency situations involving only the Armed Forces Radiobiology Research Institute (AFRRI) TRIGA Mark-F Reactor Facility. The necessary emergency elements and their interrelationships are
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identified and discussed from an overall perspective. Actual detailed emergency , implementation procedures, although not explicitly described herein, are established, identified, and referenced in this Plan. This approach provides flexibility to the AFRRI fccility emergency staff in coping with a wide spectrum of emergency situations that might involve unusual or unanticipated conditions without requiring frequent revisior s to this Plan. Provisions for reviewing, modifying, verifying, and approving these referenced detailed emergency implementation procedures are spelled out in the Plan to assure that adequate measures to protect the staff and the general public in the event of an emergency are in effect at all times in conformance with 10 CFR--SVAppendirE, Regulatory Guide 2.6, ANSI /ANS 15.16 and this Emergency Plan. Likewise, provisions for the periodic review, test, verification, and modification (if necessary) of this Emergency Plan are explicitly established herein. 1.3 GENERAL FACILITY AND SITE DESCRIPTION 1.3.1 SITE DESCRIPTION This Plan applies only to emergency situations involving the AFRRI Reactor Facility which is housed within a separate building (Building 42A) that is part of the AFRRI complex on the grounds of the National Naval Medical Center (NNMC), approxi- . mately 3 miles north of the Washington, D.C.-Maryland boundary in Bethesda, Maryland. NNMC is bounded on the west by Wisconsin Avenue; on the south by Jones Bridge Road; on the north by the Convent of the Sacred Heart, Interstate 495 (beltway), and Rock Creek Park; and on the east by Perimeter Road and Hawkins Lane. (See Figures 1.1 and 1.2). The AFRRI site, which encompasses all of the buildings,and facilities making up the AFRRI complex, is located in the southeast quadrant of NNMC. It is bounded on the 2
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j! g-- )(i/ _- AFRRi site qlf - I c e ' M AFRRtCOMPLEX 9 ENVIRONMENTAL MONITOR (S) Figure 1.2 AFRRI Site Plan, Showing the AFRRI Complex and Environmental Monitor Locations 1 l 1 1 4
i south by Palmer Road South; on the west and north by Stone Lake Road; and on the east by a circular are extending from Stone Lake Road, at the northernmost corner of the AFRRI "N" lot parking area, clockwise to the intersection of Palmer Road South and Grier Road. (See Figures 1.1 and 1.2.) Within this area, AFRRI has assured jurisdiction and control of activities. 1.3.2 FACILITY DESCRIPTION AFRRI is a tri-service military organization, subordinate to the Defense Nuclear Agency, responsible for conducting scientific research in the field of radiobiology and rslated matters essential to the support of the Department of Defense (DoD). In general, the AFRRI reactor serves as a mixed neutron and gamma source for DoD radiation rtsearch. In particular, it is the primary neutron source for radiobiology research and r:dioisotope production in support of medical research within the DoD. Historically, the AFRRI reactor has averaged approximately 1000 reactor power operations per year with en associated average burnup of about 30 Mw-hrs per year. These figures are considered representative and are not anticipated to change significantly in the future. The AFRRI reactor is a TRIGA (Training, Research, _ Isotope Production, General _A_tomics) Mark-F pool-type thermal research reactor, capable of both pulsed and steady-state operation at a variety of locations in the pool. Designed and built by General l l Atomics, it first achieved criticality on 28 June 1962 with aluminum-clad TRIGA fuel. In 1965, standard stainless-steel-clad TRIGA fuel was installed, which continues to be utilized. The AFRRI reactor is IIcensed by the U.S. Nuclear Regulatory Commission I- (USNRC) to operate at steady-state power levels up to a maximum of 1.0 Mw(t) and to pulse with step reactivity insertions (above delayed critical) up to a maximum of 2.8%
- a k/k ($4.00).(5) The broad utility of the AFRRI Reactor Facility is derived from its i
varied and unique exposure facilities and its flexible capability to operate either in the steady-state or pulse mode at a variety of locations within the pool. The exposure
facilities available for use include two large dry expot are rooms, a pneumatic tube system cf eight tubes, an in-core experimental tube, the pool .tself, and 18 small holes (0.25-inch diameter) in the upper grid plate.
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The reactor core, which is cooled by upward natural convective water flow, is located under approximately 5 meters of water, and is movable laterally within an open , cloverleaf-shaped pool approximately 4.2 meters across the major lobes, approximately 3.9 meters across the minor lobes, and 5.8 meters deep. The reactor core can be operated at any horizontal pool location (near the bottom of the pool) along the axis of the major lobes. Core movement is accomplished via a motor-driven core support dolly carriage mounted on rails above the pool surface. The reactor core can accommodate up to 87 standard stainless-steel-clad TRIGA fuel elements loaded in concentric rings to form an effective cylindrical active core region with a diame,ter of approximately 0.43 meter and a height of approximately 0.38 meter. The central 0.38-meter-long active fuel-moderator region of each fuel element contains a homogeneous mixture of uranium-zirconium hydride (U-ZrH1 ,7) with 8.5 weight
- percent uranium enriched to less than 20% in uranium-235. The nominal U-235 fuel loading per element is approximately 38.0 grams. In addition to the core, six fuel storage racks are provided within the reactor pool at fixed locations along the inside surface of the tank. Each fuel storage rack is located at least 9 feet below the normal pool water surface and accommodates up to 12 elements in a neutronically safe and adequately cooled configuration.
The A. FREI reactor core and fuel storage racks are accessible only from the pool surface within the reactor room. The reactor room not only has physical barriers - separating it from the regtetor control room and the rest of the AFRRI but also its own separate isolatable air volume for confinement isolation. The reactor room air volume is cutomatically isolated, via the closing of fail-safe ventilation dampers, upon receipt of a high-level alarm of the reactor room continuous air monitor (CAM), which continuously
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surveys air from directly over the core just above the pool water surface. Isolation of the reactor room air volume can also be manually initiated by an operator in the control room. When isolated, the reactor room is maintained at a negative pressure with respect to the rest of the AFRRL The reactor building (Building 42A), which includes the reactor room, has its own vcntilation system, which exhausts air through high-efficiency particulate air (HEPA) cbsolute filters to the AFRRI stack for discharge at a minimum height of 5.49 meters tbove the tallest building in the AFRRI complex. All radioactive effluent activities are monitored and recorded along with the total stack flow rate just prior to discharge from the AFRRI stack. A number of CAMS and radiation area monitors (RAMS) associated with the AFRRI R actor Facility are in place throughout the reactor building, with readout and/or alarm signals provided in such places as the reactor control room, the AFRRI radiation safety office, the AFRRI security office, and often at other strategic locations within the AFRRI complex. 1.4 CREDIBLE ACCIDENTS FOR THE AFRRI TRIGA REACTOR Credible accidents, including Design Basis Accidents (DBAs) for the AFRRI TRIGA rcactor, are identified and discussed in the AFRRI Reactor Facility Safety Analysis Report (SAR), dated June 1981.(6) The worst-case credible accidents identified in the AFRRI Reactor Facility SAR are classified as DBAs and involve a " fuel element drop tecident" and a " fuel element cladding failure accident." Details of these accidents, any assumptions made, and their associated consequences can be found in the AFRRI Reactor Fccility SAR(6), and the reader is referred to this report for further information. In summary, however, the radiological consequences of these DBAs are minimal with respect to thyroid doses at or beyond the AFRRI site boundary (557 mrad at 25 meters from the AFRRI facility decreasing almost exponentially to 51 mrad at 200 meters), and virtually insignificant with respect to whole-body doses at or beyond the AFRRI site boundary (51.3 a
mrad at 25 meters from the APRRI facility, decreasing to $ 0.15 mrsd at 200 meters). These conclusions clearly indicate that evacuation plans for credible AFRRI reactor-related radiological emergencies do not need to extend beyond the AFRRI reactor operations boundary but certainly are inappropriate beyond the AFRRI site boundary. For the entire spectrum of credible AFRRI reactor accidents or emergencies, there , is no potential for impact on any other AFRRI radiation source facility, except for a possible temporary cessation or delay in normal operations; similarly, the converse is also true. i l [ M
1 l 2.0 DEFINITIONS Terms unique to the AFRRI Reactor Facility or that have a specific or special l meaning when used in this Plan are defined below. ,
, Emergency. Unless explicitly stated otherwise, when used in this Plan, an "emer-gency" is a condition related to the AFRPI Reactor Facility that calls for immediate tetion, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.
Emergency Plan. The AFRRI Reactor Facility " Emergency Plan" is a document that establishes necessary emergency elements and provides the basis for actions to cope with an emergency related to the AFRRI Reactor Facility. " Emergency Plan," when used in this document, applies only to emergency situations related to the AFRRI Reactor Fecility, unless explicitly stated otherwise.
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E m ergency-A ction-I;evels-f EAIJs). " Eats
- are specific reactor re' lated iristruriient ;
readings, or observations; radiological dose or dose rates; or specific contamination levels i of airborne, waterborne, or surface-deposited radioactive materials, which relate to the AFRRI Reactor Facility, that are used as thresholds for establishing and achieving emergency classes and initiating appropriate emergency measures or procedures under l this Emergency Plan. l Emergency Classes. " Emergency classes" are generally accepted classification I 1:.bels for accident situations grouped by severity level for which predetermined , emergency measures or procedures have been addressed, considered, or provided. The full l . s:;t of emergency classes, considered as a whole, encompasses the entire spectrum of
- possible emergencies. However, the entire spectrum of credible accidents or emergencies involving the AFRRI Reactor Facility falls into the lower severity emergency classes.
" Emergency Classes," when used in this document, apply only to AFRRI reactor-related emergency situations unless explicitly stated otherwise. j 9
l Emergency Procedures. " Emergency procedures" are established and documented instructions or measures that detail the implementation actions and methods required to echieve the objectives of the Emergency Plan. Unless explicitly stated otherwise, ; l
" Emergency Procedures," when used in this Plan, shall apply only to those procedures .
r: lated to the AFRRI Reactor Facility. i . Protective Action Guides (PAGs). "PAGs" are projected radiological dose or dose commitment values to individuals that warrant protective action following a reactor-rslated radiological accident, including a release of radioactive material. The projected I dose does not include the dose that has unavoidably occurred prior to the assessment for determining if the PAG has been met. Protective actions are warranted if a PAG is met, l provided the reduction in individual dose, expected to be achieved by carrying out the protective action, is not offset by excessive risks to individual safety in taking the protective action. As per Regulatory Guide 2.6 and ANSI /ANS 15.16, the established l PAGs for emergencies involving the AFRRI Reactor Facility are: (1) Sustained actual or projected radiation levels at the site boundary of 500 mrem /hr whole-body, or (2) Actual or projected doses in the plume exposure pathway at the site ' boundary of 1.0 rem (whole-body) or 5 rem (thyroid). As already pointed out in Section 1.4, these PAGs cannot be achieved for the entire spectrum of credible accidents involving the AFRRI Reactor Facility. Therefore, no protective actions beyond the AFRRI site boundary are anticipated or required. i Emergency Planning Zone (EPZ). The "EPZ" is the area for which emergency - ! planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The EPZ size is established by the maximum distance beyond the site boundary at which the PAG is determined to be met. Since the ecceptable EPZ for the AFRRI Reactor Facility is established at the operations boundary per Regulatory Guide 2.6, ANSI /ANS 15.16, and NUREG 0849, which does not extend i 10
beyond the AFRRI site boundary, no true EPZ (i.e., area that extends offsite) exists. Ncvertheless, the EPZ sssociated with the AFRRI Reactor Facility is established and defined to exist at the AFRRI Reactor Facility operations boundary even though this area is totally within the confines of AFRRI and does not extend offsite. Offsite. The geographical area that is beyond the site boundary is "offsite." Onsite. The geographical area that is within the site boundary is "onsite." l Site. When used in this document, " site" means the AFRRI site unless explicitly stated otherwise. AFRRI Site. The "AFRRI site" is that geographical area that bs within the AFRRI site boundary. Site Boundary. When used in this document, " site boundary" means the AFRRI Site Brundary. AFRRI Site Boundary. Figures 1.1 and 1.2 illustrate the "AFRRI site boundary" and therefore the confines of the AFRRI site. NNMC, Post, Base, or Center. When used in this document, these mean the National Naval Medical Center (NNMC) which is illustrated in Figures 'I.1 and 1.2. Operations Boundary. When used in this document, " operations boundary" means the AFRRI Reactor Facility operations boundary, unless explicitly stated otherwise. AFRRI Reactor Facility Operations Boundary. As illustrated in Figures 2.1, 2.2, and 2.3, the "AFRRI Reactor Facility operations boundary" is formed by physical barriers (walls, floor, roof, doors) to the following areas within the AFRRI reactor building: Reactor Room (Rm 3161); Upper Reactor Equipment Room (Rm 3152); Lower Reactor ( , Equipment Room (Rm 2158); Radiochemistry Lab (Rm 2165); Hot Cell (Rm 2166); Warm Storage (Rms 1120 and 1121); Exposure Room No.1 (Rm 1123); and Exposure Room No. 2 (Rm 1122). The areas within the AFRRI Reactor Facility operations boundary encompass l cll areas related to the AFRRI Reactor Facility in which a potential radiological source term exists or could exist. 11
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-]l @ PLANNED POTENTIAL LOCATION (S) FOR THE EMERGENCY COMMAND POST (ECP) g i . DEPENDING ON THE EMERGENCY CLASSIFICATION AND THE SITUATION "3 ". (SEE ALSO FIGURE 2.11 DiRECTORb\ PRIMARY ECP q
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7 0FFICE. RM 2151, LOCATION
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(AREA 21M1 l , O LO G. gpyggg gy 48 ,
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i l Figure 2.2 AFRRI Floor Plan, Second Level, Showing the Reactor Operations i Boundary h 13
8 LOG.43 (PHASE HI
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-:jr erTh ii REACTOR SUIL0 LNG =
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_' _"9 p- OPERATIONS BOUNDARY J I 8 LOG. 45
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9 - I i Figure 2.3 AFRRI Floor Plan, First Level, Showing the Reactor Operati6ns Boundary ,
~ l 14
AFRRI Complex. The "AFRRI complex" encompasses all of the buildings, eppurtenant structures, and facilities of AFRRI as illustrated in Figures 1.2 and 2.1. Experiment. " Experiment" shall mean (a) any apparatus, device, or material that is 7
. nst a normal part of the core or experimental facilities but that is inserted in these fecilities or is in line with a beam of radiation originating from the reactor core, or (b) cny operation designed to measure reactor parameters or characteristics.
Reactor Shutdown. The reactor is " shutdown" when it is suberitical by at least
$1.00 of reactivity.
Reactor Secured. The reactor is " secured" when all of the following conditions are satisfied: (a) The reactor is shutdown; (b) The console key switch is in the "off" position and the key is removed from the console and under the control of a licensed operator or stored in a locked storage area; and (c) No work is in progress involving fuel handling or ! rsfueling operations, maintenance of the reactor or its control mechanisms, or insertion or withdrawal of an in-core experiment, unless sufficient fuel has been removed to insure a $1.00 shutdown margin with the most reactive control rod assumed to be physically removed from the core. Reactor Operation. " Reactor operation" is when the reactor is not shutdown, reactor system maintenance is being performed, or withdrawal / movement of a control rod is taking place. Assessment Actions. " Assessment actions" are those actions taken during or after an emergency situation to obtain and process information that is necessary to make decisions to implement specific emergency or recovery measures. l l Corrective Actions. " Corrective actions" are those measures taken to ameliorate or terminate an emergency situation at or near the source of the problem in order to (a) prevent or reduce the magnitude of a release of radioactive material under an emergency situation or (b) prevent or reduce the consequences of an accident. I 15
Protective Actions. " Protective actions" are those measures taken in anticipation of or after a radiological accident, to include an uncontrolled release of radioactive material, for the purpose of preventing or minimizing the likelihood or consequences of further radiological releases or events, particularly those that have the potential for ~ cxposing individuals offsite. Recovery Actions. " Recovery actions" are those actions taken after the emer-gency to restore the facility to a safe operational status. Such actions would include, for exImple, the decontamination of affected areas to safe levels and the repair and recertification of reactor systems, as necessary. Emergency Command Post (ECP). The "ECP" is the Emergency Support Center (ESC). The ECP is a designated location where the ECP Commander directs that emergency responses and act ons be taken. At AFRRI, the ECP is the emergency coordination and decision cer ter. Emergency Command Post (ECP) Commander. The "ECP Commander" is the
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Emergency Director. The ECP Commander has overall responsibility and final approval authority for all actions taken onsite during an emergency or recovery operation. In addition, the ECP Commander has sole responsibility and final approval authority for n:tifying outside agencies, requesting any needed NNMC or other offsite emergency I support or assistance, and authorizing any planned onsite personnel radiation exposures in excess of 10 CFR 20 limits during an emergency or recovery operation, as necessary. Moreover, the ECP Commander has overall responsibility for the AFRRI, to include the Reactor Facility, and for the safety of all personnel onsite during an emergency or recovery operation, and is the final approval authority for any protective action decisions , and any public information releases. , Acting ECP Commander. The " Acting ECP Commander" is the Acting Emergency l Director. The Acting ECP Commander is an individual within the AFRRI chain of command designated to act on behalf of and in the stead of the ECP Commander in his i 16
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tbsence onsite during an emergency or recovery operation until the arrival onsite of the ECP Commander. Emergency Coordinator. The " Emergency Coordinator" is responsible for ensuring
. adequate emergency preparedness planning, periodic review and update of this Emergency Plan and any applicable implementing procedures, coordination of this Emergency Plan and any pertinent procedures (as deemed necessary) with other applicable offsite organizations, and scheduling and critiquing periodic exercises of the Emergency Plan and procedures as necessary and required.
