ML20216H833

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Proposed Tech Specs Changing License R-119 to Possession Only License.Revised Physical Security Plan Encl
ML20216H833
Person / Time
Site: 05000087
Issue date: 06/19/1987
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20216H801 List:
References
NUDOCS 8707010594
Download: ML20216H833 (34)
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FSAR APPENDIX A FACILITY LICENSE NO. R-11?

PROPOSED TECHNICAL SPECIFICATIONS FOR THE-POSSESSION ONLY FACILITY LdESTINGHOUSE NUCLEAR TRAINING REACTOR DOCKET NO. 50-87 LJ 9707010594 070619 PDR ADDCK 05000087 P PDR

LICENSE NO. R-119 PROPOSED AMENDED TECHNICAL SPECIFICATIONS FOR THE WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR TRAINING REACTOR O '

TABLE OF CONTENTS

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1.0 DEFINITIONS 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS' 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Radiation Monitoring  ;

4.0 EXPERIMENTS 5.0 SURVEILLANCE REQUIREMENTS 5.1 Radiation Monitoring 6.0 DESIGN FEATURES j 6.1 Site and Reactor Room j

6.2 Defueled Status of the Reactor L d

6.3 Reactor and Dump Tanks I 1

6.4 Control and Safety Systems 7.0 ADMINISTRATIVE CONTROLS 7.1 Organization 7.2 Audit and Review 7.3 Operating Procedures 7.4 Actions to be taken in the Event of a Reportable Occurrence 7.5 Reporting Requirements 7.6 Records O

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The Westinghouse Nuclear Training Reactor has been defueled ard the Special Nuclear Material shipped to a NRC approved recipient. The propeted Technical Specifications amend the present Technical Specifications to conform with conditions for a non-operating reactor for possession of the facility without possession of SNM. The primary purpose of the proposed Technical Specification is the safe storage of the reactor components and remaining licensed material with the assurance that no significant radioactive material is released from the Facility (Public Safety).

1.0 DEFINITIONS The following terms are defined to aid in the uniform interpretation of the specifications. -

1.1 Administrative Controls - the provisions related to organization and management, personnel requirements, procedures, record keeping, review and audit, and reporting that are considered necessary to assure operation of the facility in a safe manner.

1.2 Moderator-Shield Water - the water that is placed in the reactor tank'.

1.3 Operable - means a component or system is capable of performing its intended function. (Operating means it is performing its function.)

1.4 Reactor Operational - means the reactor is not secured.

1.5 Reactor Secured - means that all control rods are in their down positions and the key is removed from the console lock, or when there is no fuel in the core.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Not Applicable. The reactor shall remain secured. i

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3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Radiation Monitorina Applicability These specifications apply to the minimum radiation monitoring requirements for the reactor f acility.

Objective The purpose of these specifications is to assure that adequate monitoring is available to preclude undetected radiation hazards or uncontrolled releases of radioactive material. 1 Specifications 3.1.1. Instruments to permit the periodic sampling and measuring of radioactivity in the air and the moderator-shield water shall be provided.

3 .1. 2. Portable detection and survey instruments shall be provided.

Bases The availability of instruments to measure the amount of i radioactivity in the air and moderator-shield water will assist in l assuring continued compliance with the requirements of 10CFR Part

20. The availability of the required portable monitors provides assurance that personnel will be able to monitor potential radiation fields before an area is entered.

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,, 4.0 EXPERIMENTS

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l Not Applicable. The reactor shall remain secured.

t 5.0 SURVEILLANCE REQUIREMENTS I Actions specified in this section are applicable to the possession only condition of the facility and shall be performed within the specified surveillance period.

5.1 Radiation Monitoring Applicability l

These specification apply to the surveillance of the radiation l 4

monitoring equipment and activities of the facility.

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', Objective The purpose of these specification is to assure the continued validity of radiation protection standards in the f acility.

Specifications i

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1. The portable radiation survey instruments shall be calibrated semiannually.

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2. The air in the reactor room shall be sampled and measured for particulate activity monthly.

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3. Water, if any, remaining in the reactor tank and dump tank shall I be sampled and measured for radioactive contaminations monthly.