Emergency Action Station (EAS). The "EAS" is the designated location for ccquiring emergency status information and for implementing assessment, corrective, and protective action decisions made at the ECP. The EAS Commander directs all activities at the EAS and is directly responsible to the ECP Commander.- Emergency Action Station (EAS) Commander. The "EAS Commander" is directly responsible to the ECP Commander for the immediate and continuing assessment of cmergency conditions and for implementing all corrective and protective actions taken within the reactor operations boundary (or other more encompassing evacuated areas of thn AFRRI, as appropriate) during a reactor emergency (including entry) and during any rc ctor facility recovery or restoration operation. The EAS Commander, therefore, is the primary implementation arm of the ECP Commander for assessment, corrective, and protective actions taken specifically within the reactor operations boundary and, if n:cessary, within the entire confines of AFRRI during an emergency or recovery operation. The EAS Commander is also responsible for providing emergency data, interpretation of data, advice, and assistance, as necessary, to the ECP Corgmander for d: cision making during an emergency or recovery operation. The Acting EAS Commander is a designated individual who acts for the EAS Commander in his absence until the EAS Commander arrives onsite. 17
@ s Special Advisor on Emergency Coinditions (SAOEC). The "SAOEC" is the primary AFRRI Health Physicist. The SAOEC is directly responsible to the ECP Commander for '
providing onsite and, if necessary, offsite radiological and radiation assessments for decision-making during and following an emergency or recovery operation. In addition, the SAOEC is responsible for providing emergency data, interpretation of data, advice, , and assistance to the ECP Commander, as necessary, during an emergency or recovery operation. The Acting SAOEC is a designated individual who acts for the SAOEC in his obsence until the SAOEC arrives onsite. Physicist-In-Charge (PIC). The "PIC" is the designated AFRRI Reactor Supervisor or Director. The PIC is responsible to the AFRRI Director (through the Chief, Radiation Sources Division and the Head, Radiation Sciences Department) for the normal day-to-day operation, maintenance, safety, and administration of the AFRRI reactor in accordance with the Reactor License (R-84), Technical Specifications, and applicable regulations. The PIC, as the chief administrative officer of the Reector Branch, has a staff composed of the AFRRI Reactor Operations Supervisor (ROS) and one or more other licensed Reactor Operators (ROs) or Senior Reactor Operators (SROs). Both the PIC and ROS must be licensed SROs. Reactor and Radiation Facility Safety Committee (RRFSC). The "RRFSC" is a body of individuals from within and outside of AFRRI responsible to the AFRRI Director for overseeing, reviewing, and monitoring all operations, procedures, activities, and systems / structures associated with the AFRRI reacter to ensure safety and regulatory compliance. ; I l l _ ._. . ._ _ ___A0 - . . - - - - --- -~-
l 3.0 ORGANIZATION AND RESPONSIBILITIES I The AFRRI Reactor Facility and staff fall organizationally within the Reactor Branch which is part of the Radiation Sources Division, Radiation Sciences Department of
. AFRRL Normal organizational authority flows from the AFRRI Director (or Directorate) through the Head, Radiation Sciences Department and Chief, Radiation Sources Division to the AFRRI Reactor Physicist-in-Charge (PIC). Day-to-day operations, maintenance, safety, and administration of the AFRRI reactor fall under the PIC and are performed by tha reactor staff. AFRRPs Radiation Safety Department provides normal radiation safety support and surveillance to the reactor facility and staff. Similarly, other AFRRI departments and divisions provide routine logistical and operational support to the reactor facility and staff to ensure timely, efficient, and reliable reactor operation and maintenance. Overall administration of the AFRRI Reactor License falls under the AFRRI Director, with surveillance over the safety and regulatory compliance of reactor tetivities provided by the Reactor PIC; the Head, Radiation Safety Department; and the AFRRI Reactor and Radiation Facility Safety Committee (RRFSC).
l l Under emergency situations, the Emergency Command Post (ECP) Commander is l l th2 Emergency Director or individual in charge, who has overall responsibility and final epproval authority for all actions taken onsite during an emergency or recovery operation. In addition, the ECP Commander has sole responsibility and final approval authority for notifying outside agencies, requesting any needed NNMC or other offsite emergency support, and authorizing any planned onsite personnel radiation exposures in excess of 10 CFR 20 limits, as necessary, during an emergency or recovery operation. Moreover, the ECP Commander has overall responsibility for the AFRRI, to include the reactor facility, cnd for the safety of all personnel onsite, and is the final approval authority for any protective action decisions and any public information releases during or following an emergency or recovery operation. The ECP Commander may call upon any and all manpower and equipment resources available onsite within AFRRI or available through 19
Interservice Support Agreement with NNMC as deemed necessary. However, as a minimum the working AFRRI emergency organization shall include the ECP Commander utilizing the EAS Commander and SAOEC emergency organization positions for all declared reactor emergency situations and recovery operations. It should be pointed out that tremendous in-house manpower and equipment resources are available on short notice , to the ECP Commander, EAS Commander, and SAOEC to assist them in fulfilling their responsibilities during an emergency or recovery operation. As an example, Figure A.1 (tden from AFRRI Instruction 3020.2G, "AFRRI Emergency Evacuation and Fire Plan," d2ted 30 September 1982-a copy of which is provided in total as Appendix A), illustrates thn potential emergency organization manpower resources that can be made available and utilized onsite during a full-scale AFRRI evacuation or emergency. Figure A.1 also illustrates typical interrelationships and lines of responsibility. Although this AFRRI Instruction has and may change / evolve over time, it never-thsless is provided as a representative example that has been tried and proven basically as written and provided in Appendix A. From Figure A.1 and Appendix A, it becomes quite cl:ar that AFRRI is almost totally self-sufficient within itself onsite to cope with any l emergency situation that might arise at AFRRI, except for normal utilities services, security response forces, major or sustained medical treatment and hospital services, l firefighting and rescue services, and ambulance service-all of which are dedicated, available, and provided to AFRRI by the National Naval Medical Center under Interservice Support Agreement. A copy of the Interservice Support Agreement between 1 AFRRI and NNMC is provided as Appendix B. I 1 3.1 INTERACTIONS WITH OFFSITE GOVERNMENTAL ORGANIZATIONS There are no credible everits that require direct interaction wit,h offsite govern-mental agencies except for (1) USNRC; (2) the Defense Nuclear Agency, which is AFRRI's p: rent headquarters; and (3) the National Naval Medical Center, which is AFRRI's host providing support and assistance on-post. The National Naval Medical Center grounds 20
cncompass the AFRRI site and, as the host under Interservice Sapport Agreement, NNMC provides services and support to AFRRL NNMC's operations and planning take into secount AFRRPs unique and particular requirements as a normal matter of course and management, and no planning conflict exists. Conversely, AFRRPs planning takes into cecount the resources available and committed by NNMC to AFRRI under Interservice Support Agreement. Coordination is maintained between NNMC and AFRRI by virtue of AFRRI being a tenant on the grounds of NNMC. AFRRI routinely coordinates through NNMC those internal plans, instructions, and regulations that might have an impact on or require the support of NNMC. Conversely, NNMC coordinates its center plans, instruc-tions, and regulations through AFRRL In the specific case of the AFRRI Reactor 4 Emergency Plan, no conflict exists, and NNMC will be provided copies of this Plan to sp;cifically identify for them their participation and role in support of this Emergency Plan. Training exercises, with NNMC participation, will also be conducted to test and vcrify adequate support and functionality under this Plan. The AFRRI Reactor Emergency Plan integrally depends upon NNMC for fire-fighting and rescue resources, ambulance service, major or sustained medical treatment and hospital services, and security response forces. In addition, NNMC can and has offereEl to provide assistance / support to AFRRI in the event of an emergency, as necessary, in the areas of personnel decontamination, radiation and radiological easess-ment, and equipment loan, to name a few (see Interservice Support Agreement between AFRRI and NNMC in Appendix B). 3.2 REACTOR EMERGENCY ORGANIZATION As already discussed in section 3.0 above, during an emergency the working AFRRI Reactor Emergency Organization shall consist of at least the ECP Commander, the EAS Commander, and the SAOEC, with extensive additional AFRRI and NNMC services, manpower, and equipment resources being available and called into service onsite as d:emed necessary. 21
Normal working hours for AFRRIand the reactor staff are from 0730 hours to 1600 h::urs, Monday through Friday. During these times, however, the reactor is not operated continuously. Instead, it is operated on a per-experiment basis, with the power level, duration of run, choice of exposure facility, and experimental setup design tailored for the particular experiment. Therefore, there may be times during normal duty hours as well as during nonduty hours, weekends, holidays, etc. when the reactor staff is not present on-site within the operations boundary. As a result, a flexible internal emergency organization with clear lines of succesalon is required. However, most of the credible cmergencies that have radiological release implications arise from reactor operations or
' maintenance; under these circumstances, there will be a reactor physicist-in-charge (PIC) designated, and licensed reactor staff personne1 will be present onsite within the operations boundary with Radiation Safety Department personnel present onsite. To provide reasonable assurance-that an emergency management will" exist to meet (and prepare for) reactor emergencies should one occur, the following minimum positions (with
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contingencies) and lines of succession for each are specified:
- 1. Emergency Command Post (ECP) Commander (Emergency Director)
Succession: ,
- 1. Director, AFRRI
- 2. Deputy Director, AFRRI
- 3. Senior military officer present in the AFRRI chain-of-command Contingency: Acting ECP Commander (acts only until ECP Commander arrives onsite)
Succession: '
- 1. AFRRI Officer-of-the-Day (OOD)
- 2. AFRRI Security Watch
- 2. Emergency Action Station (EAS) Commander Succession:
22
- 1. AFRRI Reactor Physicist-In-Charge (PIC) or his designee -
- 2. AFRRI Reactor Operations Supervisor (ROS)
- 3. Most-senior licensed AFRRI Senior Reactor Operator (SRO) present
- 4. Most-senior licensed AFRRI reactor operator (RO) preIent
- a Contingency: Acting EAS Commander (acts only until EAS Commander arrives I ,
T onsite) . . Succession:
- 1. AFRRI OOD *
- 2. AFRRI Security Watch
- 3. Spaal=1 Advisor on Emergency Conditions (SAOEC)
Succession:
- 1. Head, AFRRI Radiation Safety Department ' '
( l I
- 2. Acting Head, AFRRI Radiation Safety Department /
- 3. Most-senior health physicist present, AFRRI Radiation Safety Department Contingency: Acting SAOEC (acts only until SAOEC arrives onsite)
Succession:
- 1. AFRRI OOD
- 2. AFRRI Security Watch i
- 4. Emergency Coordinator (has no working function during an emergency)
Succession:
- 1. Director, AFRRI
- 2. Deputy Director, AFRRI *
- 3. Head, AFRRI Radiation Sciences Department
- 4. Chief, AFRRI Radiation Sources Division
- 5. AFRRI Reactor PIC or his designee Note that the ECP Commander and the Emergency Coordinator may be the same individual. Note also that during nonduty hours and nonduty days, in the absence of key 23 -
omergency personnel onsite, the AFRRI OOD or Security Watch (in that ceder) shall i function as the Acting ECP Commander, Acting EAS Commander, and Acting SAOEC until they arrive onsite in an emergency. Since the AFRRI OOD and Security Watch 9 positions are manned around the clock and since they act on behalf of the AFRRI Director , and Deputy Director when the latter are absent from the AFRRI site, it is logical and
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pr:ctical to delineate the AFRRI OOD and Security Watch, in that order, as the Acting ECP Commander, Acting EAS Commander, and Acting SAOEC in an emergency until
- rclieved by the arrival onsite of the ECP Commander, EAS Commander, and SAOEC. This established organization thus provides an emergency management,ons'ite at AFRRI at all times.
Although the AFRRI OOD and Security Watch are physically located outside the reactor operations boundary, they do have ready access to all areas within AFRRL In l} ; eddition, they are provided with off-normal alarm signals and other annunciators and rzadouts, all of which they are aware of, trained / instructed to respond to, and shall respond to. Typically, for an off-normal condition (other than fire or other obvious threats or emergency situations) within the reactor operations boundary during, for example, nonduty hours, the AFRRI OOD or Security Watch will notify the reactor PIC, ROS, or other available reactor operator. Based on the situation, the PIC, ROS, or other j contacted AFRRI reactor operator may or will(as appropriate) direct that the emergency organization be activated, as necessary. The AFRRI OOD or Security Watch will subsequently appropriately activate the emergency organization via telephone, using the emergency notification / call roster. The members of the emergency organization will then - respond onsite to assess and correct the situation and perform protective actions, as nseessary. As already alluded to, this procedure would not be followed in the event of a fire, explosion, act-of-God accident, security intrusion, or other obvious immediate threat to the reactor facility. For such immediate and obvious emergencies, the AFRRI OOD or J 24
Security Watch has explicit response instructions, w ich in part include activation of the 4 cmergency organization without consultation with any member of the reactor staff before . taking immediate action. Many of these events and other catastrophic occurrences on-
. site induced by natural or man-made forces require or would automatically implement responses under the overall APRRI Emergency Plan (AFRRIInstruction 3020.2), which has as one of its component parts this Emergency Plan, and basically employs the same t
identical emergency organization and capabilities. l 3.3 AGREEMENTS WITH OFFSITE AGENCIES By Interservice Support Agreement, numerous resources and services of the NNMC can and will be provided to AFRRI as necessary in an emergency. These include but are not necessarily limited to ambulance service; firefighting and rescue services; major or sustained medical treatment and hospitalization; decontamination facilities and services; cnd radiation / radiological assessment support, facilities, and equipment. The NNMC Fire Department will automatically respond to all AFRRI fire alarms or calls. Response times range from 1 to 4 minutes. Likewise, NNMC Security and the NNMC ambulance will respond to all AFRRI calls; response times range from 1 to-5 minutes. A copy of the AFRRI-NNMC Interservice Support Agreement is provided as Appendix B. ( 3.4 REACTOR EMERGENCY RESPONSE ORGANIZATION AND EXTENSIONS ! Figure 3.1 shows the relationship between the internal AFRRI minimum reactor cmergency organization and the support and support-related organizations that might be called upon and/or notified in an emergency. Activation of the internal AFRRI reactor emergency organization during normal duty hours is initiated by the AFRRI reactor operator who first is alerted to the situation. This individual is required by internal AFRRI procedures / instructions to immediately take etrtain actions for certain situations. After accomplishing these immediate actions, he would then notify the EAS Commander, ECP Commander, and SAOEC by means of the emergency notification / call roster, using the telephone or the AFRRI public address 25
OFF Slit (NNZCl IKEKGENCY SUPPORI l SERVICES /FUICil0NS i l A a I I I I 1!' I I I al NitMC NNMC NNMC 8l NNMC NNMC NNMC R ADIAT10N SAF Elv FIRE 0EPARTMENT er me rsunseNo a AM9ULANCE eutnic^t snarssrons HOSPITAL l* 3ECU"'IY DECONTAMINATION SE RVICES & F ACIllTIES '""P' H ' 'O ^ t " ^ I i " ' l{ nrscuti a r^n^ut necai e evax,m vr aiscai ir aiuten. estcuniry nescorist i ,g,,,,y,,s,,,,,,,,,,,,, asse ssureo si n eo s gp . ..0 u . s u w .. ~
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y - MINIMUM AFRRt INTERNAL REACTOR l
,._._._._.___._._._._._._._.___,___._._._..J. .. .. _._._,_
EMERGENCY _._._ _ _._ _ N_._ ORGANIZATION y' m - ' EMERGENCY COMMANO POSi lECP) EMERGENCY ACil0N ST ATION IE AS) i SPECIAL ADVISOR ON EMERGENCY . CONDITIONS ISAGEC) " COMMANDER COMMANDER l lEMERGENCYDIRECTORl 99cC' SssiF8- l S E t551 % SUCC8 SS'
- 1. MFAD, AFRRI RADIATION SAFETY SIGNEE DEPARTMENT l. OIRECTOR. AFRMI
- 2. ACilNG HEAO, AFRRt RADIAT10ft ' 2. AFRRI REACTOR OPERATIONS I'
- 2. DEPUiY DIRECTOII. ArilRI T SUPE RVISOR 1ROSI SAFETY DEPARTMElef l*
- 3. SENIOR MilliA"f 0FFICER 3. MOST SENIOR AFRR1SENiDR
- 3. MOST SENIOll HEALTH PHYSICIST PRESENT fft AF ARI CHAIN 0F- RE ACTOR OPE RATOR (SROI PRESENT. AFMRl RADIATI0ft COMMAND AVAllAgtE '
SAFETY DEPARTMENT ' ce *4: naut tacv; 4. MOST SEN10fl ATRRt RE ACIOR CONilNGENCYr k""""" "" [ OPERA 10R fR0l AVAllA8tt ;' ACilNG ECP COMMANDER
- ACTil10 SADEC"' s, ,cc,33,oy . I eon,,NG,ncy e$
SUCCESSION I. AFRRI 0FFICER OF THE ACTING E AS COMMANDER"
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- f. AFRR1000 OAY1000) succt ssioN:
- 2. AFRRt SECURITY WATCH 2. AFARI SECURITY WATCM 3. AFMRl000
$!, 2. AFRRt SECUllifY WATCH f *.
L.- _, ,_,- _,_,- - _,_,_,_, ,_, ,./ } -_.---_-_-~~_.-_-_----8 0FF SITE AGEleCYllESI
/ EMERGENCY COORDINATOR 9
/ DEFENSE NUCLEAR AGENCY N0ilFICAil0ff / succt ssioN:
lAS NECESSAnV/REOutRt 01 / 1. OIRECTOR. AFRR1 PU9 tic AFFAIRS /INFORMATION
,/ 2. OEPUTY DIRECTOR. AFRRt USitRC HEADOUARTERS. '
/ 3. HEAO. AFIIRI RAOIATION l
DEFEllSE NUCLEAR ABEIICY j SCIENCES DEPAniMENT Y KEY j gg gj g / 4. CHIEF. AFRRI RADIATION
/ SOURCES DIVISION PUStlC NEWS ' LINE OF RESPONSl81tliY
'...................................** MEDIA
. S. R CT0R PMYSICIST-IN. __, q Nu t t $'. (ALWAYS 0 PEN /PRESENT UPON ESi ASLISHMENil
- UNilt ECP CORNIAIIOER AnillVES Off SITE
" UltilL E AS COR118ANDER ARRIVES ON SITE
. .. > LINE OF COMMUNICAll0N (AT 0lSCRETl0fl 0F SENDE RI
'" UllTIL SAGEC ARRIVES ON SITE COMPONENT CATEGORIZAil0N p HAS 150 WOIIKilts FultCTION DUnitIG AN OROREAKOOWN EMERGEftCY Figure 3.1 Configuretleet and Aegmentation of ttie AFRRI Resetor Emergency
_ @tlen __
, system. During nonduty hours and nonduty days, the AFRRI OOD and Security Watch will function to activate and initially man the AFRRI emergency organization. Internal as well as external augmentation of the AFRRI reactor emergency organization is the responsibility of the ECP Commander or, in his absence, the Acting ECP Commander.
- Once the minimum AFRRI reactor emergency organization is activated and operable on-site, the principals have, through the ECP commander, numerous on- and offsite services, manpower, and equipment resources at their disposal for utilization and fulfillment of their delegated emergency responsibilities.
Interface with the appropriate NNMC emergency service or field units is by telephone (except for a fire alarm, which automatically summons the NNMC Fire Department) via emergency telephone call numbers that are posted throughout the AFRRI and are explictly and readily available to the AFRRI OOD and Security Watch at the AFRRI front desk, the AFRRI directorate, reactor operations staff in the reactor control room, and numerous other AFRRI staff throughout AFRRL The actual telephone numbers are subject to change on occasion, but two emergency phone numbers are considered j stable: (1) NNMC fire and ambulance service is available by dialing "147," and (2) NNMC Security is available by dialing "222." If necessary, other emergency support needed from NNMC can be summoned simply by calling one of the above-cited emergency NNMC desks. Medical admission to the NNMC Emergency Room is automatic when the NNMC ambulance answers a call from on-post. Paramedical support is available upon arrival of the NNMC ambulance; if additional paramedical support is required, the ambulance team can summon it onsite. The overall AFRRI Emergency Plan, like this Plan, has provisions for contacting the news media through the Defense Nuclear Agency (DNA) Public Affairs /Information Office. For reactor emergencies, the onsite ECP Commander will authorize and provide all public news /information releases via the DNA Public Affairs /Information Officer. 1 All other interfaces with outside agencies like USNRC or Headquarters, DNA, shall
< be the responsibility of the ECP Commander.
L e
i 3.5 PROLONGED EMERGENCIES AND MANAGEMENT ENDURANCE In the event of a prolonged or protracted emergency or recovery operation, j sufficient AFRRI reactor operations, radiation safety, and management staff can be
. l
- reassigned from the normal daytime work schedule to provide at least six knowledgeable staff members per shift to monitor, advise, assist, perform and direct all internal and .
i external emergency activities onsite, as necessary, for virtually an indefinite period of i time. These six staff members will be comprised of at least one licensed reactor operator, one health physicist, and one senior military officer of the AFRRI directorate or AFRRI chain of command onsite at all times during the course of an extended emergency or recovery operation. NNMC Security, hospital, emergency room, ambulance, and fire cmergency response services are staffed 24 hours per day. In addition, other NNMC emergency services can be made available during nonduty hours and nonduty days on a per-request basis through the NNMC Officer of the Day or NNMC Commander, as necessary. 3.6 REACTOR EMERGENCY DIRECTOR: AUTHORITY AND RESPONSIBILITY The ECP Commander is the emergency director. The ECP Commander has overall responsibility for the safety of all personnel onsite and for the AFRRI, to include the reactor facility, during an emergency or recovery operation. He has overall responsibility and final approval authority for all actions taken onsite during an emergency or recovery operation to include emergency downward classification and termination. In addition, the ECP Commander has sole responsibility for ensuring notification of outside agencies, for . requesting any needed NNMC or other offsite emergency support, and for authorizing any planned onsite personnel radiation exposures in excess of 10 CFR 20 limits, as necessary, during an emergency or recovery operation. Moreover, the ECP Commander is the final approval authority for any protective action decisions and any public information releases, through the Defense Nuclear Agency Public Affairs /Information Office, during or following an emergency or recovery operation. 27
To assist him in fulfilling his responsibilities, the ECP Commander may call upon cny and all manpower, service, and equipment resources available to him within AFRRI or through Interservice Support Agreement with NNMC, and apply them as he deems
; . necessary onsite or on-post, as appropriate. The ECP Commander is responsible for ansuring that radiation / radiological assessment actions are carried out by the SAOEC and l
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that emergency assessment, corrective, and protective actions are implemented by the EAS Commander, as necessary. The ECP Commander has the responsibility and authority fer assembling subteams, directing actions, and discharging the duties of paragraphs 3.9 through 3.13 below. The ECP Commander is also responsible for delegating responsibil-ities and duties to the SAOEC and the EAS Commander, to include but not necessarily limited to, their authority for assembling subteams and directing or performing tbc cetions and activities necessary for them to carry out their responsibilities and functions during an emergency or recovery operation. The ECP Commandershall-be-located atn Emergency Command Post (ECP). The line of sucession for the ECP Commander is as described and IIsted in section 3.2 and Figure 3.1. . 3.7 EMERGENCY IMPLEMENTATION POSITIONS: AUTHORITY AND RESPONSIBILITY The EAS Commander and the SAOEC are the primary emergency implementation positions directly responsible to the ECP Commander for directing and carrying out assessment, corrective, and protective actions onsite during an emergency or recovery l l op: ration. The responsibilities and authority for these two emergency implementation l . I positions are described in sections 3.7.1 and 3.7.2, respectively, below. 3.7.1 EMERGENCY ACTION STATION (EAS) COMMANDER: AUTHORITY AND l i RESPONSIBILITY l The EAS Commander is directly responsible to the ECP Commander for imple-menting, directing, and carrying out actions onsite to assess and correct emergency situations directly involving the reactor facility and its associated structures and equip-i ment. The EAS Commander is also responsible to the ECP Commander for 28
implementing / carrying out protective actions, as necessary. In addition, the EAS i Ccmmander is responsible for providing emergency status information and data (particu- l larly with respect to the reactor and its associated structures and equipment) as well as interpretation of data, advice, and assistance to the ECP Commander, as necessary, - during an emergency or recovery operation. The EAS Commander's sphere of control over cetivities is normally confined specifically within the reactor operations boundary but, if necessary, will automatically extend to more encompassing areas of the AFRRI, up to and l including the entire confines of AFRRI, should larger areas or the whole of AFRRI become affected or demand evacuation as a result of the emergency (for example, due to the sounding of a fire alarm, etc.). The EAS Commander derives his authority for fulfilling his responsibilities from the ECP Commander. Upon approval from or notification to the ECP Commander, the EAS Commander may assemble subteams and direct their activities to assess and correct the emergency situation, as necessary, within the confines of the AFRRI, including specifically the area (s) within the reactor operations boundary. The EAS Commander is responsible to the ECP Commander for all actions taken within the operations boundary or, if necessary, within a more encompassing area of AFRRI when involved or required, and has the authority to make on-the-spot decisions and to direct or perform immediate actions deemed necessary, provided that the ECP Commander is informed of such immediate decisions and actions as soon after the fact as possible. The EAS Commander shall be located at the Emergency Action Station (EAS). During any reactor facility recovery operation, the EAS Commander will also serve as the ECP Commander's primary implementation arm for directing and carrying out , approved recovery actions directly involving the reactor facility and its associated structures and equipment. The line of succession for the EAS Commander is described and listed in section 3.2 and Figure 3.1. 29
3.7.2 SPECIAL ADVISOR ON EMERGENCY CONDITIONS (SAOEC): AUTHORITY AND RESPONSIBILITY The SAOEC is the primary AFRRI Health Physicist onsite. The SAOEC is directly responsible to the ECP Commander for providing onsite and, if necessary, offsite radio-logical and radiation assessments during and following an emergency or recovery operation for decision-making. In addition, the SAOEC is responsible for providing emergency information/ data (except for reactor and reactor facility status information), interpretation of data, advice, and assistance, as necessary, to the ECP Commander during an emergency or recovery operation. The SAOEC shall be located at the ECP unless directed by the ECP Commander to personally provide support at the EAS or elsewhere. The SAOEC derives his authority for fulfilling his responsibilities from the ECP Commander. Upon approval from or notification to the ECP Commander, the SAOEC may assemble subteams and direct their activities to assess radiation / radiological conditions, as necessary. The SAOEC may be requested to provide a radiation surveil-lance subteam for support of the EAS Commander at the EAS. If this is accomplished, the activities of this subteam shall fall under the direction and authority of the EAS i Commander upon the subteam's arrival at the EAS. During any reactor recovery operation, the SAOEC (in conjunction with the Emer-gancy Coordinator) will serve as the ECP Commander's radiation safety surveillance and I oversight compliance coordinator. The line of succession for the SAOEC is described and listed in section 3.2 and Figure 3.1.
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3.8 EMERGENCY COORDINATOR The Emergency Coordinator is responsible to the AFRRI Director for the local coordination of emergency preparedness. He has the responsibility and authority for representing AFRRI and the AFRRI Reactor Facility in the broader AFRRI and NNMC planning for emergencies. Specifically, the Emergency Coordinator is responsible for 3 L - _ . - _ _ _ __ _ __ _
p::rforming or ensuring adequate emergency preparedness planning, periodic review and update of this Emergency Plan and any applicable implementing procedures, coordination of this Emergency Plan and any pertinent procedures (as deemed necessary) with other +- applicable offsite organizations, and scheduling and critiquing periodic exercises of this - Emergency Plan and its procedures, as necessary and required. The Emergency Coordinator has no working function during an actual emergency. However, during a recovery operation, the Emergency Coordinator will provide logistical support to the EAS Commander and (in conjunction with the SAOEC) will provide oversight surveillance and compliance reporting to the ECP Commander. The line of succession for the Emergency Coordinator is described and listed in s:ction 3.2 and Figure 3.1. 3.9 INFORMATION RELEASES TO THE NEWS MEDIA AND PUBLIC The ECP Commander has sole responsibility and final approval authority for emergency status and information releases to the news media and public. Approved information releases will be made to the news media and the public by the Defense Nuclear Agency (DNA) Public Affairs /Information Office in Alexandria, VA. The DNA Public Affairs /Information Officer is responsible to the ECP Commander for all informa-tion releases to the news media or the public during or after an emergency or recovery i operation. 3.10 RADIATION / RADIOLOGICAL ASSESSMENT i The ECP Commander is responsible for ensuring that onsite and offsite radiation / radiological assessments are performed, as necessary, and that this information is made available for effective decision making. The SAOEC is responsible for - directing / performing these assessments outside the reactor operations boundary, as n::cessary and as directed by the ECP Commander. The EAS Commander is responsible for directing / performing radiation / radiological assessments specifically within the reactor operations boundary. The EAS Commander may request the SAOEC (through the ECP l 31
Commander) to provide a radiation assessment subteam at the EAS to assist him in performing radiation / radiological surveys within the reactor operations boundary or other more encompassing area of AFRRI over which the EAS Commander has direct control of cetivities. NNMC may also provide radiological assessment support upon request by the ECP Commander. Therefore, radiation / radiological assessment (s) shall be accomplished by the SAOEC with assistance from the EAS Commander, any radiation survey subteams established onsite, and, if necessary, NNMC radiation safety services. Any requested NNMC radiation safety support personnel will be determined by that office. There are no credible accidents requiring offsite dose assessments or protective actions. Nevertheless, ths ECP Commander may direct the SAOEC and/or NNMC Radiation Safety support crores to perform offsite (on-Center or off-Center) radiation / radiological assessments at his discretion (for example, strictly as a precautionary measure or verification check). 3.11 DOWNGRADING OF EMERGENCY CLASSIFICATION, TERMINA'h10N OF _ EMERGENCY, AND RECOVERY DECISIONS The ECP Commander has sole responsibility for and is the only individual who can downgrade an emergency during its course, terminate an emergency, initiate recovery, and terminate recovery. The ECP Commander may call upon any and all sources of advice, consultation, data, or resources available to him as he deems necessary to arrive at such decisions. Subsequent planned organizational changes or actions are to be
, epproved by the Emergency Coordinator, who shall inform impacted agencies and coordinate those changes / actions.
3.12 RECOVERY OPERATIONS The ECP Commander has overall responsibility and final approval authority for any recovery operation. Upon approval by the ECP Commander, recovery implementation activities will be carried out by the EAS Commander, with the Emergency Coordinator L 32
i providing logistical support and the SAOEC providing radiation surveillance, decontamin-stion, and safety support to the EAS Commander. In addition, the Emergency Coordinator , in conjunction with the SAOEC will provide oversight surveillance and compliance
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reporting to the ECP Commander; the NNMC Radiation Safety Office may provide ! support to the SAOEC upon request by the ECP Commander. Therefore, recovery , operations will be approved, directed, and monitored by the ECP Commander with the assistance of:
- a. The EAS Commander (for implementation and direct supervision of approved recovery operation activities)
- b. The Emergency Coordinator (for manpower, supplies, and equipment; and for oversight and compliance surveillance)
- c. The SAOEC (for radiation / radiological support, safety support, and decontam-ination services; and for oversight and compliance surveillance)
- d. The NNMC Radiation Safety Office (if necessary, to assist and support the
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SAOEC's responsibilities) 3.13 AUTHORIZATION OF PERSONNEL EXPOSURES BEYOND OCCUPATIONAL LIMITS
- The ECP Commander, with the advice, consultation, and coordination of the SAOEC, may authorize planned personnel exposures to volunteer emergency workers in excess of normal occupational limits specified in 10 CFR 20, should this extremely unlikely situation ever become necessary. The generally accepted, one-time personnel ,
exposure guideline limit to save a life is 100 rem (whole-body); to save vital equipment / facilities or to terminate / mitigate a serious accident, the guideline limit is 25 rsm (whole-body). In either case, exposures shall be limited to volunteers. Doses in excess of these generally accepted, one-time personnel exposure guideline limits shall not be authorized for any planned emergency activities. i 33 _ ,_
4,0 EMERGENCY CLASSIFICATION SYSTEM Four emergency classes are specified and designated within Regulatory Guide 2.6, ANSI /ANS 15.16, and NUREG 0849. These are (1) " Notification of Unusual Event," (2)
" Alert," (3) " Site Area Emergency," and (4) " General Emergency." However, these cmergency classes, taken collectively, do not encompass the entire spectrum of emer-gency situations, particularly at the low severity end of the spectrum. As a result, AFRRI has created a fifth emergency class (class I) designated " Events Less Severe Than the Lowest Category" to provide additional emergency preparedness planning to cope with the more likely but less severe emergency situations that might arise.
4.1 EVENTS LESS SEVERE THAN THE LOWEST CATEGORY (CLASS d) Events of this classification are generally peripheral to reactor operations and do i not necessarily indicate changing the reactor status. Nevertheless, the reactor might be shut down to reallocate personnel or due to injury to a key individual or if a potential for escalation is perceived to exist. Similarly, the reactor operations boundary or a specific area within it might be evacuated and/or isolated,. as necessary, if (for example) a potential for radiological escalation is deemed to be present. Events in this classification may require onsite as well as on-post (offsite) local NNMC services such as ambulance, medical treatment, decontaminaton, security response, and radiation surveillance, etc., as necessary. Events in this category do not specifically require immediate or short-term USNRC notification. Instead, reporting
. would normally occur after the fact as part of the routine reporting system via the annual report.
This emergency class may include, for example: a) Civil disturbances or bomb threats nonspecific to the reactor, b) Personnel injury within the operations boundary with or without radiological or contamination complications, c) Notification of officially declared severe weather warnings for the area, \ u
d) Small but unusual observed loss or drop in pool water that is determined to be within the capabilities of the normal makeup water system (s), e) Minor radiation incidents within the operations boundary to include experiment failure post-irradiation during, for example, norma 1 retrieval or handling operations, or
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f) Minor fire or explosion nonspecific to the reactor facility, the reactor, or its control systems. 4.2 NOTIFICATION OF UNUSUAL EVENT (CLASS 1) This emergency class may arise as a result of either man-made events or natural i phenomena that are recognized as possessing significant hazard potential that was previously nonexistent or unrecognized. There is usually sufficient time to take precautionary and corrective measures to prevent escalation of the event and/or to mitigate its consequences. Events in this classification wi11'normally warrant termination or alteration of normal routines and possible evacuation and/or isolation of specific areas. This emergency class may include, for example: a) Specific threats to or breaches of reactor facility security, such as civil disturbances or bomb threats specifically directed against the reactor, b) Sustained fire or minor explosion within the reactor operations boundary (especially within the reactor room) that could adversely affect the reactor or its control systems, c) Official report / notification or observation of existing or imminent severe l n:tural phenomena in the immediate local area that might cause reactor facility . structural damage, d) Significant or continuing loss of pool water from the reactor tank, to include - unplanned leaks / breaks of the primary coolant boundary, all of which are either isolatable or determined to be within the capabilities of the normal and emergency makeup water systems, such that core uncovering is either not possible or is not likely without further escalation, 35 y
e) Failure of an experiment during or after its irradiation in an exposure facility, involving a significant release of radioactivity within the operations boundary, or f) Actual or suspected in-pool fuel element clad failure (s) or damage suggested
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by visual cues, high coolant / air radioactivity, or other radiation-detection methods.
. 4.3 ALERT (CLASS 2)
An alert condition may exist when events have occurred or are in progress that require emergency response to prevent, control, or limit a serious potential or actual r:diological hazard. Suspension of the normal routine is strongly indicated, as is cvicuation and/or isolation of affected areas, as necessary. Situations that might occur or lead to this class of emergency include, for example: a) Irradiated fuel element clad rupture in a fuel-handling operation, specifically if the occurrence is out-of-pool, i.e., in air rather than water, b) Severe natural phenomena onsite causing actual dantage to the reactor facility structure that results in a concurrent radiological source term, c) Sustained fire or an explosion, including missile impact, within the reactor op: rations boundary that directly compromises the reactor facility structure and results in a concurrent radiological source term, d) A very drastic or continuing significant loss of pool water from the reactor ttnk, exceeding the capacity of the normal and emergency makeup water systems, which can ultimately or does actually lead to the core becoming uncovered, or e) Severe or extensive fuel damage involving, for example, multiple clad failures. 4.4 SITE AREA EMERGENCY (CLASS 3) There are no credible events attributable to the reactor or its operation that are projected to lead to emergency conditions or situations in this class. 4.5 GENERAL EMERGENCY (CLASS 4) There are no credible events attributable to the reactor or its operation that are projected to lead to emergency conditions or situations in this class. 36
4.6 IMPLEMENTING PROCEDURES Specific AFRRI internal implementation procedures are contained in Radiation Sources Division (RSD) Instruction, RSD 5-3, entitled " Reactor Emergency Procedures,"
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2 which addresses each of the possible emergency classes identified in sections 4.1 through 4,3 above. In addition, AFRRI Instruction 3020.2, entitled "AFRRI Emergency Evacuation , and Fire Plan," contains pertinent implementation procedures whenever a full-scale AFRRI complex evacuation occurs or is initiated, regardless of the cause. It should be noted that this Reactor Emergency Plan, which shall be implemented for reactor cmergencies, is an integral component part of AFRRI Instruction 3020.2. i d i e o 1 y 37 l .
l i 5.0 EMERGENCY ACTION LEVELS (EALs) There are no credible accident scenarios associated with the AFRRI Reactor ! Fecility that have projected exposures at or in excess of the established protective action guideline (PAG) limits of 1 rem (whole-boay) or 5 rem (thyroid) for any individual beyond tha reactor operations boundary. Therefore, protective action guides for the general public beyond the site boundary and even for on-site personnel beyond the operations boundary are inappropriate. Nevertheless, evacuation of the AFRRI complex might still bo carried out strictly as a precautionary measure at the discretion of the ECP l l Commander. , Somewhat similar concepts (i.e., thresholds) are employed internally, based on assessment, for the determination of actual emergency classification, as shown in Table 5.1. Action levels (i.e., thresholds) specified in Table 5.1 and described in subsections 7.1, 7.2, and 7.3 of Section 7.0 are the EALs for entering the various possible emergency classes, activating the emergency organization, and initiating appropriate assessment, corrective, and protective actions for the emergency event. I
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Teble 5.1. Emergency Classification Guide Emergency Class Emergency Action Level (EAL) Purpose - Class 3: Receipt or notification of vague bomb threats or civil disturbances 1. Alert staff Events Less is. Mfle to the reactor to pa==iM-Severe Than escalation The Lowest Observation or notification of 6_
- injury or disablement Category within the operations boundary 2. Initiate assessment and/
Notification or receipt of officially declared severe weather warn- or confirmatory ings for the area actions, as necessary Observation of a small but unusual loss or drop of normal reactor pool water that is determined to be within the capabilities of the 3. Provide normal makeup water system (s) treatment and/ or initiate Observation of a minor radiation incident within the operations corrective boundary to include an experiment failure post-irradiation during, actions, as for example, normal rsMoval or handling operations or via receipt necessary of unexpected higher than normal reactor facility radiation read-ings or alarm (s) below the EAL thresholds identified for a Class 1, "Notifleation of Unusual Event" emergency condition listed below Fire alarm or observation /notifloation of a fire or explosion determined to be outside of and not immediately adjacent to the
- reactor operations boundary or not involving the reactor facility.
(continued next page) e G 39
l Tcbla 5.1-continued I Emergency Class Emergency Aetion Level (EAL) Purpose 1 Class 1: Receipt or notifloation of bomb threats or civil disturbances 1. Assure that Notifloation 8pecifloany dreeted against the reactor and having potential emergency of Unusual redologieel reisese or remotor faciHty struetwal damage implica" personnel are Event tiens readily available to respond, as Notifiestion or reempt of an unenticipated remotor facility intru- neessaary i sion detection system alarm (s). (Note: Such events wiH be acted upon in aseordance with the APRRI Resetor Facility Physical 2. Perform Security Plan. which is protected from public disclosure.) confirmatory and/or extent-Sustained fire CL10 minute duration) or minor explosion within the og. consequences operations boundary (especiaHy within tne reactor room) which assessments, as could adversely affect the resetor or its control systems deter- necessary mined via observation, notification, or a fire alarm determined to be initiated from within the reactor operations boundary Offleial report /notifloation or observation of existing or imminent reetive and pro-severe natural phenomena in the immediate local area whfeh might teedve actions, cause remeter facility structural damage as neeemary Low pool water level alarm actuation (loss of 26 inches of water 4. Provide
! from the normal pool water level) in conjunction with observation appropriate off-a nodfloatice of a continuing unusur.1 or signifleant loss of pool site agencies with water, to include observation /notifleation of unplanned current status i leaks / breaks in the primary coolant bour.dary, all of which are information j either isolatable or determined to be within the capabdities of the normal and emergeney makeup water systems such that core uneovering is not possible or is not likely without twther esealation -
Visual observation euse of actual or suspeeted in-pool fuel damage or elad failure (s) or actuation of unanticipated radiation alarms j (with or without visual cues for an experiment failure), specif1-
! onlly: R1 radiation area monitor (RAM), Ioented near the surface of the remeter pool,1500 mR/hr forli minutes R2 RAM, located on the west wen of the resetor room,210 mR/tr forli minutes E3 RAM, loosted on the west wau of the reactor prep area adjaeont to and acting as a radiation streaming deteetor'for exposure room #1, i
210 mR/hr for21 minutes E8 RAM, located on the west well of the l reactor prep area adjeeent to and acting as a radiation streaming detector for exposure room #2, A10 mR/hr forl1 minutes R5 RAM, located on the emble trail boom to the reactor core dolly carriage and acting as a criticality monitor during reactor shut-down or secured periods,250 mR/hr fora 1 minutes stack gas monitor, which samples and monitors the gaseous radioactive effluents from the top of the APRRI stack, equivalently 280 times MPCairat the top of the stack for Ar-41 (unrestricted area) forli
- minutes or the reactor room continuous air monitor (CAM), which samples air (specifteelly particulates contained within the air) from directly over the core near the pool surface, equivalently 1 100 times MPCair for unknowns (restricted area) for21 minutM of
. which must be unenticipated alarms i
l(continued next page) 40
l Tabla 5.1-continued Emergency Class Emergency Action Level (EAL) Purpose Observation of an irradiated fuel element elad rupture during a 28 fuel hamning operation, specifteelly if the occurrence is out-of- 1. A mure AM pool, La., in air rather than water *
,, g, ,
** # ""d Offleial report or observation of severe natural phenomena onsite !
causing damage to the resetor facility structure in conjunction l with the unantleipated EAL radiation alarm (s) identified under ' class 1, "Notifloation of Unusual Event," above C *'* h gter d Rosetor facility fire alarm or report / observation of a sustamed "'** fire Ct10 minute duration) or explosion (including missile impact) "*""*'I within the operations boundary that is determined to have directly compromised the reactor facility structure (especially and particu- 3. Isolate and/or larly the reactor room) in conjunction with the unanticipated EAL evacuate affected radiation alarm (s) identifled under Class 1, " Notification of Unu- syst,,(,3j,,,,g,3, sual Events," above **"*""*'I Low pool water level alarm actuation (less of26 inches of water 4. Perform from the normal pool water level) in conjunction with observation t nt f-or notifloation of a very drastie or continuing significant loss of pool water which is determined to be in ezeems of the capabilities of the normal and emergency makeup water systems and which can ultimately or does actually lead to the core becoming uncovered ,"*""*'I Verified visual observation of severe / extensive fuel' damage involv- 5. Mwm ar-reetin sedons, ing multiple clad failures (alone), or unanticipated alarms of the reactor room CAM (at the EAL threshold identified for a Class 1, ""*""*'I "Notifleation of Unusual Event," above) in conjunction with radia- " tion alarms for: R1, R2, and RS, and/or the stack gas monitor (also aed at the EAL threshold levels identified for a Class 1, "Notifleation of Unusual Event," above) provided the alarms are concurrent, for ""*""*'I a duration 21 minute, and unanticipated
- 7. Provide notifleation to and consultation with appropriate offsite agencies, as neeenery
- 8. Provide informa-tion for the public through the Defense Nuclear Agency (DNA)
Public Affairs / Information Offlee Notes: 1) " Unanticipated" within Table 5.1 and sections 4.0 and 5.0 essentially is used to ensure that the # alarm or other threshold indication is in fact associated with a real emergency hasard and not, for example, as a . result of a test or calibration of the system or as a result of planned and approved special work permit oporttions where such alarms or thresholds would be anticipated as a matter of course.