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4. The reactor facility shall be surveyed for radioactive

( ) contamination semiannually.

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1 Bases u Experience has demonstrated that calibration of the portable survey l

instruments semiannually is adequate to assure that significant deterioration in accuracy does not occur.

The specified frequencies for monitoring radioactive contamination in the air and water in the reactor room as well as in the overall reactor facility is based on previous experience.

Surveillance testing intervals shall also contain maximum intervals as set out below to provide operational flexibility and not to reduce frequency. Established frequencies shall be maintained over the long term.

a. Semiannual (intervals not to exceed seven and one-half months).
b. Monthly (intervals not to exceed six weeks). i 6.0 DESIGN FEATURES 6.1 Site and Reactor Room l

,The facility known as the Westinghouse Nuclear Training Reactor is located on Commonwealth Edison property adjacent to the exclusion area for the Zion Station.

6.2 Defueled Status of the Reactor The reactor fuel elements, including control rod followers, have been j removed from the facility and shipped to a NRC approved recipient. l e

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6.3 Reactor and Dump Tanks The water from the reactor tank is dumped to the dump tank. The water te:tod to be within the specified limits of 10CFR20 may be discharged from the dump tank.

6.4 Control and Safety Systems The reactor controls are deenergized, removed from the core and stored in the facility. The reactor safety system is no longer l required for the non-operating reactor. I 7.0 ADMINISTRA.TIVE CONTROLS l 7.1 Organization The facility shall be under the direct control of the Facility Manager. He/She shall be responsible to the Westinghcuse management for the safe operation of the reactor facility. The Facility Manager (or his/her Appointee) shall review and approve the operating procedures prior to their use in the facility and within the limits prescribed by the facility license. He/She shall enforce rules for l

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the protection of personnel against radiation.- A Radiation Safety Engineer, appointed by the Facility Manager, shall be responsible for maintaining surveillance over all radiation monitoring in compliance with State and' Federal regulatory codes and standards.

7.2 Audit and Review 7.2.1 The Reactor Safeguards Committee (RSC) shall include at least three scientists or engineers who are not in the line organi-zation responsible for reactor operations and'shall represent at least one half of the Committee membership. The minimum qualification of the RSC members with regard to nuclear experience shall be:

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1. Each member must have a minimum of five years industrial l experience in nuclear and related fields and must have a minimum .

of three years of active participation in his nuclear oriented i

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2. The experience end knowledge of each member must be applicable to or pertain to the Committee's responsibility to properly review the f acility and its operation from the standpoint of safety.

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3. Each member must be capable and willing to exercise his individual judgement in regard to all Committee reviews and decisions.

7.2.2 The RSC shall meet at least once each six months. A quorum of the RSC shall consist of at least four members and at least half of those present shall be from organizations outside the line organization responsible for facility operation.

, 7.2.3 The RSC shall review activities and advise the Facility Manager and/or whatever echelon of management it feels appropriate on all matters pertaining to the safe operation of the facility. The reviews shall coveri

1. Proposed normal operating procedures,. emergency procedures and changes thereto. .
2. Safety standards associated with the operation of the facility.
3. Proposed changes to the Technical Specifications.
4. Facility operation for compliance with internal rules, procedures and regulations, and with license provisions, j
5. Performance of facility apparatus and equipment.

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6. Proposed changes or modifications to the facility not described in the Safety Analys'is Report.

7.2.4 Recording and reporting requirements for the RSC shall include:

1. Minutes of each meeting.
2. Special reports on facility inspections, including Committee's findings.
3. Special reports on facility radiation safety practices and records made semiannually.
4. All Committee reports and meeting minutes shall be l transmitted through the line management up to and including  ;

the Manager, TOS.

l 7.3 Operatina Procedures 7.3.1 Approved written procedures shall be followed for the following items: ,

1. Radiation safety procedures.
2. Emergency situations.

7.3.2 New procedures and changes in the operating procedures shall require review by the RSC and the approval of the Facility Manager. -

7.3.3 Temporary changes in the operating procedures which do not change the intent of the original procedures may be made by the Facility Manager. Such changes shall be recorded in the operating records and reported to the RSC.