- 2) 80 tiraes MPCair (unrestricted area) for Ar41 at the top of the stack is equivalent to 62.2 x 10-3 m R/hr at the AFRRI site boundary.
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- 3) 100 MPCair-minutes for unknowns (restricted area) in the reactor room is equivalent to 0.375 MPCair-day for tmknowns (unrestricted area) at the top of the AFRRI stack (this assumes no HEPA filtration and a dilution factor of 0.18).
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i , 6.0 EMERGENCY PLANNING ZONE (EPZ) Per Regulatory Guide 2.6, ANSI /ANS 15.16, and NUREG 0849, the EPZ associated with the AFRRI Reactor Facility is hereby established and defined to exist at the AFRRI Reactor Facility operations boundary, which is totally within the confines of AFRRI and the AFRRI site. There are no credible accidents associated with the AFRRI reactor that have projected radiation doses reaching or exceeding the protective action guideline (PAG) limits of I rem (whole-body) or 5 rem (thyroid) at or beyond the operations boundary, which is the established EPZ boundary within the AFRRI site. The size of the area within the AFRRI Reactor Facility operations boundary is large enough to ensure that these PAG limits will not be reached or exceeded at or beyond the EPZ boundary for the spectruin of credible accidents associated with the AFRRI reactor. Further, the size of the area
- within the reactor facility operations boundary is large enough to provide a response base that would support actions outside this area should this ever be needed. Moreover, the (ntire NNMC site area (illustrated in Figures 1.1 and 1.2) provides an additional controlled eccess area for emergency actions should this ever become necessary.
The predetermined protective actions for the EPZ are described in sections 7.1.4, l 7.2.4, and 7.3.4, and are detailed in AFRRPs internal emergency implementation procedures / instructions (i.e., within AFRRI Radiation Sources Division Instruction RSD 5-3, " Reactor Emergency Procedures"). t 9 42
7.0 EMERGENCY RESPONSE The following subsections address and describe the anticipated assessment, corree-
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tive, and protective actions for each of the three possible classes of reactor emergencies at A?RRI, and also provide information about the activation of the emergency organi- - z: tion. It should be pointed out that the ECP Commander (Emergency Director) may tuthorize deviations from these anticipated actions, as necessary, based on the actual cmergency situation that exists. It should also be pointed out that the EAS Commander is responsible to the ECP Commander for the assessment of radiation / radiological conditions within the reactor operations boundary, while the SAOEC is responsible to the ECP Commander for the assessment of radiation / radiological conditions at and beyond the reactor operations boundary. 7.1 EVENTS LESS SEVERE THAN THE LOWEST CATEGORY (CLASS 5) 7.1.1 ACTIVATION OF THE EMERGENCY ORGANIZATION i
- These events are generally peripheral to reacia operations. Although such emergencies would be more likely to occur during normal duty hours, some could occur during nonduty hours. For those that occur during duty hours, the operator on duty shall cppropriately activate the emergency organization (via telephone or public address system), alerting emergency personnel of the event and placing them in a state of rndiness should escalation occur. For those events that occur during nonduty hours, the AFRRI Officer of the Day (OOD) or AFRRI Security Watch shall activate the emergency organization via telephone, using the emergency notification / call roster, and will assume ,
- tha positions of Acting ECP Commander, Acting EAS Commander, and Acting SAOEC, as necessary, until they arrive onsite. In either case, the appropriate NNMC emergency -
support units will be notified, as needed. For personnel injury within the reactor operations boundary, the normal AFRRI i steff would be available onsite to respond. Therefore, activation of the emergency organization shall follow the procedure described above for duty hours. The EAS ! 43
Ccmmander and ECP Commander shall be notified and shall respond appropriately. The SAOEC and AFRRI Radiation Safety Department s':aff shall likewise be notified and utilized as appropriate. 7.1.2 ASSESSMENT ACTIONS
! For minor radiation incidents or personnel injury involving radiation exposure or rIdioactive contamination within the reactor operations boundary, the R1, R2, R5, E3, cnd E6 reactor radiation area monitors (RAMS) together with the reactor room continuous cir monitor (CAM) and stack gas monitor shall be used to determine if a more severe class I
of emergency exists. Airborne particulate radiation will be determined by the reactor room CAM, while airborne gaseous concentrations will be determined by the stack gas monitor. Assessments will include a determination of the injury and the degree of
; r:diation exposure or contamination. Portable and fixed-radiation monitoring devices are available for these radiation / contamination assessments, In the absence of contamina-tien, assessment will involve consideration of the nature and extent of injury, the appropriate first aid, and the need for ambulance transport.
For vague bomb threats or civil disturbances nonspecific to the reactor, the ECP Commander (or Acting ECP Commander) shall assess the validity and specificity of the threat, and may direct that a search be conducted within the reactor operations boundary to check for potential bombs and to ensure the integrity of physical security. Advisories may also be made to NN'1C Security. For declared severe weather warnings for the area, the ECP Commander (or Acting l ECP Commander) shall receive update reports of the situation after the emergency l organization has been placed in a state of readiness. For fires or minor explosions not impacting the reactor facility, the ECP Commander (or Acting ECP Commander) shall receive status reports from the responding NNMC fire / rescue and NNMC security forces, as appropriate. l 44
For all other nonradiation-:ulated events in this class, assessments will be made by the reactor operations staff using direct visual observation to verify that a more severe class of emergency hes not exist. j 7.1.3 CORRECTIVE ACTIONS For minor radiation incidents or personnel injury involving radiation exposure or . r:dioactive contamination within the operations boundary, the reactor may be shut down (if operating) and the reactor room may be isolated (if airborne radiation exists or is suspected). Once the source of radiation is determined from assessment actions, corrective actions shall be initiated to eliminate the source or mitigate its consequences, as necessary. In the absence of radioactive contamination or unusual radiation levels associated with personnel injury, AFRRI procedures (first-aid and transport) will be followed. If a victim is contaminated, local decontamination will be attempted and carried out if judged to be nonaggravative of the injury and the situation. For more complicated or severe cases, the injured will be transported via NNMC ambulance to the NNMC hospital for medical treatment and/or decontamination, as appropriate, after being cppropriately prepared for transport (e.g., using contamination isolation methods, as ! n:;cessary). For a situation involving a small but unusual loss or drop of normal pool water that j is determined to be within the capabilities of the normal makeup water system, the t normal pool makeup water system (s) will be put into operation and a visual search for Iraks in the primary boundary will be carried out and appropiiately corrected if found. l . For a fire or minor explosion determined to be outside of and not immediately cdjacent to the operations boundary where the reactor facility is not involved, standard - AFRRI procedures shall be followed, which would use the services of the NNMC Fire i Department to correct or mitigate the situation. NNMC Security services shall also be us:d in the event of an explosion. l For all other nonradiation-related events in this category, no corrective actions would be necessary unless escalation subsequently occurred. i i 45
7.1.4 PROTECTIVE ACTIONS At this level of emergency, protective actions are generally either nonexistent or indistinguishable from corrective actions. In the special case of contamination, appropri-cta protective measures shall be taken to avoid the spread of contamination.
. 7.2 NOTIFICATION OF UNUSUAL EVENT (CLASS 1) 7.2.1 ACTIVATION OF THE EMERGENCY ORGANIZATION In the event that a situation exists or develops that presents a potentially serious h:2ard to the reactor, the operator on duty (during normal duty hours)'or the AFRRI OOD or Security Watch (during nonduty hours) shall activate the emergency organization (which shall respond) via telephone notification or public address announcement, as appropriate.
When required, requests for emergency offsite (NNMC) support shall be made by the ECP Commander or, in his absence, by the Acting ECP Commander (AFRRI OOD or Security Watch).
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7.2.2 ASSESSMENT ACTIO.NS Civil disturbances or bomb threats specifically directed against the reactor shall be assessed by the ECP Commander (or Acting ECP Commander) for validity and specificity - using, where possible, NNMC Security's experience and the information source. In cddition, a search shall be conducted within the reactor operatior.; ';oundary either by NNMC Security escorted by AFRRI staff personnel or by AFRRI reactor staff personnel alone to check for potential bombs and to check the integrity of physical security. For an actual or suspected intrusion into the reactor controlled access area, procedures described in the AFRRI Reactor Facility Physical Security Plan, which is protected from public disclosure, shall be followed. For a sustained fire or explosion within the reactor operations boundary, the ECP Commander (or Acting ECP Commander) shall assess the situation based on reports from tha responding NNMC Fire Department staff, the EAS Commander, and visual checks of 46
th2 reactor facility external boundary structural integrity. Radiation levels will also be checked to ensure that a more severe emergency class does not exist. For verified imminent or existing severe natural phenomena in the immediate local
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crra that might cause reactor facility structural damage, the ECP Commander (or Acting ECP Commander) shall continually assess the situation by cbtaining frequent reports , about the reactor facility structural integrity during the course of the severe natural phenomena. All other situations will be assessed by the ECP Commander, utilizing reports from thn EAS Commander and the SAOEC as necessary, to determine the magnitude of the event, the likelihood of escalation versus prompt control, and the need for emergency off-i site (NNMC) support. In all cases involving radiation / radiological consequences, the event shall be categorized as a Class 1 or higher emergency if any of the EALs listed under Class 1 in Table 5.1 (section 5.0) are determined-to-have-been-met. 7.2.3 CORRECTIVE ACTIONS For civil disturbances or bomb threats specifically directed against the reactor facility, the ECP Commander (or Acting ECP Commander) shall assign AFRRI staff msmbers to escort and assist NNMC security personnel in searching the area within the rcictor operations boundary for potential bombs and in checking the integrity of reactor facility physical security, or shall assign reactor facility staff members to conduct the same search alone. Any suspicious packages or conditions will immediately be reported to ths ECP Commander for the initiation of appropriate further corrective and protective , ections by offsite (NNMC) response forces. Depending upon urgency, specificity, and manpower reallocation requirements, the Ieactor may be shut down and the reactor room ^ vtntilation system may be isolated. For an actual or suspected intrusion into the reactor controlled access area, procedures described in the AFRRI Reactor Facility Physical Security Plan, which is protected from public disclosure, shall be followed. 47 -
For a sustained fire or explosion within the reactor operations boundary, the ECP Commander shall direct that radiation / radiological conditions within the reactor opera-tiens boundary be' checked and shall direct the dispatch of a team (s) to check for injured
. personnelin the area, who shall be treated in accordance with section 7.1.3. Upon arrival onsite, NNMC fire / rescue and/or security forces shall take appropriate actions to correct or control the situation, as necessary.
For verified imminent or existing severe natural phenom- 1 the immediate local arra that might cause reactor facility structural damage, the .r shall be shut down end the reactor room ventilation system may be isolated. For a continuing significant or unusual loss of reactor pool water, the ECP Commander shall direct that all available means be taken to maintain the pool water level as high above the top of the core as possible. In addition, the ECP Commander shall direct the EAS Commander to conduct a search for leaks / ruptures of the primary coolant boundary and to appropriately correct such conditions as necessary. For all Class 1 emergency situations dictated by the assessment of radiation / radiological conditions, the reactor shall be shut down and the reactor room , vtntilation system shall be isolated. In addition, the reactor room (or other affected area within the operations boundary as appropriate) shall be ordered evacuated, pending evaluation of the problem, identification of the probable source or cause, and implement-ation of appropriate control and response measures. All evacuated areas shall be under l the direct control of the EAS Commander, with approval for entry / reentry into such evacuated areas resting with the ECP Commander. Authorized entry / reentry into such cvacuated areas shall be limited to personnel rescue and approved emergency response operations. 7.2.4 PROTECTIVE ACTIONS For a Class 1 or higher emergency dictated by radiation / radiological conditions, the reactor room (or other affected area within the reactor operations boundary) shall be 48
ordered ' evacuated by reactor facility intercom, by voice order, or via the sustained sounding of a high-level radiation alarm (s). The evacuation order shall follow prescribed i written procedures. Personnel accountability shall be by direct observation of the l effected area. All evacuees shall be surveyed for contamination, and individual radiation ~ doses shall be determined by the subsequent readout of personnel dosimetry devices. If p;rsonnel contaminatica is found, preventive measures shall be taken to limit or avoid the 1 spread of contamination, initiate the decontamination of affected individuals, and l subsequently obtain (if necessary) whole-body counts (at the NNMC hospital) for those effected. I For emergencies of this or a higher class, access to the reactor room (or other l effected area within the reactor operations boundary) shall be under the direct control of I I the EAS Commander, with approval for entry / reentry into such an evacuated area resting with the ECP Commander. Authorized entry / reentry shall be limited to personnel rescue efforts and approved emergency response operations. For radiation-related. reactor emergencies, reactor area and effluent monitors ' i id:ntified in Table 5.1 will be used for the initial determination of the emergency class. Additional emergency support and confirmatory radiation / radiological instrumentation l shall be provided by the SAOEC as necessary, and includes alpha survey meters, air 1 samplers, swipes, portable beta-gamma survey meters, self-reading pocket dosimeters, th:rmoluminesent dosimeters, etc. All this equipment, except for alpha survey equipment I and air samplers, is readily available within the reactor control room or the emergency
- cache located just outside the reactor control room. Alpha survey equipment and air samplers are readily available from the AFRRI Radiation Safety Department or from any .
emergency cache located near designated AFRRI exits. The portable radiation survey maters available within or adjacent to the reactor control room are capable of measuring penetrating and nonpenetrating radiation from background levels up to high-radiation 1svels (-300 R/hr). These instruments are routinely checked for adequate operability on a qu:rterly basis. 49
t Collected filter material and swipes can be counted and analyzed as necessary in tha AFRRI counting laboratory located in the AFRRI Radiation Safety Department. Area thermoluminescent dosimeters (TLDs) are routinely placed in locations within
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cnd external to the reactor operations boundary, and will provide integrated dose information for post-accident assessment. In addition, criticality dosimeters exist in s;veral locations at and within the reactc- operations boundary, which would also provide post-accident neutron dose assessments, if needed. All AFRRI staff members as well as any AFRRI visitors are provided with and must wear personnel dosimetry as a normal matter of course upon entry into AFRRI and the I AFRRI Reactor Facility operations boundary. , 7.3 ALERT (CLASS 2) l 1 7.3.1 ACTIVATION OF THE EMERGENCY ORGANIZATION Events of this class involving significant radiation / radiological consequ,ences are generally credible only when reactor power operations or fuel handling are in progress. Th:refore, for events of this class that occur during duty hours, the operator on duty shall activate the emergency organization via telephone notification or public address an-i n:uncement. The emergency organization shall immediately respond by manning the ECP and EAS. Upon ECP and EAS manning, the ECP Commander shall make a preliminary assessment of the situation based on reports! from the EAS Commander and the SAOEC, j and shall request any additional offsite (NNMC) support that is needed. t i j . Every attempt will be made to maintain radiation etposures to emergency personnel within the limits of 10 CFR 20 and/or the Protective Action Guides (PAGs) of 1 ram (whole-body) or 5 rem (thyroid). However, the ECP Commander (with the advice and ' consultation of the SAOEC) may authorize planned personnel exposures in excess of these limits to facilitate rescue of injured personnel or to take corrective actions that will mitigate the consequences of the emergency event, should this extremely unlikely situation ever become necessary. The generally accepted personnel exposure guideline 50
limit for lifesaving is 100 rem, while the personnel exposure guideline Ilmit for taking smergency corrective action is 25 rem. In either case, such personnel exposures will be l l 2 on a planned and voluntary basis, and will be restricted to a once-in-a-lifetime acute l exposure dose. - For events of this class that occur during nonduty hours, the AFRRI OOD or Security Watch shall activate the emergency organization via telephone, using the cmergency notification / call roster, whose members shall respond onsite. The AFRRI OOD or Security Watch shall additionally man the positions of Acting ECP Commander, Acting EAS Commander, and Acting SAOEC until those members arrive on site, and shall request any additional offsite (NNMC) support that is needed. 7.3.2 ASSESSMENT ACTIONS This class of emergency shall be defined by achievement of any of the Class 2 EALs illustrated in Table 5.1 (section 5.0). Assessment.shall be performed by the ECP Commander based on reports from the EAS Commander and the SAOEC. The appropriate assessment actions described in section 7.2.2 shall be performed (if not already accom-plished), and radiation / radiological assessments shall be performed within the reactor operations boundary as well as at and beyond the operations boundary, as necessary. 7.3.3 CORRECTNE ACTIONS ( For all events in this class, the reactor shall be shut down and the reactor room l
.t ventilation system shall be isolated. In addition, the reactor room (or other affected area within the reactor operations boundary) shall be ordered evacuated by reactor intercom, l v: ice order, or by the sustained sounding of "a high-level radiation alarm (s). The l cvacuation order shall follow prescribed written procedures. The applicable corrective -
actions delineated in sections 7.1.3 and 7.2.3 shall be p'erformed (if not already accomplished), and radiation / radiological assessments of the occupied areas within the rtactor operatices trea shall be performed and evaluated for possible evacuation as nIcessary. All evacuated areas shall be under the direct control of the EAS Commander, l . 51 1 ._
with approval for entry / reentry into such evacuated areas resting with the ECP i i Ccmmander. Authorized entry / reentry into such evacuated areas shall be limited to life-saving rescue of injured personnel and approved emergency response operations.
. For a severe loss of reactor pool water, the ECP Commander may authorize the lowering of fuel in storage to the bottom of the reactor tank, or may authorize the off-loading of all elements in the pool into shielded storage casks (available onsite) if personnel radiation exposures can be assessed and controlled and do not pose a significant l
ptrsonnel hazard. In either case, the ECP Commander shall direct that all available mtans to establish and maintain a standing water level in the pool (as high as possible and [ es long as possible) be taken. Should the core become uncovered, the ECP Commander shall order the reactor room and reactor building roof evacuated, and may also direct the sv:cuation of other areas within the reactor operations boundary as well as the initiation i of radiation / radiological assessments at the site and operations boundaries, as necessary. 7.3.4 PROTECTIVE ACTIONS The appropriate protective actions described in section 7.2.4 shall be taken. The ECP Commander shall order the evacuation of the reactor room (or other affected area within the reactor operations boundary) if radiation / radiological consequences are pres-ent, and shall additionally direct that the reactor be shut down and the reactor room vtntilation system be isolated. Injured personnel will be moved to a safe area using the nstrest available exit, and evacuated area (s) shall be conspicuously marked and treated as a contaminated area until cleared by the SAOEC. All evacuated areas shall be under the direct control of the EAS Commander, with approval for entry / reentry into such evacuated areas resting with the ECP Commander. Any subsequent entry / reentry into an evacuated area shall be limited to the life-saving rescue of injured personnel and approved emergency response operations. r 52
r 8.0 EMERGENCY FACILITIES AND EQUIPMENT 8.1 EMERGENCY SUPPORT CENTER (ESC) The Emergency Support Center (ESC) is designated or known as the Emergency Cem > and Post (ECP) at AFRRL The ECP is the designated area where the ECP - Cemt ander (emergency director) receives information about the emergency; directs assessment, corrective, and protective actions to be implemented; requests / summons support; initiates notifications to offsite agencies; authorizes and approves information for public release; and makes decisions, as necessary, during the course of an. emergency. In addition, AFRRI internally utilizes a second emergency station, designated or known as the Emergency Action Station (EAS). The EAS is the designated area where the EAS Commander acquires and relays emergency status information; implements assessment, i corrective, and protective actions; requests support from the ECP; and provides emer-l g:ncy information to and advises the ECP Commander, as necessary, during the course of an emergency. (The EAS Commander is directly responsible to the ECP Commander.) { Therefore, at AFRRI the ECP is the emergency coordination and decision center, while the EAS is the emergency acquisition and implementation center. This is not to say that assessment, corrective, and protective actions cannot be implemented from the ECP-they can; however, in most instances the EAS will implement such actions. Instances in which the ECP will implement assessment actions include the determination of r:diation/radiologleal conditions at and outside of the reactor operations boundary, at and outside of the AFRRI complex, and at or beyond the site boundary, as necessary. For these particular instances, the Special Advisor on Emergency Conditions (SAOEC), who is nt:rmally located at the ECP with the ECP Commander, willimplement such actions from , the ECP upon direction from the ECP Commander. Communication links (via telephone i and/or walkie-talkie) shall be established between the ECP and EAS as soon as possible after they are established and manned. These emergency communication links will be maintained at all times during the emergency once established. 53
The primary location of the ECP shall be in the AFRRI Directorate area, which is on the second floor of AFRRI (Rm 2151, area 2106), located outside of the reactor operations boundary and outside of the reactor building. The primary location of the EAS shall be in the reactor control room (Rm 3160). The secondary location of the ECP shall be in the AFRRI library (Rm 3432), which is on the third floor of AFRRI outside of the ' reactor operations boundary and outside of the reactor building. The secondary location of the EAS shall be in the AFRRI security office (Rm 3112), which is located next to the AFRRI front desk on the third floor of AFRRI, outside of the reactor operations boundary and outside of the reactor building; that office has several reactor RAM readout units and other alarm annunciators either inside it or very nearby (within 25 feet) in Hallway 3101 or in Rm 3114. The tertiary location of the ECP shall be outside the front of AFRRI, under the point where Palmer Road South passes over Stone Lake Road. The tertiary location of the EAS shall be just outside the-front enkonce of-APRRI-All-these-locations are illustrated in Figures 2.1 and 2.2. For situations involving or requiring full-scale evacuation of the AFRRI (for example, when a fire alarm sounds), the tertiary ECP and EAS locations will be utilized. l For situations that occur during nonduty hours, the secondary or tertiary EAS location (depending on the situation) will serve as both the EAS and ECP until the arrival onsite of the normal AFRRI reactor emergency organization personnel. Virtually all of the instrumentation readouts and controls necessary to assess and correct reactor-related emergency conditions within the reactor operations boundary are l
. located in the reactor control room, which is the designated primary EAS location. These readouts provide radiation / radiological information as well as nonradiological system status information concerning the reactor and its associated equipment, the reactor facility, and the area within the reactor operations boundary. As an example, some of the readouts provided in or visible from the reactor control room are:
- a. reactor RAM readouts for the various areas within the reactor operations boundary; 54
- . - - %__ ,m- - - - _ . _ _ . - . . _
y _ _ - ,
- b. reactor room CAM readout of airborne particulate radiation within the reactor room;
- c. stack gas monitor and stack flow monitor readouts of the activity and flow rate at the AFRRIstack;
- d. Iow reactor pool water level alarm readout;
- e. status indicators and controls for the positive-sealing fall-safe ventilation dampers serving the reactor room;
- f. status indicators and controls for the reactor primary, secondary, purification, and nitrogen-16 diffuser pumps;
- g. AFRRI stack particulate monitor readout;
- h. reactor primary coolant temperature and conductivity readouts for various points in the loop;
- i. a gross primary coolant activity monitor readout; J. status indicators and controls for core position, in-pool lead shield door position, and control rod positions;
- k. redundant and independent reactor power level monitor readouts;
- 1. redundant and independor.1 fusi Wmperature monitor readouts;
- m. status indicators for the exposure room shield plug doors;
- n. annunciators for the emergency stop circuit and all other SCRAM indications;
- o. status indicators for reactor building AC power supplies to various equipment within the reactor building;
- p. public address system receivers and reactor intercom transmitters and -
receives;
- q. ,
portable radiation survey monitors;
- r. a pressure differential monitor readout for the reactor room;
- s. decontamination and emergency supplies / equipment; and
- t. visual as well as television camera coverage of the reactor room and doors 3106 and 3152 to the reactor operations boundary.
55
. i l The reactor control room, due to its available internal readouts and controls and its j proximity to and direct visibility into the reactor room, permits effective assessment and control that would be more difficult at the other backup (secondary and tertiary) EAS locations. In the event that radiation levels exceed 100 mR/hr at the center of the reactor control room or that the boundary separating the reactor control room from the reactor room becomes compromised so that airborne contamination exists in the control
- room, the EAS would then be moved to the secondary EAS location in the AFRRI security office (Rm 3112). Although such a move of the EAS would result in the loss of several l
available parameter readouts, the most important radiation / radiological readouts together with the low pool water level alarm annunciator are still available within or very near to (within 25 feet) the AFRRI security office, i.e., at the secondary EAS location. , The primary and secondary EAS locations both have telephone and intercom (public address) transmitter and receiver hookups. The primary and secondary ECP locations i hsve telephone hookups and public address receivers. Dedicated emergency walkie-talkies and a bullhorn are available for use as necessary. The emergency walkie-talkies will serve I as the primary communication link between the ECP and EAS when telephone links are i inoperable or unavailable, e.g., when the tertiary EAS and ECP locations are utilized or when other conditions demand or require the use of the emergency walkie-talkies. The AFRRI Directorate area (primary ECP location, Rm 2151, area 2106) is the normal work center for the AFRRI Directorate or management, and it is staffed and occupied by at least one person at all times during normal AFRRI duty hours. Similarly, the reactor control room (primary EAS location, Rm 3160) is the normal work center for reactor operations and it is generally staffed by members of the Reactor Branch during normal duty hours; during reactor operations, there will always be at least one licensed r reactor operator on duty. Located within 15 feet of the reactor control room (primary EAS) but outside of the reactor room are a cache of emergency supplies (containing such items as portable 56
radiation survey meters, decontamination supplies, personnel whole-body and extremity dosimeters, swipes, towels, blankets, tape, drop cloths, and protective clothing); three fire extinguishers; an industrial first aid kit; an industrial air mask / air pack; a large tool chest; a fire alarm box; and a deep sink with blockable drain. A more sophisticated decontamination area with showers and warm drains is located two floors below, . Immediately adjacent to the reactor prep area. The secondary and tertiary EAS locations, as well as several other strategic locations throughout AFRRI, have similar emergency supply and equipment eaches which are readily available for use, as necessary. 8.2 RADIATION / RADIOLOGICAL ASSESSMENT EQUIPMENT Some of this equipment has already been identified in section 8.1 above. However, specifically within the reactor control room (primary EAS) are readouts for the following fixed radiation / radiological monitors: at least five reactor RAMS, three of which are monitoring the reactor room at various points and two of which are associated with each of the reactor exposure rooms; at least one reactor room CAM, which surveys for airborne - radioactive particulates; and a stack gas monitor with an associated stack flow monitor which surveys for radioactive gases at the top of the AFRRI stack. Other radiation / radiological readouts are normally provided in the reactor control room, which survey for high radiation in the reactor primary coolant loop, high particulate radiation in the AFRRI stack, and high radiation fields at other points within the reactor operations boundary, but these are not specifically required under the AFRRI Reactor License or Technical Specifications.(5) Therefore, these additional radiation readouts must be - l considered as supplemental, but they will provide additional useful assessment data, when 1 available. Also located within the reactor control room are two portable radiation survey meters, one of which is capable of high range (up to ~300 R/hr). In addition, just outside the reactor control room in hallway 3106 is an emergency cache box with various emergency supplies and equipment; this also contains additional portable radiation survey 57
.m , - - ~ - - , _ , , , - - - . , - - - - - - - , - - - - -
s meters, quick readout personnel dosimeters, and extremity dosimeters that are not normally used or worn by the reactor facility staff. Available elsewhere within AFRRI but outside of the reactor operations boundary are numerous other sources of portable and fixed radiation survey and assessment
. equipment, including air samplers and multichannel analyzers with various detectors that are capable of providing radioisotopic analysis. Portable emergency radiation survey meters and other emergency supplies and equipment are also located at selected and strategic AFRRI exits, within emergency caches that can be rolled to nearby positions as necessary. One of these portable emergency caches is located at the front entrance of AFRRI, and is therefore available for use at both the secondary and tertiary EAS locations. External meteorological data readouts are also available at the secondary EAS location, should such data ever be required for radiological assessment at or beyond the AFRRI site boundary. Information concerning internal temperature, relative humidity, and barometric pressure is available at several points within AFRRI.
8.3 DECONTAMINATION, FIRST AID, AND MEDICAL FACILITIES 8.3.1 DECONTAMINATION FACILITIES AFRRI has numerous and extensive,onsite facilities and manpower for decontam-ination. Nevertheless, NNMC has additional decontamination facilities that are available to AFRRI in an emergency. (See AFRRI-NNMC Interservice Support Agreement, Appendix B.) Within the confines of the reactor building (both 'within and outside the reactor operations boundary) are several decontamination sinks and showers with warm drains. In addition, there are other sinks with blockable cold drains that could be used for short-term or minor decontamination. Within the reactor room as well as just outside the reactor control room (primary EAS) are decontamination supplies for short-term confine-ment of minor spreadable contamination. The AFRRI Radiation Safety Department maintains personnel, equipment, and supplies to handle major radioactive contamination 58
l l problems'and decontamination efforts. Protective clothing is located in the portable and fixed emergency caches throughout the AFRRI; self-contained breathing equipment (industrial air masks / air packs) is adjacent to these caches. One emergency cache is located just outside the reactor control room (primary EAS) and another is located just outside the AFRRI security office (secondary EAS). The emergency cache located just , outside the AFRRI security office (secondary EAS) at the AFRRI front entrance is portable, so that it can be easily wheeled / carried outside the front entrance of AFRRI (tertiary EAS) or to other locations as necessary. In the unlikely event that injured and/or contaminated personnel could not be decontaminated and/or treated adequately at AFRRI, the individual would be appropri-ately prepared and transported (via NNMC ambulance) to the NNMC hospital, which has full hospital emergency care and facilities to capably handle any personnel decontamina-tion and/or medical situation that might arise. Preparation of such individuals for transport shall be accomplished in accordance with applicable internal AFRRI instructions / procedures by the AFRRI Radiation Safety Department or health physics staff using common sense, good judgment, and sound practices. The NNMC hospital is located approximately 500 yards from the AFRRI complex on the grounds of NNMC. 8.3.2 FIRST AID The onsite AFRRI staff is comprised of numerous medically trained personnel and several medical doctors. Immediate first aid will be provided by the most available trained individual, with subsequent onsite treatment provided by available paramedical and medical personnel Sustained or major medical treatment, if necessary, shall be performed by NNMC Hospital personnel upon ambulance transport to the NNMC Hospital. . The AFRRI medical staff shall be notified of personnel injury onsite by telephone, public address system, or walkie-talkie, as appropriate. Notification of NNMC to request ambulance and medical services shall be by telephone, radio, or walkie-talkie, as appropriate. Transport of injured personnel will be by NNMC ambulance to the NNMC 59
hospital. Preparation of an Individual for transport shall be in accordance with internal AFRRI instructions / procedures using common sense, good judgment, and sound practices. Responding NNMC fire and ambulance persontel are trained to provide first aid and
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paramedical treatment, respectively. At AFRRI an industrial first aid kit is located just outside the reactor control room (primary EAS). In addition, a full medical bag, oxygen supply, gurney, and wheelchairs are readily available at the AFRRI front entrance. 8.3.3 AMBULANCE SERVICE NNMC ambulanet service shall be used, as necessary, for the transport of injured and/or contaminated personnel to the NNMC hospital (located approximately 500 yards from the AFRRI complex). In the event of transport of a contaminated individual, a health physics member of_the AFRRI Radiation Safety Department staff shall accompany the individual in the ambulance to advise on proper handling, to minimize personnel doses and the sprea'd of contamination, and to provide dose estimate information. NNMC ambulance personnel are trained in first aid and paramedical treatment. NNMC ambulance, decontamination, and medical services are provided to AFRRI under AFRRI-NNMC Interservice Support Agreement (see Appendix B). 8.3.4 NNMC HOSPITAL NNMC hospital services (medical treatment and decontamination) are provided to AFRRI under AFRRI-NNMC Interrurvice Support Agreement (see Appendix B). The NNMC hospital complex routinely handles all emergency cases on the NNMC, and is a designated and certified radiation accident emergency facility capable of handling
. radiation-exposed and contaminated victims. Training of NNMC hospital personnel is performed on a continual basis at NNMC. The NNMC hospital also has its own Radiation l
Safety Office staffed with personnel who are trained in radiation assessment and control 7 techniques. 1 \ 60
8.3.5 OTHER MEDICAL AND RADIOLOGICAL SUPPORT All conceivable medical and radiological support can be supplied either by AFRRI internally or by NNMC under Interservice Support Agreement (see Appendix B). No other offsite support is necessary. 8.4 EMERGENCY COMMUNICATIONS Primary emergency communications shall be by telephone at, from, and between all designated ECP and EAS locations except the tertiary ECP and EAS locations, where designated emergency walkie-talkies shall be the primary means .of communications onsite. Telephonic communications can be accomplished from any number of units in and near the primary and secondary ECP and EAS locations and the tertiary ECP location, as necessary. Specifically, there are four phones, each with a minimum of two independent lines, at the primary ECP location. Two phones with two independent lines each exist at the primary EAS location. In addition, there are six other phones, with two lines each, within 25 feet of the primary EAS location (within the reactor operations boundary but outside the reactor room). There are four phones with three lines each at the secondary ECP location. There are two phones with three lines each at the secondary EAS location, and one additional phone having two lines a mere 20 feet away at the AFRRI front desk. Finally, there is one phone with one line at the tertiary ECP location but no phones at the tertiary EAS location. The primary EAS location has an intercom system that links the reactor control room to specific areas within the reactor operations boundary and the AFRRI. This system is used on a routine basis for communications between the reactor control room - and the reactor room, the AFRRI dosimetry readout room (near the reactor prep area), the AFRRI television control center (on the second level of AFRRI), and the reactor prep area. All locations associated with this intercom system have the capability to both transmit and receive. 61 l t
j The secondary EAS location is adjacent to the AFRRI front desk, which has an AFRRI complex public address system. For this system, transmission occurs only from f the AFRRI front desk, with reception only throughout the rest of AFRRL Public address systems are also available in NNMC security vehicles, and at least one portable loudspeaker (bu!! horn) is available for use at the ECP or EAS locations, as necessary. An alternate communication system totally independent of ground links shall be available for emergency use as necessary. This systern uses self-powered walkie-talkie units, three of which are designated emergency units kept at the secondary EAS location. These walkie-talkie units operate on a common dedicated frequency' assigned to AFRRI, and shall be used as the primary means of emergency communications onsite whenever the tertiary ECP and EAS locations are used or their use is required for other reasons. If necessary, several additional walkie-talkie units are available from the AFRRI Logisitics Department. The primary communication units and links (telephone) are used daily for normal operations; if found inoperative, they are immediately repaired by NNMC telephone services. The alternate units (walkie-talkies, bullhorn, and public address / intercom system) shall be tested at least quarterly, and power pack changes (if appropriate) shall be made at least as often as recommended by the manufacturer. l Off-site authorities and agencies contacted by telephone for emergency support or for notification purposes will be able to verify the contact via telephone callback to either a primary or secondary onsite telephone number (except at the tertiary ECP
, location where only a single line exists). Telephone callback numbers will be provided by j the initial AFRRI caller within the emergency message form (EMF).
8.5 EMERGENCY MESSAGE FORM (EMF) The following example EMF format may be used to transmit information to offsite agencies (including USNRC) for notification, as necessary. For offsite (NNMC) l 62
emergency support requests, no callback verification or EMF is specifically required, but may be used upon request. EXAMPLE FORMAT FOR EMERGENCY MESSAGE FORM (EMF) ,
- 1. Name of caller: -
- 2. Title of caller:
- 3. Date and time of call:
- 4. Organization called:
- 5. Location of organization called:
- 6. Location of incident / emergency (AFRRI, License #R-84):
- 7. Purpose of call:
- 8. Description of event:
- a. Emergency class:
- b. Date and time of occurrence:
- c. Actual or expected releases and estimate of their impact:
- d. Meteorological conditions (as available and necessary):
- 1) Wind speed and direction:
- 2) Atmospheric stability:
3)' Precipitation (actual or expected):
- 4) Temperature:
- e. Events (brief description):
- f. Actual or projected consequences:
- 1) Actual or projected doses within, at, and outside operations boundary: ,
- 2) Actual or expected injuries onsite:
- 3) Actual or projected facility damage: '
- g. Status of emergency:
- 1) Status to present:
- 2) Potential for escalation:
63
- 3) Potential for downgrading:
- 4) Projection for emergency termination:
- 9. Recommendations to organization called for offsite actions:
- 10. Telephone number (s) for callback verification:
8.6 ONSITE EMERGENCY CACHES Several emergency cache units shall be located at several(at least two) exit points to the AFRRI complex. At least one of these emergency cache units shall be located near the secondary EAS location. These units shall be mobile and removable to an outside area if necessary. Emergency equipment deemed necessary to support emergency actions onsite and to permit, as a minimum, two personnel to enter an airborne contamination area, shall be contained within (or provided adjacent to) these emergency cache units. In addition, a fixed emergency cache shall be located near the primary EAS location and will provide such ~ equipment as is deemed prudent and necessary for immediate emergency support and area access. (Note: portable emergency cache units and any adjacent emergency equipment may also be brought..to the primary, secondary, or tertiary EAS locations as necessary). The following is provided solely as an example of equipment contained in or provided adjacent to a typical portable onsite emergency cae.a unit. (Equipment listed below is for the AFRRI front-entrance emergency cache unit.) i Survey meters: Illgh range (1) Low range (1) Alpha (1) 200-mR pocket chambers (10) Dosimeter charger (1) Battle lantern (1) HIVol air sampler (1) 64
MSA self-contained breathing apparatus (2) (Available adjacent to emergency cache unit) Rubber boots (2 Pr) Masking tape (2 rolls) - Grease pencil / felt-tip pens (2) Radioactive insignia tape (1 roll) Protective clothing sets (6) Plastic bags (12) Pint plastic jars (2) HercuHte sheet (1) ' Particulate filters (1 box) Clipboard (1) Documentation set (1) TLD wrist dosimeters (5) i Urine sample cups with/ lids (1 pack) Cotton-tipped swabs (1 pack) . TA312 telephones (2) Wrenches, 5/8", 3/4",1",1-1/8" (1 ea) Bonding radiation tape (1 roll) High-radiation-area signs (3) Smear patelles (1 box of 500) Charcoal filters (1 box) . Self-powered walkie-talkies with chargers (3) (Available adjacent to emergency
~
cache unit) Emergency cache units with their contained and associated equipment shall be 4 inventoried and checked at least quarterly by the AFRRI Radiation Safety Department staff, which may include a battery change in battery-powered units as required. Units due 65
- - 1. -,.