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7.4 Actions to be Taken in the Event of a Reportable Occurrence i

7.4.1 With the removal of the fuel from the reactor, Reportable  !

Occurrences shall include but not necessarily be limited to the following:

1. A significant uncontrolled release of radioactivity external j to the reactor facility.
2. An exposure of personnel in excess of approved NRC levels.

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7.4.2 In the event of a Reportable Occurrence, the following actions shall be taken:

1. The Facility Manager shall be notified and corrective action taken prior to resumption of the' operation. involved. I I

- 2. The licensee shall notify, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telsphone or telegraph, the NRC and shall submit within ten days a report in writing.

3. A report shall be made which shall include an analysis of the cause of the occurrence, efficacy of corrective action and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Reactor Safeguards Committee for review and shall be maintained as part of the facility records.

7.5 Reporting Reauirements In addition to reports otherwise required by applicable federal regulations, the licensee shall report the following occurrances to the NRC in accordance with the requirements of 10CFR50.73d.

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7.5.1 The licensee shall report to the NRC in writing within 30 days of any change in the Facility organization'al structure.

7.5.2 The licensee shall submit in writing, to the NRC an annual operating report within 60 days after the end of each calendar year, providing the following information:

1. A narrative summary of operating experience and changes in facility design and operating procedures related to safety of the public.
2. Discussion of the major maintenance operations performed during the reporting period, including the reason for any corrective maintenance required. 1
3. A summary description of changes in the facility or procedures, and tests and experiments carried out under the conditions of Section 50.59 of 10 CFR Part 50.

o 4. A sunrnary of the nature and amount of radioactive ef fluents

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released or discharged to the environs beyond the effective .

control of the licensee as measured at or prior to the point of such release or discharge.

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5. A summary of reportable occurrences.

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't.6 Records 7.6.1 In addition to the requirements of applicable regulations, records and logs shall be prepared and retained for a period of at least five (5) years for the following items as a minimum: -

1. Reactor operating records, including power levels and periods-of operation at each power level.

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2. Records of inadvertent trips,-including reasons therefore.
3. Records of experiments, including any unusual events involved i in their performance and in their handling.
4. Records of reportable Occurrences.
5. Records of' tests and measurements performed pursuant to the Technical Specifications.
6. Records of maintenance operations involving substitution or .

replacement of reactor equipment or components.

7.6.2 Records and logs shall be prepared and retained for the life of the facilit'y for the following items as a minimum:

1. Records of fuel inventories and transfers. )
2. Records showing radioactivity released or discharged into the air or water beyond the effective control of the licensee as measured at or prior to the point of such release or discharge. I
3. Records of facility contamination and radiation survey results.

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4. Updated, corrected, and as built drawings of the f acility.

7.6.3 Records of radiation exposures for all facility personnel and visitors shall be retained indefinitely or~until the Commission authorizes their disposal.

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l FSAR APPENDIX 8 FACILITY LICENSE N O '. R-119 EMERGENCY PLAN FOR THE 14ESTINGHOUSE NUCLEAR . TRAINING REACTOR FACILITY DOCKET NO. 50-87 JUNE 1987 ALL FUEL AND f4EUTRON SOURCES'HAVE BEEN SHIPPED I OFF-SITE TO APPROVED DOE FACILITIES. 'THE ONLY REMAINING RADIOACTIVE MATERIAL WITHIN THE FACILITY CONSISTS.OF ACTIVATED METALS AND CALIBRATION SOURCES FOR RADIATION DETECTION INSTRUMENTATION.

UNDER THESE CIRCUMSTANCES AND WITH A " POSSESSION ,

ONLY" LICENSE FOR THE FACILITY, AN EMERGENCY PLAN FOR THE FACILITY IS'NOT NECESSARY.

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FSAR APPENDIX C FACILITY LICENSE NO. R-119

' OPERATOR REQUALIFI. CATION PROGRAM FOR THE WESTINGHOUSE NUCLEAR TRAINING REACTOR DOCKET NO. 50-87 DELETED DUE TO THE NON-OCEFATINC- STATUS OF TWE FACILITY .