for calibration are typically exchanged for calibrated units. The term of calibration shall be the same as for all other onsite portable units or as specified on the individual unit. l I i 6 66
9.0 RECOVERY Downward classification of an emergency to include eraergency termination can only be authorized by the ECP Commander based on the predetermined EALs cited in section 5.0, Table 5.1, and the results of assessment actions described in sections 7.1.2, 7.2.2, and 7.3.2. The ECP Commander also has the overall responsibility for any recovery - operation, and is therefore in charge of any recovery operation. As needed, specific recovery procedures shall be written for each and every recovery operation plan before its approval and use; these procedures shall be approved by the ECP Commander as a minimum. Each recovery procedure or plan obviously must be specifically tailored to the actual situation as it exists and to the emergency conditions that were experienced. As a result, to be effective, such recovery procedures or plans cannot be written and approved before the fact. However, any and all recovery procedures-or plans-that-are-written and approved shall include specific considerations of contamination levels, identified hazards, as well as radiation levels; decontamination, if required, shall conform to the provisions of 10 CFR 20, as a minimum. e 67 i
I l 10.0 MAINTAINING EMERGENCY PREPAREDNESS 10.1 TRAINING AND DRILLS 10.1.1 PERSONNEL TRAINING AND RETRAINING i All licensed AFRRI reactor operators and senior reactor operators participate in I1e AFRRI reactor operator requalification program, which involves routine lectures and classroom instruction on a continual basis during the course of each year. The AFRRI emergency management staff, along with other key AFRRI staff personnel, are invited to attend those sessions that address emergency planning and procedures in order to keep them updated. In addition, all AFRRI staff personnel receive emergency planning
,information and review of the overall AFRRI Emergency Plan (which includes this Plan)
! along with pertinent instructions on an annual basis. AFRRI security watch personnel 4 4 ! (i.e., the AFRRI Officer of the Day and the AFRRI Security Watch) receive a pretour briefing, and are required to review all AFRRI Watch Instructions (including AFRRI Instruction 3020.2 and this Emergency Plan) at the start of their tour of duty. Additionally, all AFRRI security watch-stander 3 receive a briefing on AFRRI Instruction 3020.2 (which includes this Emergency Plan) at least semiannually. NNMC Security and Fire Department personnel are invited annually to receive an orientation and familiariza-tion tour of AFRRL Training / certification of emergency offsite (NNMC) security, medical, and radiation safety personnel is conducted by NNMC under pertinent military regulations. AFRRI staff personnel designated to the AFRRI reactor emergency organization as well as other key AFRRI staff with anticipated emergency response functions or
. responsibilities shall participate in an initial training program and an annual retraining ,
program, conducted by the Emergency Coordinator or his designee, to include classroom training and involvement in the annual AFRRI reactor emergency drill and evaluation. This training is designed to ensure that emergency personnel understand their roles and responsibilities as well as to demonstrate and verify their abilities to perform assigned functions in an emergency. 68
Copies of this Emergency Plan and any subsequent modifications to it shall be provided to designated offsite (NNMC) emergency response units as a normal matter of course. In addition, copies of this Emergency Plan together with emergency notification / call rosters shall be provided and readily available (as a minimum) to AFRRI security watch personnel, AFRRI reactor staff personnel, and the AFRRI Directorate, at appropriate strategic points near telephones within AFRRL 10.1.2 DRILLS An AFRRI reactor, emergency. drill shall be conducted annually. This drill shall involve a simulated preconceived emergency scenario to test the emergency organization, preparedness, and response of onsite and, to the appropriate extent, offsite personnel, services, equipment, and functions or actions. The emergency scenario shall be developed, planned, and exercised by the Emergency Coordinator or his designee in conjunction with assigned observers chosen by the Emergency Coordinator or his designee. An invitation will normally be extended to non-AFRRI members of the AFRRI Reactor and Radiation Facility Safety Committee (RRFSC) to participate as planners or observers for a drill Drills shall be executed as realistically as possible, and shall involve the use of appropriate onsite emergency personnel, equipment, and services, as necessary. Off site (NNMC) emergency personnel, services, and equipment shall be called upon, utilized, or included in the drill as appropriate and necessary, with a minimum requirement of testing the communication links and notification procedures at least every 2 years. 10.1.3 EVALUATION OF DRILLS At the conclusion of each annual drill, a critique shall be held, with the Emergency . < Coordinator (or his designee) who executed the drill presiding over the session. Inputs shall be provided by the drill observers, and discussion shall be open to all drill , participants. Critique attendance willinclude the Emergency Coordinator or his designee, l all observers, members of the AFRRI reactor emergency organization who participated, and any other participants. Critique attendance may also include the available AFRRI 69
Reactor Branch and Radiation Safety Department staff, applicable offsite emergency support agencies / groups, and interested individuals authorized by the AFRRI Directorate to attend. The Emergency Coordinator or his designee, who executed the drill and. presided over the drill critique, shall subsequently prepare a summary report of the drill for appropriate dissemination, use, and filing. This report will provide a basis for any resultant planned / identified modifications to this Emergency Plan or its associated implementation procedures, as necessary. 10.2 EMERGENCY PLAN REVIEW AND UPDATE This Emergency Plan shall be revised and updated as required, with written modifications taking effect upon review and concurrence by the RRFSC and subsequent i approval by the Emergency Coordinator. Notwithstanding, this Emergency Plan shall be reviewed on an annual basis by the Emergency Coordinator or his designee in conjunction with the AFRRI Reactor Physicist-In-Charge (PIC). Any planned / identified. written modifications to this Emergency Plan as a result of an annual review shall be presented before the RRFSC for review and concurrence, and shall be subsequently approved by the Emergency Coordinator before taking effect. This Emergency Plan and any subsequent revisions or modifications to it shall be distributed in a timely fashion after approval (within 30 days) to all applicable and authorized agencies responding to or responsible under this Plan. The Emergency l Coordinator or his designee, who performs the annual review of this Plan, shall be responsible for the annual review and certification of any and all agreements with offsite emergency support agencies that are relied upon under this Plan. In addition, onsite emergency notification / call rosters shall be reviewed and appropriately updated quarterly by the AFRRI Reactor PIC with assistance, as necessary, from the Emergency Coordi-nator or his designee, the Head of the AFRRI Radiation Safety Department, and the AFRRI Administrative Officer. 70
l l 10.3 MAINTENANCE AND SURVEILLANCE OF EMERGENCY EQUIPMENT Surveillance and maintenance of emergency supplies and equipment insures their availability, reliability, and proper condition for immediate use. The AFRRI Radiation Safety Department is responsible for surveillance and maintenance of onsite emergency supplies and equipment kept in and adjacent to numerous emergency cache boxes at , I strategic locations throughout the AFRRI complex. AFRRPs emergency supplies and equipment are routinely inventoried and verified to be operational and complete on a monthly basis by the AFRRI Ra6ation Safety Department staff. Fire extinguishers located throughout the AFRRI complex are also routinely checked on a monthly basis by the NNMC Fire Department staff. The AFRRI Security Watch reactor annunciator / alarm box (which provides audible and visual alarms during nonduty hours for low reactor pool water, high airborne radiation in the reactor room, and a high radiation field in the reactor room), located outside the reactor operations boundary in Hallway 3101 near the AFRRI front desk, is verified to be operational on a quarterly basis by the AFRRI reactor staff who also maintain it. Telephone and radio communication equipment maintenance is provided by NNMC utility services or the manufacturer of the equipment, as necessary and appropriate. Designated onsite emergency walkie-talkies are routinely inventoried and verified to be operational by the AFRRI Radiation Safety Department staff on a monthly basis. Fixed onsite public address systems are used by (a) the reactor staff within the reacwr operations boundary and (b) the AFRRI receptionist or Security Watch personnel for announcement throughout the AFRRI complex on a routine day-to-day operational basis as required. Surveillance of these systems occurs as a result of their
- normal everyday use, and any maintenance required is performed by AFRRPs Logistics Department, as required. All other offsite (NNMC) emergency supplies and equipment are inventoried and maintained by NNMC in accordance with their own procedures.
Maintenance and calibration of the AFRRI Reactor Facility safety and radiation detection / measuring equipment is conducted in accordance with Table 10.1 below. 71
Surveillance / testing is performed routinely on a daily or weekly (as appropriate) basis and whenever the system (s) are used.
. Table 10.1. Maintenance and Calibration Schedule for Reactor Facility Safety and Radiation Detection / Measuring Equipment Mimmum Maintenance and Equipment Calibration Frequency Basis Reactor safety systems:
Power safety channels Annually or as necessary* Technical specifications (5) Fuel temp. safety channels Annually or as necessary* Technical specifications (5) Others Annually or as necessary* Technical specifications (5) Reactor radiation area monitors (RAMS) Quarterly or as necessary** Technical specifications (5) Reactor room centinuous air monitor (CAM) Quarterly or as necessary** Technical specifications (5) Stack gas monitor Semiannually or as Internal AFRRI Radiation necessary" Safety Instructions and/or Health Physics Procedures Portable survey monitors / meters Quarterly or as necessary" Internal AFRRI Radiation f Safety Instructions and/or 1 Health Physics Procedures Radioanalysis equipment Quarterly or as necessary Intemal AFRR1 Radiation before use" Safety Instructions and/or Health Physics Procedures Performed by AFRR1 reactor staff
" Performed by AFRR1 Radiation Safety Department (primary)in conjunction with the i AFRRI Logistics Department staff, as necessary.
i (5) Seereference 5,section 12.0. , 72
11.0 WRITTEN PROCEDURES 11.1 ESTABLISHMENT OF WRITTEN PROCEDURES This Emergency Plan requires written implementation procedures and certain cmergency information for the spectrum of credible accidents or emergency conditions identified below. These procedures shall address emergencies ranging from Class X, ,
" Events Less Severe Than The Lowest Category," up through and including Class 2, " Alert," as described in section 4.0 of this Plan. These procedures shall be delineated within Internal AFRRI instruction (s) (AFRRI's Radiation Sources Division Instruction, RSD 5-3, " Reactor Emergency Procedures"). They shall also contain an emergency natification/ call roster, an ECP Commander's notification / call roster, and an Emergency Classification Guide with emergency classes # through 2 and their associated EALs shown in tabular form.
Accidents or emergency conditions for which written procediiIres and emergency information are required include: Bomb threats 1 Civil disturbances Personne!. injury Experiment failure Minor radiation incidents Unusualloss of water from the primary boundary Natural act-of-God events / accidents Breaches of security (Note: Such events shall be acted upon in accordance with the AFRRI Reactor Facility Physical Security Plan, which is . protected from public disclosure.) Fire or other full-scale evacuation Explosions and missiles Fuel damage 73
11.2 REVIEW AND UPDATE OF PROCEDURES The review and update of existing AFRRI internal emergency procedures / instructions required under this Emergency Plan shall be accomplished in
'~
accordance with the same review and update process as for this Emergency Plan (see section 10.2); the Emergency Coordinator shall be the final approval authority for any and all applicable internal AFRRI procedure / instruction modifications. Procedural modifica-tions suggested by the evaluation of drills (section 10.1.3) may be made upon approval by the Emergency Coordinator. Such changes or modifications to AFRRI's internal reactor emergency procedures / instructions will normally be presented before the AFRRI Reactor and Radiation Facility Safety Committee for concurrence; however, this concurrence may be sought and obtained after the fact if the Emergency Coordinator decides that the change should be made immediately. e 74
\
l
12.0 REFERENCES
- 1. Proposed Revision 1 to USNRC Regulatory Guide 2.6, " Emergency Planning for Research and Test Reactors," March 1982.
- 2. Draft 2, American National Standard ANSI /ANS 15.16, " Emergency Planning for -
Research Reactors," 29 November 1981.
- 3. NUREG 0849, Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors, USNRC, Washington, DC, May 1982.
- 4. AFRRI Instruction 3020.2, (latest version) "AFRRI Emergency Evacuation and Fire Plan," Armed Forces Radiobiology Research Institute, .Bethesda, MD, (latest and operable version /date).
- 5. Technical Specifications for the AFRRI-TRIGA Reactor Facility, License R-84, Armed Forces Radiobiology Research Institute, Bethesda, MD. USNRC Docket No.
50-170, 2 September 1980.
- 6. Safety Analysis Report (SAR) for the AFRRI-TRIGA Reactor Facility, License R-84, Armed Forces Radiobiology Research Institute, Bethesda, MD, USNRC Docket No.
50-170, June 1981, as amended. O f 75
O APPENDIX A TO THE EMERGENCY PLAN FOR THE AFRR1 TRIGA REACTOR FACILITY i l l
-~ - n. - - - - - , - - . - - . . . - , . ., -
AFRRI EMERGENCY ORGANIZATION: LINES OF RESPONSISILITY ANO FLOW OF INFORMATION EMERGENCY MUSTER *== OEFT CHAIRMEN /
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LOCATION [EML) HEacs . ou u. (pare.3] EMERGENCY COMMAND RECOROER POST (ECR] , (pare.13 o l % s s i s
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i-/ / EMERGENCY ACTION STATION l/ / (EAS) (para. 23 g l/ p# AREA EAS f f CONTROLLER COMMANOER 4 M j (2al NONRAOlOLOGICAL PERSON HAZAROS ADVISOR TURNING IN g imme.j; m.. ma, mem3 a} i__ l
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WI "* U*I FIRE MARSHAL FACILITY AOVISOR j mammmmmmmmmmmmeg as a j I .
- t t h NUMSER LETTER COCE REFERS TO g ENTRY TEAM RADIAMN SECTION OF TEXT IN THIS ENCLOSURE. (FORMEO ANO KEY: b* CONFIGU REO 3o gnv S j
w LINES OF COMMUNICATION / REPORTING SY EAS COR) i (ALwAYS PRESENTI ( 211 (2il g mamman> LINES OF COMMUNICATION / REPORTING AT THE CISCRETION OF SENOER 2 LINES OF RESPONS181LITY l Figure A.1 Example of the Potential Full-Scale AFRRI Emergency Organization (from enclosure 4 to AFRRI Instruction 3020.2G, "AFRRI Emergency Evacuation and Fire Plan," dated 30 September 1982)
DEFgNSF .TJCLEAR AGENCY ' ! ARMED FORCE 5 RADICBIOLOGY RESEARCH INSTITUTE BETHESDA, MARYLAND 20814 I AFRRI 3020.2G , RSD:JAS:hs 30 Sepamber 1982 AFRRIINSTRUCTION 3020,2G / Subj: APRRI Emergency Evacuation and Fire Plan Refs (a) AFRRI-NNMC Interservice Support (Host-Tenant) Agreement (b) APRRIInstruction 6310.1A (c) NNMC Instruction 11320.1E, Fire Bill (d) APRRI Reactor Facility Emergency Plan (upon U. S. Nuclear, Re -'latory Commission (NRC) approval) Encl: (1) Actions and Responsibilities of All AFRRI Personnel for Implementing the AFRRI Emergency Eyscuation and Fire Plan (2) Actions and Responsibilities of AFRRI Security Watch. Per:sonnel for the APRRI Emergency Evacuation and Fire Plan (3) Emergency Protection or Destruction of Classified Material; Security of the Armed Forces Radiobiology Research Institute (4) AFRRI Emergency Organizatiom Assignments and Responsibilities , (5) Procedure for AFRRI Evecuation Search Teams _ (6) . Criteria for Notification oLOutsideAgencies_. . i
- (7) Sources of Additional Help (8) APRRI Reactor Facility Emergency Plan (upon USNRC Approyal)
- 1. Purpose. To establish an effective emergency evacuation and fire plan for AFRRI.,
- 2. Cancellation. AFRRI Instruction 3020.2F, AFRRI Emergency Evacuation and Fire r Plan, dated 16 January 1978, is hereby cancelled.
I
- 3. Sjo2e. This Instruction provides guidance for all AFRRI personnel on responding to any hazardous condition at the AFRRI that requires emergency actions. The NNMC (National Naval Medical Center) Disaster Preparedness Plan will take precedence over this Instruction in accordance with Reference (a). The AFRRI Reactor Facility Emergency Plan (upon its approval by NRC) wJ1 likewise take precedence over this Instruction in accordance with Reference (d).
- 4. Evacuation Alarm. Full-scale evacuation of the AFRRI is initiated by sounding the fire bell for all emergency conditions.
- 5. Primary Action anc' ho gesibilities
- a. All AFRF,1 gec-*N1. The required duties are listed in Enclosure 1 of this
. Instruction. A clTj IDInstruction with pertinent enclosures shall be provided to all ' ';
AFRRI personnel and shall be issued to each new employee by the Head, Occupational Safety and Health Office during the check-in procedure. i
m AFRRI 3020.2G 30 September 1982
- b. Security Watch Personnel. Duties are listed in Enclosure 2, which will be posted at
- the AFRRI Reception Desk. Security Watch personnel will be required to be aware of its content. The AFRRI Administrative Officer is responsible for seeing that all watch-standers receive a briefing of this material at least semiannually.
- c. AFRRI Emergency Personnel (1) The- AFRRI Emergency Organization assignments and responsibilities are outlined in Enclosure 4. The Radiation Safety Department (SAF) is responsible for the periodic training and for ensuring proper assignment of personnel to the AFRRI
,,' Emergency Organization. SAF is also responsible for maintaining a current roster of those assigned to the AFRRI Emergency Organization. (2) Evseuation Search Teams. Duties are outlined in Enclosure 5. The AFRRI Administrative Officer is responsible for training and assigning personnel to all AFRRI . evacuation search teams and for maintaining a current roster of these teams.
- 6. Supplementary Actions and Responsibilities
- a. Reference (b) outilnes the procedures for managing injured and/or contaminated personnel; the MedicalTeam Leader willimplement these procedures.
- b. Nree separate AFRRI Fire and Emergency Evacuation Information Guides for use at the Emergency Command Post (ECP), at the Emergency Action Station (EAS), and at i
- the AFRRI Reception Desk will be assembled and maintained by SAF. These guides will l
- be kept in the ECP Emergency Box, in the Front Door Emergency Box, and at the AFRRI Reception Desk. Enclosures 4 and 6 outline the instructions governing the material in these guides.
- c. An AFRRI Emergency Notification Roster shall be maintained by SAF and posted in the OOD/ Security Watch instruction book. All department representatives identified in it shall maintain a list of home telephone numbers for their personnel; this shall constitute l the AFRRI personnel recall roster. l 4
- d. The precautions and procedures of Reference (c) shall be adhered to. with the l following exceptions: !
(1) Emergency telephone number stickers and the employee safety booklet shall - be used instead of posting Reference (c). l I i
- W
AFRRI 3020.2G 30 September 1982 (2) The investigation and reporting requirements of DNA shall be followed.
- e. The Administrative Officer shall (1) Plan and conduct drills at least twice a year to exercise and test the procedures of this Instruction.
(2) Review and, if necessary, update this Instruction annually, not to exceed 14 months. FOR THE DIRECTOR: t s [ ~ R. S. CUNNINGHAM CDR, MSC, USN Administrative Officer DISTRIBUTION: C Plus - 1 cy HQ, DNA , 2 cys PAO, DNA - I cy CO, NNMC 1 cy NNMC Rad Saf Officer . I cy NNMC Security 1 cy NNMC Fire Dept 1 cy NNMC Emerg Room , 1 cy RRF3C, AFRRI 1 cy RXSC, AFRRI 1cyJNACC 1cyNRC l l t i 3
9 ACTIONS AND RESPONSIBILITIES OF ALL AFRRI PERSONNEL FOR IMPLEMENTING THE AFRRI EMERGENCY EVACUATION AND FIRE PLAN
- 1. During Duty Hours
- a. Upon DISCOVERY of fire, smoke, or other hazardous condition, personnel must l (1) PULL the nearest fire alarm.
(2) EVACUATE the Institute immediately. (3) REPORT as soon as possible the nature and location of the emergency or hazard to the Emergency Action Station (EAS) Commander located outside the front entrance of AFRRI.
- b. Upon HEARING a fire alarm, regardless of its duration, all personnel must (1) EVACUATE the building immediately by the nearest safe exit.
(2) ASSEMBLE in appropriate muster area (see page 2 of this Enclosure). (3) MUSTER in an orderly manner with respective Department Chairman / Head or representative, and comply with his/her verbal orders. 1 (4) DO NOT INTERFERE with emergency activities or act independently. l
- 2. During Nonduty Hours
- a. Sign in and out on the Security Area Register maintained at the AFRRI Reception Desk located at the front entrance of AFRRI on nonduty days and after 1800 hours on duty days.
- b. Upon DISCOVERY of fire, smoke, or other hazardous condition, personnel must (1) PULL the nearest fire alarm.
(2) EVACUATE the Institute immediately. (3) REPORT as soon as possible the nature and location of emergency or hazard to the Security Watch or Duty Officer located at the front entrance of AFRRI.
- c. Upon HEARING a fire alarm, regardless of its duration, all personnel must
. (1) EVACUATE the building immediately by the nearest safe exit.
(2) ASSEMBLE outside the front entrance of AFRRI with the Security Watch or Duty Officer. (3) DO NOT INTERFERE with emergency activities or act independently. Enci ' to AFERI :nstr 1020.2G
AFRRI EMERGENCY MUSTER LOCATIONS [EML: VMD g% EMERGENCY MUSTER LOCATION (EML) M k EML BACKUP [ AREA J f\ a .
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ACTIONS AND RESPONSIBILITIES OF AFRRI SECURITY WATCH PERSONNEL FOR THE AFRRI EMERGENCY EVACUATION AND FIRE PLAN The following actions apply to nonduty hours:
- 1. Maintain the Security Area Register, which lists on-board personnel.
- 2. Upon DISCOVERY or notification of a fire or other hazardous condition, the Security Watch or Duty Officer will do the following:
- a. PULL the nearest fire alarm.
- b. EVACUATE the emergency area immediately,
- c. UNLOCK the AFRRI front entrance (if applicable).
- d. CALL the NNMC Fire Department (dial 147 or 50333).
- e. CALL appropriate personnellisted on the AFRRI Emergency Notification Roster.
I
- f. CHECK radiation monitors in Room 3112 for high radiation indications (i.e., g 100 mR/hr). ,
- g. TAKE the Security Area Register (which lists on-board personnel) and remain either at the front entrance or go to a safe area nearby.
- h. MEET and brief responding Fire / Rescue personnel.
- i. ESCORT and provide assistance as necessary to the Fire / Rescue personnel upon i
entry into AFRRI. ( NOTE: If a radiological hazard exists or is suspected, contact Radiation Safety Department (SAF) before permitting entry.]
- 3. Upon HEARING a fire alarm initiated by someone else, Security Watch personnel will follow items 2b through 21 above. In addition, they will:
- a. Obtain information about the emergency from the person who pulled the alarm.
- b. Relay this information to the Duty Officer and the AFRRI Administrative Officer.
i
- c. Make sure that the person who gave the information is available to assist emergency personnel upon arrival.
- 4. Responsibility and Authoritv. The Duty Officer is authorized to act on behalf of the Director and Deputy Director in their absence. Therefore, Security Wntch personnel should use sound judgment; their primary concerns should be for personnel safety and protection of the Institute, in that order. In addition, the Duty Officer is responsible for directing and taking appropriate actions in response to an emergency until properly relieved by arrival on-station of the Emergency Command Post (ECP) Commander.
Inci 2 :: AT?i.: :r.2:r 1020.2G
1 3 EMERGENCY PROTECTION OR DESTRUCTION OF CLASSIFIED MATERIAL; SECURITY OF THE ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE Emergency procedures for the protection, removal, or destruction of classified material within the Armed Forces Radiobiology Research Institute (AFRRI) due to natural disaster, civil disturbance, enemy action, entry by unauthorized persons, or evidence of forced entry are as follows:
- 1. After Normal Duty Hours
- a. In case of any emergency listed above, the Security Watch will notify the AFRRI Duty Officer, the AFRRI Classified Material Control Officer / Custodian, and the National Naval Medical Center (NNMC) Security as soon as possible. Security Watch personnel will contact the proper persons listed on the DA Form 727 that is on the front of the safe in Room 3112. NNMC Security will provide a security force to help Security Watch personnel maintain security during disaster control operations, threats, or emergencies, by doing the following:
(1) Establish a perimeter security when directed. (2) Control entering and exiting emergency vehicles and all other traffic. (3) Ensure the greatest possible security for vital areas. (4) Prevent riot, panic, hysteria, and other signs of potential mob action. { (5) Man and secure all entry points against illegal entry into the NNMC and the AFRRI, as appropriate. i (6) Prevent disorderly movements, or other detrimental activities. (7) Prevent sabotage, espionage, and looting. (8) Help to evacuate damaged areas. (9) Perform other related tasks as directed. (10) When directed, dispatch any teams and equipment required for emergency recovery operations. (11) Coordinate the security operations of the emergency recovery unit with those of AFRRI.
- b. The Classified Material Control Officer / Custodian or alternate will 2
determine the extent of the emergency and thereby establish the procedures for safeguarding classified material.
- c. If an unauthorized person is found in AFRRI after duty hours or if any evidence of forced entry into AFRRI is noted, the Security Watch will call the NNMC Security for assistance.
1 Enci ? to .EEEI Inst:- 1020.2i _ _ _ . , _ _ _ _ , . .. ._, _ _ _ ._ _ _._ _ _ . _ , _._
- 2. During Normal Duty Hours
- a. The Classified Material Control Officer / Custodian (or in his/her absence, the alternate) will be notified, who will take responsibility for the security or destruction of all classified material within the AFRRI. -
- b. If the AFRRI is evacuated, anyone having classified material signed out from the Security NCOIC will return the material to the Security NCOIC at the top of the steps ,
directly in front of AFRRI. The Security NCOIC shall safeguard the material until the emergency is over. Then he/she will either return the material to the person who signed for it or return it to the safe. W 2
AFRRI EMERGENCY ORGANIZATION: ASSIGNMENTS AND RESPONSIBILITIES
- 1. Emergency Command Post (ECP). Physical Location: Initially, the ECP will be located under the bridge at the foot of the parking lot in front of AFRRI. The ECP may subsequently be moved to the AFRRI library or to another nearby building having adequate communications if safety, convenience, or the demands of the emergency warrant such a move.
- a. ECP Commander (1) Succession to Command is as follows:
(a) Director, AFRRI (b) Deputy Director, AFRRI (c) Senior military officer present (2) Physicallocation will be at the ECP. (3) Responsibilities: The ECP Commander has overall responsibility for the Institute and the safety of personnel on-site during an emergency and during recovery operations; for ensuring that outside agencies are notified as necessary; and for requesting any needed NNMC or off-site emergency support. The ECP Commander will utilize the Emergency Organization Staff, as outlined in this Instruction, to comply with all responsibilities and duties as' stated. . (4) Duties: (a) Ensure that the ECP Emergency Box in the Directorate Area is carried to the ECP during evacuation. (b) Receive information about the emergency from the sources shown on the AFRRI Emergency Organization Diagram (see page 15 of this Enclosure). (c) Ensure that the NNMC Fire Department has been notified. (Telephone numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.) (d) If applicable, ensure that the NNMC Emergency Room is notified of injured personnel and their status. (Telephone numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.)
- (e) Ensure notification of the CO, NNMC; the IIQ, DNA; the NRC; and the Joint Nuclear Accident Coordination Center (JNACC) in case of an actual emergency, as necessary. (Telephone numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.)
(f) Ensure that additional support is summoned if evaluation of the emer-gency shows that more help is needed. (Sources of additional support with telephone 1 Enci - to JEE: Instr ICO.n
numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation j Information Guide located in the ECP Emergency Box.) 1 (g) Approve information before its release to the news media by the DNA , j Public Affairs /Information Officer. (Naws release information directive is found in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.) (h) Ensure personnel are designated to man the telephone (s) and other emergency communication equipment at the ECP. (i) Ensure that the billet for Recorder for the ECP is manned, to log all actions and decisions at the ECP. (Log books and writing instruments are in the ECP Emergency Box.) (j) If personnel are injured and/or contaminated, direct the Medical Team Leader to provide life-saving actions as needed, and monitor the decontamination of personnel as applicable via the Health Physics personnel. AFRRI Instruction 6310, latest revision, outlines decontamination procedures. (k) Ensure the billets of Special Advisor on Emergency Conditions, EAS Commander, Search Team Marshal, and MedicalTeam Leader, are manned as applicable. (1) Evaluate and provide final approval authority for all major emergency actions to be implemented at the EAS. , (m) Give orders to secure from the emergency condition and reoccupy the ! AFRRI when appropriate. (n) Function as commander for all Emergency Recovery Operations, both immediate and long-term. This includes approv9tl authority for the selection of major recovery alternatives, approval authority for major recovery actions, and authority for sanctioning normalInstitute operational activities to resume. (o) Final approval authority for any planned personnel exposures in excess of 10 CFR 20 limits. Such decisions should be made only after consultation with the Special Advisor on Emergency Conditions.
- b. Recorder for ECP (1) Succession is as follows: .
(a) Secretary to Director (b) Secretary to Deputy Director - (c) As designated on site by ECP Commander (2) Physical location will be at the ECP. (3) Responsibilities: The Recorder for the ECP is responsible to the ECP Commander for maintaining a log of all actions snd decisions occurring at the ECP and
-2 - - - - - _ - - ._._.._._~. - -__ - ..-_ - --_ _ - _ _ ._ ___ _. . - _ _ _ - - . _ _ _ .
I l
~
l for holding reports for the record and subsequent filing with SAF after appropriate review and action has been taken. , (4) Duties: . (a) Receive and record information and reports from the Search Team Marshal and pass this information on to the ECP Commander. (b) Maintain a log of all actions and decisions that occur at the ECP. (c) Maintain a temporary file of reports for the record. These reports will be filed in SAF after they have been reviewed and appropriate action has been taken.
- c. Special Advisor on Emergency Conditions (SAOEC)
(1) Succession is as follows: (a) Head, Radiation Safety Department (b) Acting Head, Radiation Safety Department (c) Most-senior AFRRI Health Physicist on-site (2) Physicallocation will be at the ECP. , (3) Responsibilities: The Special Advisor on Emergency Conditions is responsible to the ECP Commander for providing technical advice and interpretation of information on actual or potentially hazardous conditions, either radiological or nonradiological, and . overseeing all health physics and radiation safety aspects of the emergency response at the ECP, the AFRRI site, and the Institute boundaries. As Head, SAF will maintain AFRRI files of all alerts and exercises under this Instruction. (4) Duties: l (a) Establish appropriate radiation-monitoring programs for the AFRRI site bcundary, Institute boundary, and unrestricted area as required by the emergency and as directed by the ECP Commander. (b) Assure that proper notification is made to outside agencies as required, and verify these with the ECP Commander. (c) Ensure the ECP Commander is provided with a current list of telephone numbers and sources of additional assistance available from outside agencies. (These are listed in the ECP copy of the AFRR1 Fire and Emergency Evacuation Information Guide, in the ECP Emergency Box.)* 1 l (d) Assure the NNMC Radiation Safety Officer is notified in case of an actual radiological emergency / hazard. (e) Decide if the nature of the emergency warrant 3 a beta / gamma survey of the ECP, EAS, and/or Emergency Muster Location (EML), and aevise the ECP Commander accordingly. 3
f (f) Provide advice, assistance, data, and interpretation of data to the ECP l Commander, as necessary. (g) Provide advise, assistance, and consultation to the ECP Commander for , any planned personnel exposures in excess of 10 CFR 20 limits.
- d. MedicalTeam Leader .
(1) The Director, AFRRI, shall identify two individuals to be assigned as the primary and alternate for this Billet. (2) Physicallocation will be at the ECP. (3) Responsibility: The Medical Team Leader is responsible to the ECP Com-mander for managing the treatment of injured and/or contaminated personnel as outlined in AFRRIInstruction 6310.1A. (4) Duties: (a) Assign and direct Medical Personnel to perform life-saving actions, as necessary, for injured / contaminated personnel (b) Estabilah and maintain close coordination with the Team I Health Physics Advisor if any personnel are contaminate (or suspected ottontamination. (c) Establish e.nd maintain communications with NNMC Emergency Room, as necessary.
- e. Medical Personnel (1) The Director, AFRRI, shall ensure at least two personnel, with alternates, have been identified for assignment to this Billet, (2) Physicallocation will be at the ECP.
(3) Responsibilities:. The Medical Personnel are responsible to the MedicalTeam Leader for performing life-saving actions as necessary for injured / contaminated . personnel. (4) Duties: (a) Perform life-saving actions as necessary on injured / contaminated per-sonnel. (b) Keep Medical Team Leader informed of nature and status of injured /- - contaminated personnel.
- f. Team I Health Physics Advisor (1) Assignment and succession of a person to fill this billet shall be accomplished by the Heac', Radiation Safety Department (SAF). .
4
(2) Physicallocation will be at the ECP. (3) Responsibilities: The Team I Health Physics Advisor is responsible to the Special Advisor on Emergency Conditions for assuring that all radiation surveys at and
. outside the. boundaries of AFRRI are performed as required and as directed; assuring that
- all actions concerning radioactively contaminated personnel are performed as required and directed; and assessing radiation levels and environmental releases of radioactive material at and outside the boundaries of the Institute. The Team I Health Physics
~
Advisor is also responsible for directing and assisting the Team I Health Physics Monitors in the decontamination of contaminated personnel.
- (4) Duties
(a) Assure that appropriate emergency radiation equipment is readily avail-able (or accessible) and operable. (b) Assign Team I Health Physics monitoring personnel to perform surveys of radioactively contaminated personnel and of areas outside the boundaries of AFRRI, as directed. (c) Direct and assist the Team I Health Physics Monitor in the decontami-i nation of contaminated personnel. . , (d) Assign Teant I Health Physics monitoring personnel to accompany injured / contaminated persons to the NNMC emergency room, if requested by the Medical Team Leader. (e) Assure that radiation surveys outside the confines of AFRRI are per- ~ formed as required by the emergency conditions when directed by the Special Advisor on Emergency Conditions; provide this data to the Special Advisor on Emergency Conditions, s g. Team I Health Physics Monitors (1) The assignment of two personnel and alternates for this billet shall be accomplished by Head, SAF. (2) Physicallocation will be at the ECP. (3) Responsibilities: The Team I Health Physics Monitors are responsible to the Team I Health Physics Advisor for performing their assigned health physics monitoring ,! tasks. (4) Duties: (a) Perform surveys and conducting the decontamination of radioactively contaminated personnel as required and as directed by the Team I Health Physics Advisor. (b) Accompany injured / contaminated persons to the NNMC emergency room when directed. (c) Perform radiation surveys outside the confines of AFRR1 as directed by the Team I Health Physics Advisor; provide this data to the Team I Health Physics Advisor. 5 4
- h. Search Team Marshai (1) Succession is as follows:
(a) Administrative Officer - (b) Chief, Administrative Services Division - (2) Physicallocation will be at the ECP. (3) Responsibilities: The Search Team Marshal is responsible to the ECP Commander for personnel accountability and for information on the general status of the AFRRI facility immediately after an emergency evacuation. (4) Duties:
, (a) Receive sweep reports from the Evacuation Search Teams.
(b) Receive muster reports from the Department Chairmen / Heads. (c) Determine (from compiling and evaluating data received) if anyone is missing and who might still be in AFRRI. (d) Report information on personnel accountability and facility status to the ECP Commander and to the Emergency Action Station Commander, as applicable. (e) Provide Evacuation Search Team Sweep Reports, Department Muster Reports and any additional personnel or Facility Reports to the ECP Recorder for
~
disposition and filing with SAF.
- 1. Evacuation Search Teams (1) Assignment of personnel and alternates to fill these billets shall be the responsibility of the AFRRI Administrative Officer.
(2) Location. After each Evacuation Search Team Member has searched its assigned area (s), they will report to the Search Team Marshal at the ECP. Each Team Member will then muster with their department at the Emergency Muster Location (EML). (3) Responsibilities: Each Evacuation Search Team Member is responsible to the i Search Team Marshal for searching a specific assigned area (s) for personnel and hazards, and reporting the search results to the Search Team Marshal and, if required, to the EAS , Commander. (4) Duties: Each Team Member is to perform the following duties in assigned
- zone (s), subject to their own discretion and good judgment in case of difficulty:
(a) CHECK all spaces (including rest rooms and equipment rooms) for personnel and immediate hazards. (b) CLOSE doors to offices and laboratories. 6
(c) CLOSE corridor doors. (d) TURN OFF or extinguish (if possible without undue risk) all sources of heat, fire, and/or sparks. (e) CLOSE gas jets (if possible without undue risk). (f) SECURE classified material and lock any safe observed open. (g) REMOVE (or secure) all flammable liquids from the immediate vicinity of a fire or hazard (if possible without undue risk). (h) REPORT any unsecured radioactive source to the Search Team Marshal at the ECP and the EAS Commander at the EAS. (1) DO NOT TURN OFF interior lights, unless they afe the source of a hazard. (j) DO NOT MOVE an injured person unless in imminent danger and likely to sustain further injury if not moved or removed. (k) PUT OUT any fire in assigned zone, without endangering life; or leave zone and report its status to the Search Team Marshal at the ECP and the EAS Commander at the EAS. NOTE: Report always to the Search Team Marshal at the ECP, whether or not able to search assigned zone (s). Make sure that the Search Team Marshal correctly records the Team's report, including any hazards noted and any areas not searched. If an immediate hazard is observed in an assigned area, report directly to the EAS Commander at the EAS. Then report to the Search Team Marshal at'the ECP, and muster at the EML. j 2. Emergenev Action Station (EAS). Physical Location: Initially, the area immediately outside the front door of the AFRRI will be the EAS (see page 2 of Enclosure 1 of this 4 Instruction). After establishing this station, the EAS Commander may move the EAS to another area having adequate communications, for reasons of safety or efficiency; before doing so, the EAS Commander will notify the ECP Commander for approval to move.
- a. EAS Commander (1) Succession to Command is as follows:
. (a) Chief, Radiation Sources Division (b) Physicist-In-Charge (PIC), Reactor i
(c) Acting PIC, Reactor (2) Physicallocation will be at the EAS. (3) Responsibilities: The EAS Commander is directly responsible to the ECP
- Commander for the immediate and continuing assessment of emergency conditions and for all actions taken within the boundary of the Institute during the emergency (including entry) and during any recovery or restoration operation (s).
7
(4) Duties: (a) Act for the Director of AFRRI in performing staff and technical supervision of and compliance with emergency evacuation procedures and actions. , (b) Establish the Emergency Action Station (EAS) and notify ECP when operational. (c) Assign personnel to fill vacant emergency billets at the EAS, if necessary. (d) Direct and advise all EAS personnel (e) Establish and maintain close communications with the ECP Commander, and to provide him/her with status and emergency information. (This can be most easily accomplished by designating a runner to transport one of the three Emergency Walkie-Talkies available at the EAS to the ECP Commander, when evacuating the building.) (f) Receive reports directly from the person who initiated the evacuation or when applicable from en Evacuation Search Team (s) within whose search zone (s) an emergency or hazard is noted. (g) Receive personnel accountability reports /information from the Search Team Marshal. - (h) Receive notification and information on the location, extent, and type of has.ard or emergency throughout its duration. _
. (i) Meet and brief responding Fire / Rescue personnel upon their arrival at AFRRI.
(j) Direct the establishment of Institute controlled-access points as neces-sary, for personnel traffic control and Institute physical boundary security. (k) Establish, direct, and coordinate all Entry Team activities. (1) Recommend actions to the ECP Commander and implement them, if approved. (m) Implement and carry out all directives from the ECP Commander pertaining to activities within the Institute boundaries during an emergency or recovery /- restoration operation. -
- b. Recorder for EAS (1) Succession is as follows:
(a) Secretary of Radiation Safety Department. (b) Secretary of Radiation Sciences Department. (c) Alternate as assigned on-site by the EAS Commander. - 3
(2) Physicallocation will be at the EAS. (3) Responsibilities: The Recorder for the EAS is responsible to the EAS Commander for maintaining a log of all actions and decisions that occur at the EAS, and
. for forwarding received reports and information to the EAS Commander.
(4) Duties: (a) Receive and record information from the Area Controller. (b) Receive an'd record information from the EAS Commander. (c) Maintain a log of all actions and decisions made at the EAS. (d) Upon. termination of alert turn in all records and reports to SAF for filing.
- c. Team II Health Physics Advisor (1) Succession is as follows:
(a) Head of the Safety Operational Health Physics Division (b) Alternate assigned by Head, SAF (2) Physicallocation will be at the EAS.
. (3) Remonsibilities: The Team II Health Physics Advisor is responsible to the EAS Commander for the assessment of radiological conditions within the Institute, and for the direction and coordination of activities of the Team II Health Physics Monitors. ,
(4) Duties: (a) Ensure that the EAS Emergency Box, located in the AFRRI main lobby, is moved to the EAS. (b) Ensure that the front door emergency constant air monitor (CAM) is properly positioned and functioning. (c) Assure that a Team II Health Physics Monitor (s) begins to dress out in appropriate protective equipment for entry with the Entry Team (firemen and others) upon direction and establishment by the EAS Commander. (d) Inform and advise the EAS Commander of radiological conditions within the Institute. Including the result of the emergency CAM sampling. l (e) In coordination with the Area Controller, aid in the setup of a controlled-access point to prevent or reduce the spread of contamination, if necessary, upon establishment and direction by the EAS Commander. (f) Assist in coordinating Entry Team efforts as directed by the EAS Com mander. 9
I 1 (g) Assign a Team H Health Physics Monitor (s) to ac::ompany the Entry i Team (s) to perform radiation surveys, upon establishment of an Entry Team (s) by the EAS 1 Commander. (h) Assess and advise the EAS Commander of the on-site health physics aspects of the emergency or hazardous condition, during the course of the emergency, as necessary. .
- d. Team H Health Physics Monitors (1) This bulet will be filled by at least two Health Physics personnel assigned by SAF.
(2) Physical location will be at the EAS. (3) Responsibilities: The Team H Health Physics Monitors are responsible to the Team H Health Physics Advisor for performing their assigned health physics monitoring tasks. (4) Duties: (a) When evacuating the building, move the EAS Emergency Box to the EAS and set up the front door emergency constant air monitor (CAM). ~ (b) Dress out as directed by the Team H Health Physics Advisor. (c) If designated a member of an Entry Team by the EAS Commander or the Team II Health Physics Advisor, perform radiation surveys continuously during the entry, and inform.and advise the Entry Team Leader of the radiation environment and any radiation hazards. Keep a close watch on radiation dose to the Entry Team Members, and recommend to Entry Team Leader necessary actions to prevent overexposure. (d) Report results of radiation surveys to the Team H Health Physics Advisor or the Entry Team Leader, as appropriate.
- e. Nonradiological Hazards Advisor (1) Succession is as follows:
(a) Head, Occupational Safety and Health Office (OSH)
~
(b) Alternate assigned on-site by EAS Commander. (2) Physicallocation will be at the EAS. . i (3) Responsibilities: The Nonradiological Hazards Advisor is responsible to the i EAS Commander for providing information, advice, and assistance concerning nonradio-logical hazards. (4) Duties: (a) Assure that appropriate and operable emergency equipment is readily available, or accessible, and operational. 10
(b) Provide information, advice, and assistance as necessary to the EAS Commander concerning nonradiological chemical and toxic material hazards within the Institute. . f. Area Contr'llero (1) Succession is as follows: (a) Security NCOIC (b) Acting Security NCOIC (c) Alternate assigned on-site by EAS Commander. (2) Physical location will be at the EAS. (3) Responsibilities: The Area Controller is responsible to the EAS Commander for facility boundary security, for vehicular traffic control at the site, and for personnel trsffic control at the facility boundary. (4) Duties: (a) Assign personnel to direct and control traffic on the roads surrounding AFRRI to ensure quick access for emergency vehicles and_ equipment. _ (b) Control personnel access to the AFRRI to ensure that only authorized personnel enter the building during an emergency. (c) Assign personnel to establish and maintain facility boundary security and personnel traffic control at the facility controlled-access point (s) upon. establishment and direction by the EAS Commander.