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'N FSAR l APPENDIX D FACILITY LICENSE NO. R-119 PHYSICAL SECURITY PLAN i FOR THE WESTINGHOUSE NUCLEAR TRAINING REACTOR DOCKET NO. 50-87 m

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4 THE SECURITY PLAN HA5 E:EEN FEVISED TO FEFLECT THE FEMOAL OF ALL 5 FECIAL NUCLEAR MATERIAL 5 FROt' THE FACILITY O

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O TABLE OF CONTENTS i

1.0 Introduction f i

2.0 Use and Storage Area at a Fixed Site 2.1 General Layout 2.2 Area Where Material Is Used and Stored 2.2.1 Temporarily Established *CAA's 2.2.2 Permanently Established CAA's l

1 3.0 Detection Devices and Procedures.

3.1 Earliness of Detection 3.2 Detection Through Monitoring of Controlled Access Areas (CAA)

W 4.0 Access Control at a Fixed Site 4.1 Preauthorization Screening l i

4.2 Badging System 4.3 Lock System 4.4 Personnel Entry Control System 4.5 Escort System 4.6 Search 5.0 Security Organization at a fixed Site 5.1 Management Organization 5.1.1 WNTC Manager 5.1.2 NTR facility Manager 5.1.3 Security Officer 5.1.4 NTR Lead Engineer 5.1.5 Licensed Operators O 0084N 4

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- 6.0 Connunications at a Fixed Site I

i 7.0 Response Procedures at a Fixed Site 7.1 General Procedures 7.2 Bomb Threat to Facility 7.3 Civil Disturbances -

7.4 Equipment Out of Service 7.5 Local Law Enforcement Authorities 7.5.1 Relative Locations of WNTC and Police Administration Building 7.5.2 Size of Force 7.5.3 Kind of Assistance 7.5.4 Arrangements 7.5.5 Reports 8.0 Material Transportation Requirements 8.1 Advance Notification 8.2 Receiver Confirmation 8.3 Container 8.4 Inspection 8.5 Responsibility'for In-Transit Physical Protection 9.0 Receiver Requirements Transportatjon

'10.0 In-Transit Physical Protection Requirements i

10.1 Communications 10.2 Minimum Transit Times 10.3 Preauthorization Screening 10.4 Response Procedure 10.5 Notification 4 10.6 Lost Material Notification O Oee ,

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i 11.0 - Export Requirements 12.0 Import Requirements FIGURES

1. WNTC Site
2. Zion Site Map
3. Map of Zion
4. WNTC and NTR Facility Building
5. NTR Facility Layout
6. NTR Visitors Register Record
7. Oper.ir.; :nd C10;ir.g "0 Ord g N, 1 Centrolled A :::: Ar::
8. Security Organization Chart iii 0084N W

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1.0 Introduction This document provides the physical security plan for the Westinghouse 1 Nuclear Training Center (WNTC) at Zion, Illinois. In anticipation of (

decommissioning the Nuclear Training Reactor (License R-119), all special i nuclear material, including both the fuel and sealed neutron sources, has I been shipped offsite to Department of Energy facilities. With the removal of the fuel and sources, a physical security plan for the protection of special nuclear material is not required. Pending completion of the decommissioning of the facility in accordance with the Decommissioning Plan approved by the USNRC, this plan describes the physical security measures to be taken for the protection of the licensed facility and the small remaining quantities of licensed radioactive material. The format of this plan follows the previously approved physical security plan with appropriate indications to note those provisions which are no longer applicable due to the absence'of special nuclear material.

2.0 USE AND STORAGE AREA AT A FIXED SITE 2.1 General Layout The site characteristics and location are shown in Figures 1, 2 and 3.

The layout of the Westinghouse Nuclear Training Center (WNTC) building is q shown in Figure 4.

The site is located on property owned and exclusively controlled by Zion Generating Station of Commonwealth Edison Company. The property boundary is shown in Figure 2. Commonwealth Edison is a joint venture partner with Westinghouse in the Training Center, and has effectively relinquished control of the site shown in Figure 1 to Westinghouse for operation of the Training Center.