- g. Facility Advisor (1) Succession is as follows:
(a) Facility Manager, LOG (b) Assistant Facility Manager, LOG (2) Physicallocation will be at the EAS. (3) Responsibilities: The Facility Advisor is responsible to the EAS Commander for providing information, advice, and assistance concerning the AFRRI facility. (4) Duties: (a) Duties of the Facility Advisor are to perform tasks as assigned and provide information as requested by the EAS Commander pertaining to the AFRRI facilities and equipment. (b) Serve as a member of the Entry Team at the direction of the EAS Commander. 11
- h. Fire Marshal (1) Succession is as follows:
(a) NNMC Fire Marshal (b) Representative of NNMC Fire Marshal at the site (2) Physicallocation will be at the EAS. . (3) Responsibilities: The Fire Marshalis responsible to the EAS Commander for providing and coordinating fire-fighting and rescue operations during an emergency. (4) Duties: (a) Receive briefing upon arrival at the scene, by the EAS Commander. (b) Assign fire and rescue personnel to the Entry Team (s) upon direction by the EAS Commander. (c) Establish and maintain communications with entering fire and rescue personnel (d) Coordinate activities of entering fire and rescue personnel. (e) Inform and advise the EAS Commander of the activities of entering fire and rescue personnel, and of the status of the fi'/e hazard or other nonradiological hazard, as appropriate. . (f) Ensure that fires, other nonradiological hazards, and injured personnel are given fire and rescue attention and treatment, as appropriate, by entering fire and rescue personnel.
- i. Radiation Source Advisors (1) Succession is as follows:
(a) Primary Source Manager from each of the three major AFRRI radiation sources (i.e. Reactor, Cobalt, and LIN AC) (b) Alternates assigned by Chief, Radiation Sources Division (2) Physical location will be at the EAS. (3) Resoonsibilities: The Radiation Source Advisors are responsible to the EAS ' Commander for providing information, advice, and assistance concerning their respective major radiation source facilities at AFRRI. (4) Duties: Duties of the Radiation Source Advisors are to provide information, advice, and assistance upon request by the EAS Commander concerning their respective major radiation source facilities at AFRRI. 12
- j. Entry Team. Personnel appointed to an Entry Team are selected by the EAS Commander at the time of or during an emergency from competent personnel available at the EAS. An Entry Team usually consists of one or more firemen, a Team II Health Physics Monitor, and a member from LOG. Other personnel may be assigned by the EAS
- Commander, depending on the nature of the emergency. l The EAS Commander will assign the duties of the Entry Team before entry into the Institute. An Entry Team Leader will be appointed by the EAS Commander. Upon entry, the Entry Team members are responsible to the Entry Team Leader who, in turn, is responsible to the EAS Commander. Communications will be established and maintained between the EAS Commander and the Entry Team Leader upon entry into the Institute.
- k. Person Turninst in Alarm Upon DISCOVERY of a fire or other hazardous condition, .
(1) PULL the nearest fire alarm. (2) EVACUATE the Institute immediately. (3) REPORT the nature, extent, and location of the emergency or hazardous condition to the EAS Commander or the Security Watch, as appropriate, at the EAS. NOTE: The person turning in or initiating an evacuation alarm shall report to the EAS Commander or to Security Watch Personnel, as appropriate, at the EAS immediately after evacuating the Institute, regardless of whether the alarm was intentional or inadvertent.
- 3. 'Emercency Muster Location (EML). Physical Location: The Emergency Muster Location GML) will be under the bridge adjacent to the front entrance of AFRRI for all AFRRI departments except VMD. VMD will muster in the rear parking lot behind Building 47 (New Animal Facility),
- a. Department Chairmen / Heads (1) Succession is as follows:
(a) Department Chairman / Head for each department (b) Acting Department Chairman / Head for each department (2) Physicallocation will be at the EML. (3) Responsibilities: Each Department Chairman / Head is responsible at the EML for personnel accountability and control within his/her department at the EML and for ~ reporting this personnel accountability information to the Search Team Marshal at the ECP. (4) Duties: (a) Muster and account for all Department personnel at the EML. 13
1 i I (b) Give Department muster report to the Search Team Marshal at the ECP, to include the names of any Department personnel not accounted for, who might be inside the AFRRI. (c) Provide to the Search Team Marshal the names of all Department - personnel who have pocket ion chamber dosimeter readings greater than 100 mR.
- b. Staff ,
(1) All persons not assigned a specific emergency duty or responsibility and who are in the AFRR1 complex at the time of an emergency are classed as staff. (2) Staff Responsibilities. Upon hearing the fire bell, all staff members will immediately evacuate the AFRRI complex via the nearest safe exit, and assemble at the EML. (3) Duties: (a) Immediately evacuate the building via the nearest safe exit upon hearing a fire alarm. (b) Muster in an orderly fashion with the appropriate Department Chairman / Head or representative at the EML (see Enclosure 1) . (c) Follow the directions of the appropriate Department Chairman / Head or representative and the ECP Commander. (Under no circumstances is any member of the staff to interfere with any emergency activities or to act independently after reporting to ' ' the EML.) NOTE: During nonduty days and after 1800 hours on duty days, in addition to the above, each staff member is responsible for signing in and out on the Security Area Register maintained at the AFRRI Reception Desk. W o 9
1 t l i AFRR1 EMERGENCY ORGANIZATION: LINES OF RESPONSIBILITY AND FLOW OF INFORMATION EMERGENCY MUSTER DEPT CHAIRMEN /
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PROCEDURE FOR AFRRI EVACUATION SEARCH TEAMS
- 1. Search Areas. The specific search zones within AFRRI are illustrated on page 2 of this Enclosure.
- 2. Duties. Each Evacuation Search Team shall perform the following duties in its
- assigned zone (s), subject to discretion and good judgment in case of difficulty:
- a. CHECK all spaces (including rest rooms and equipment rooms) for personnel and immediate hazards.
- b. CLOSE doors to offices and laboratories.
- c. CLOSE corridor doors.
- d. TURN OFF or extinguish (if possible without undue risk) all sources of heat, fire, and/or sperks.
- e. CLOSE gas jets (if possible without undue risk).
- f. SECURE classified material and lock any safe observed open. '
- g. REMO E or secure all flammable liquids from the lii1 mediate vicinity of a fire or hazard (if possible without undue risk). .
- h. REPORT any unsecured radioactive source to the EAS Commander at the EAS and ~
the Search Team Marshal at the ECP.
- i. DO NOT TURN off interior lights, unless they are the source of a hazard.
J. DO NOT MOVE an injured person unless he/she is in imminent danger and likely to sustain further injury if not moved or removed.
- k. PUT OUT any fire in assigned zone, without endangering life; or leave zone and report its status immediately to the EAS Commander at the EAS and the Search Team Marshal at the ECP.
l NOTE: Report always to the Search Team Marshal at the ECP, whether or not able i to search assigned zone (s). Make sure that the Search Team Marshal correctly records the Team's report, including any hazards noted and any areas not searched. If an immediate hazard is observed in an assigned area, report directly to the EAS Commander at the EAS. Then report to the Search Team Marshal at the ECP and remain available at the ECP to l provide additional assistance, if needed. If not needed, muster at the EML. l l l l \ l F.nci 5 to M ERI Instr 2020.2G ! f
AFRRI ZONE ASSIGNMENTS FOR EVACUATION SEARCH TEAMS FIRST LEVEL JONE 1-E Y tFl M " ZONE 1-H . F8T P31.Fi FIkli ,
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4
. CRITERIA FOR NOTIFICATION OF OUTSIDE AGENCIES REQUIRED NOTIFICATION Pcrsonnel Notified Requiring Instruction or Regulation Conditions . NNMC Fire NNMC/AFRRI Host-Tenant Agreemt Fire and/or hazardous Department N00168-81274-007; term. date Sep 86 conditions HQ,DNA DNA Instruction 7730.2B Nuclear accident or signi-ficant incident involving nuclear material AFRRI Instruction 5200.14 Felony, crimes, incidents AFRRI Instruction 5200.14 Natural phenomenon or disaster; racial or labor dis-turbances involving DNA personnel or facilities DNA Instruction 5230.1; Nuclear accident or AFRRI Instruction 5230.1 significant incident NRC (after con- AFRRI Reacter License R-84 Reactor or nuclear sultation with and accident or incident concurrence of EAS Commander & Reactor Physicist-in-Charge)
PAO,DNA DNA Instruction 5230.1; Nuclear accident or AFRRI Instruction 5230.1 significant incident JNACC DNA Instruction 7730.28 Nuclear accident or l significant incident l CO, NNMC NNMC/AFRRI Host-Tenant Agreemt Formally declared emer-N00168-81274-007; term. date Sep 86 gencies & drills or practice activities in preparation j for operations under
. emergency conditions l
NRC Title 10 CFR, Part 20, Standards Any incident involving by-(immediate) for Protection Against Radiation product, source, or special nuclear material that has caused or threatened to cause violations of 10 CFR l 20.402 or 20.403 News Media DNA Instruction 5230.1; Promotion of public safety Representatives AFRRI Instruction 5230.1 or prevention of widespread public alarm l Incl ts to /JERI Instr 2020.20
SOURCES OF ADDITIONAI SUPPORT Personnel / Committing Instruction, Organization Regulation. or Letter Tvoe Supoort Offered Disaster Prepared- NNMC/AFRRI Host-Tenant Agreemt Complete emergency ness Officer / Plan N00168-81274-007; term. date Sep 86 support NNMC Emergency Room NNMC/AFRRI Host-Tenant Agreemt Emergency medical N00168-81274-007, term. date Sep 86 treatment NNMC Ambulance NNMC Instruction 11240.20 Emergency medical treatment NNMC Radiation NHBETH Instruction 6470.40 Film badge development Sdety Office ' safety and interpretation; radioactive material counting and monitoring NNMC Decontami- NHBETH Instruction 6470.40 Decontamination of nation Facility personnel NNMC Security NNMC Instruction 11320.1C Perimeter control NBS (Dr. Schwebel) Radioactive material counting and analysis NRC Emergency NRC Radiological Assistance Team Program Environmental Protection Environmental Agency evaluation Maryland Department Environmental of Health evaluation i i l Enci 7 to /,.FER: Instr 2020.2G
l J APPENDlX B TO THE EMERGENCY PLAN FOR THE AFRRI TRIGA REACTOR FACILITY i j
. DISF:OSITION~ FORM Per use ad mis foem. eee All M*3 3. ** M*eenen, egeasy is TACCIN.
e tFlmtsCE :s ;** ;I th6CE. ' W SJ E C , i AO,AFRRI Interservice Support Agreement
' Commanding Officer AO 19 OCT 31
- (CcdeC335), NNMC ~
sherry /51316 Sethesda, MD 20814 Ref:. (a) CO, NNMC ltr NNMC:C335:MS:pse of IJ Oc 1981 Enc 1: (1) ISNA-N00168 31274 007 Enclosure (1) has been signed and is returnd irt accordance with reference (a). Og.ic,ia At Sic,Neo R.S CUNNINGHAM CDR, MSC, USN Administrative Officer 9 0 a M 4
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e } 3 OCCUMEM T ICENTIFl&4 (' Z' ens)
.SUPPoliT AGREEMENT _.E,........ ._ . . ._ ~ A r, ,1 ~
. . _ ~E. m . . . . .. .. . _.
- 24. wAJo.t CCNW ANQ CCCE 24. SUSQACIM ATE COMM ANC COD E
- 2. Suk*b4 Est (Name. Ornse Jrmoed b compasse esersees vnnnta vo n14. a .
Ce-mding Officer, s. antsEnT AonEE9Eu f wuweEm '. tea ='s ^ 7ica C A 75
*"* *~#
Nacional Naval Medical Cantar N00168-81274-007
- 3achesda, Maryland. 20014 3. su,En5EoCo AanEEutur muueEn eEconAnwiCAL.AaruowCsunrnyCoot: N00168-30276-007 0986 5.. RECEIV ER (names Ornes.3rmeed e.comedoes.aemeeep S a. CCCAAC.' PEQSTI'lle tuutER Annad; corces Radiobiology EIT362Z Researett rascituca; '
S c. SusCRQlN ATE.COMe6ANO C30E Uaftnsg..NuclRak" AgenC7 Sesi. see4QM' Coma 6ANO CCCE l Eechesdz,. Maryland 200I4. m 200L OWOGilPA#*HCA4 Anth Cm' C3uJ6TWV CCCE
- 4. SuppCRT AGREEMENT RESCURCE suMM ARY
~ su R*LI Ew W W A** Y EA mt. e". 3RC55 ACCIT10N AL CCSTS g
u r. - o v.u vor m oo.. ..u...A.uc ....u.....u. AK ' I,aundr r Serrice
- S 3.000.00
. AD, AE. I Ccannon Setmrice Alf,. A f Counnorr Servica-AJ.,. AL
- Connotr Serrtce' AM.
Ccannotr Serrice 1 AN I .25 ' O.00 AP,AW,AO ' Util. PtJ. Transtr. I l 9R0 n00 00 n AI I Connon Serrice AZ ,. SA. I Counnotr Serrice BB, BC i Ccannon Serrice BD, SE 1 Cmon Serrice
+ MO, MN i Counnetr Serrice-SN. -
Connnotr Service r l
- _.- 1.
, I I I I TarAL S 883,000.00 de .Er.14w CM QM A-(whoss assawscasses pro,ves saandar eareregassee an edessa ear. o one c;
, 7~. SAVlNGI ACCRU EC/ CCST5'INCU RREC/ h*AN- Y EARS sAVEQ' EXPENoEo To FEDER AL GoVERNM ENT Tip. CcKTS. 7C. 16AN-Y EA AS S AV ED 7d. M AN YEAA5 ExpCNCEO Tam SAvipeGs FY- Fvt FY:
'- PY-
,A PuMC8NG. ANC REIMSURSEMENT AMR ANoEMENT (factues edt eeesess.concorrwne essune/resmourseweene proceeures. ,o r u.tuneins.
naueam .msra. ,ean. 1,ntsneis.,ameeen,. c.e.. Asas nae us e,,o.,.na.. -nocn aoeaa neaur ene-
<7,..e .,s o ., s ,. 3 P
AERRI will submir MI?R's to NNMC for billing authorization. NNMC will submit SF 1080 for =cuchly billing to AFERI, DefEnsa Nuclear Agency, Bethesda, Maryland. 20014
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^m DoD 4000.19-M APPENDIX IV CATECORIES OF SUPPORT SERVICES ACMINISTRATIVE AND LOCISTICAL SUPPORT SERVICIS CATE CATE.
- AA Computer & Daca Processing AI Terminal Operations AH Finance &.Accouncing AU Administrative Offica Sp' ace AC Military / Civilian Personnel AV' Education Services AH Legal AV Civil Engineering AE Mail. Pic3c-up and. Delivery AI Propercy ')isposal Services AF Custodial AT Administracive Services AG. Eurchasing/Conme-H vig AI Informacion Office Services AIE Eira Protectictr BA Religious Services / Chaplain-Ar Folict Proteccion BH. Safety A.I Housing / Lodging BC Comunicacion Services AIC Laundry / Dry Cleaning BD' Comunity Services AL. Medical /Dencal BE Logiscic Air-Suppore AM Messing 3F' Officer /NCO Clu Service AN Storage / Warehousing BG Social Accions AO' Tcansportacion BH' Search & Rescue AE Utilicies EI Tesc &. Eva1uacion AQ- Hertuary EI Weather Service AR Stavadoring BIC Aerial / Photography AE , Calibratiotr of Precision Instr. EL Ceodetic Support SUPPLY SUPPORT MAINTENANCE CATECORIES SUPPORT CATECORIES SA. Aircraft MA EN Aircraft Equipment &. Components -
MB . _ _ SC Amunicion- MC SU Ordnanca Equipment &. Components MD
. SE Cloching & Textiles ME SF Cormuunicaciotr Equipmene & Components ME'
_ EG Vehiclea . MG SH. Veh+-"T e Equipment & Components MH
. SI Construccion Equipment & Components MI EJ Materials Handling Equipmenc & Components MJ SIC Eire Fighting Equbment &. Components
- MK SL Electrical Equipment &.Componencs ML SM Electronic Equipment & Components MM SN ' General Supplies MN SO Medical /Dencal Equipment & Components MO
,. SF Missiles MP
, SQ Missile Equipment &. Components MQ SR. Parachuter MR SS- Photographic Equipment & Components I
MS
. ST Petroleum,. 01.ls,. Lubricants & Chemicals MT i
SU Railroad Equipment & Components MU l SV Ships & Vesseis MV l SW Subsistence Supplies MW SX Life Support Equipment i MX SY - Office Machine Repair MY SI Industrial Planc Equipment MZ 41 l 6 Govtitesesen? PewsTissel OpseCE:19?e 1st.4ted et i.3 f
l
.. 4 s . mmI
$7ECIFIC PROVISIONS 1 Ganarait a The agreemanc baevaan the Consnanding Officar, Nacional Naval Medical cancar referred. to harain as the. "Suppliar/Hoac" and che. Commanding Officar, Armed Forces Radiobiology Rasaarch Institure rafarred to harain as the "Racaiver/Tanant" form =1has the incarsarvice support to be rendered, and is negociacad. in accordance with the: following directivas:
- 1) DOD 400.19 - Defensa Rara 11 Incarservica Support Manual
- b. This agramment is based. upon the, assumed continuance of mission and tasks assignad. to che suppliar and/or Racaiver as presently prescribed by curranc diretcives front higher anchority and. accompanying functional f=d4"!. responsib 41 d cias . When changes in chasa respectiva responsibilicias occur this agramment.will be amandad. to reflace such changes, and if appropriaca raquases for funding adjustmancs will be made ac char cima.
- 2. Support Functions Tha Supplier will provide the sarvices , supplies ,
utilicias,. fac111cias, assiscance and data as set forth in this agreemanc at Annar II, subject to reimbursement when appropriata, in accordance with cpplicabla.deparemanc directivas. Whera "raimbursable or non reimbursable" for an itant is not indicated, the. support providad by the Suppliar to the Racalver ' rill ba on a. nonreimbursabia basis. 3 .. Raimbursement 31111ngs en Racaivar wi11 ba on a monthly basis. Suppliar will bill Racaivar on 57 1080 for all servicas notad as reimbursabia in Annex j II Tha.Racaiver warr submit a. M4 T4 *=7 Incardeparrmancal Purchasa Raques e
- (MI2R.) DD Forz 448 to Suppliar citing each specific type of reimbursable servica; tha accouncing classificacion which will bear the cost of the servicas; and the number of this agreemanc and the dollar limitation. The Suppliar wd11 acknowledge acceptance of services requestad by complacing and returning an Acceptance of MI?R DD Form 448-2 within five working days of racaip t.
. 4 Pl==4n3 Requiramancs. The Racaiver will advisa the Supplier relative en any changes in support requirements in sufficient time to insure budgetar r recognition and to pernic the Suppliar as much time as possible to adjus c aTt respond to Receiver requiramancs.
5 Review, Revision, Modification and Cancellation ,
- a. This agramment shall be reviewed annually, during July, by each par:y to avaluata its ef fectiveness, currency and mutual budgetary i= pact and to datarmine the naad. to initiata and to ef f ac: modification in time to become effective by L Oc:ober of that year.
(. ( .
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- h. This agraammac is subf act to modi.iication or car.ninacion as mutually ag;:aad. co in. accordanca wich. che. following.:
L). Raquasts for modificacion will be forwarded by ona parcy em tha. other by writrazt antica Mod 4 NM ons. en t-his agreemanc v411 be consecutively nuairerad. axnL will be affacci.ve upctr appro. val by both parties. . Z) This agreemanc will be carminated. if sicher party is disescablished a= when direccad by higher authority.
- c. Thi.s agrammene shall concinua in afface unedi che dace shown in Block 4 or until. it. is carminacad as above.
- 6. Tan =ne shall hava exclusiva use of the assigned fac111cias and buildings.
Tanarte shall. have che, right to usa in, common. with Ecst; roada, packing areas (as assigned.);. pedascrian walks, utilicy syscams,. firm. and. other alarm sys cams, and archanga and recrancion fac111cias (aucharized military personnel only) . 9 l e e
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{- s N ANNEX III
, r0 3ET*JEEN
^
TZE NAIIONAL NAVAL MEDICAL CENTER AND
- - ARMED FORCES RADI0 BIOLOGY RESEARCH INSTITUTE Boards and Committees of the NNMC to which AFRRI may nominate members:
Number to Boards and Committees Be Nominated L Advisory Board COM (0) 1
- 2. Advisory Group EM Club l
- 3. Advisory Group ist and 2nd Class Mess 1
- 4. Enlisted. Recreattua. Committee 1 5 Recreation Council 1
~
&. Junior Advisory Board [- COM (0) 1 71 Board.of-Appraisal (Utilities) 1
- 8. Medical Library Committee 1
-r
- 9. Saf,ety Policy Committee 1
- 10. Shop Safety Committee i
- 11. Supervisors Safety Committee 1 s
=
O
.9
i; , , e -- l' . . s / 1 '4 i.4 Emerg'ency Plan ! ~
~
- forithe: -
y AFRRI TRIGA Reactor Facility i = , . 1 2 : l.icense 484 or g , m
- o l
e
- c. Docket No: 50170 G I F
( _ l
- , 4 1
,i s is DEFENSE NUCLEAR AGENCY
(> ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE BETHESDA, MARYLAND 20814 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ 1}}