The NTR Facility controlled access area is the cross-hatched area shown in Figure 5. ,

2.2 Area Where Material Is Used and Stored 2.2.1 Temporarily and Permanently Established Radioactive Material Area Other areas within the NTR Facility may be established as Radioactive Materials Storage Areas in accordance with the provisions of 10 CFR 20 for radioactive materials in restricted areas.

2.2.2 Radioactive Materials Area l The reactor room is designated as the Radioactive Material Area in the NTR facility. The Radioactive Material Area contains the reactor, and 3 radioactive materials storage area (see Figure 5). The Radioactive I (3

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O Material Area is a vault type room approximately 27 foot cube in size and geometry. Figure 5 identifies the important features of the Radioactive Material Area and the NTR Facility.

Walls. Roof and Floor The walls of the Radioactive Material Area are composed of 8 inch concrete i block and 5 inch gypsum block. The north wall is penetrated by a pipe trench 26" x 12" just below floor level. There is also a 24" x 10" ventilation supply duct penetration in this wall. j The roof of the Radioactive Material Area is composed of sheet metal with 1 1/2" ribbing to carry a load of 55 lbs per f t . The sheet metal is covered with > 2" of rigid insulation and a roofing membrane of built up 1 asphalt-gravel composition. An exhaust fan with a 12" x 12" duct  !

penetrates the Radioactive Material Area roof.

The floor is composed of greater than 4 inches of poured concrete.

Points of Ingress and Egress l The south wall has an opening 10' 41/2" wide and 7' 41/2" high for large

.. equipment access purposes. The opening has a metal door jamb and three O

V sections of enclosure. The sections consist of two transition panels bolted to removable mullions and to the door jamb and a hollow metal emergency exit door 3' x 7' - 2". The emergency door (door no. 7) 1 has no hardware on the outside and is opened using the emergency crash bar j hardware on the inside. -

l The interior wall has one door opening 3'4" x_9'0". This is the normal [

entrance into the Radioactive Material Area, (door no. 6 in Figure 5).

There is a metal door jamb installed with a hollow metal door, 3' 0" by 8'10". There is a small 10 x 10 inch wire reinforced viewing window in the center of the door at about five feet f rom the floor level. The door has six pin key lock and latch with an emergency crash bar on the Radioactive Material Area side for emergency exits.

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Storage of Special Nuclear Materials Not applicable with no SNM at Fixed Site.

Access to the Radioactive Material Areas Access to the Radioactive Material Area is controlled by members of the NTR staff who control the opening and closing of the access doors. l l

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O Lightina in the Radioactive Material Area No special arovisions for lighting within the Radioactive Materials Area are' required.

3.0 DETECTION DEVICES AND PROCEDURES AT A FIXE 0 SITE 3.1 Earliness of Detection Perimeter Monitoring Doors 6 and 7 (Fiaure 5). Each of the access points to the Radioactive Material Area is monitored by a magnetic switch. mounted on the inside of the door actuated by a magnet mounted on the door jamb. When the magnetic switch is opened (door open), an alarm is actuated at the alarm panel in-the Control Room (Figure 5).

Duress Alarm Not applicable with no SNM at Fixed Site.

Alarm Controls and Indications Controls and Indications at WNTC

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Annunciator Panel. The annunciator panel in the NTR Control Room (for location, see Figure 5) contains audible and. visual alarms for the following circuits. l

1. Two zones for Doors 6 and 7.

Each circuit is called a " zone" or a " channel" or sometimes a " subsystem" or " system".

l Indic'ations at the Zion Police Administration Building Not applicable with no SNM at Fixed Site.

l Isolation Zone Monitoring No isolation zone monitors'are installed.

. Emeraency Power Supply Not applicable with no SNM at Fixed Site.

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Alarm Stations The Nuclear Training Reactor (NTR) Facility has no continuously manned alarm stations. It does have a Security Alarm and Control Panel located in the Control Room as shown in Figure 8.

3.2 Detection Through Monitoring of Radioactive Material Area Radioactive Material Monitoring l l

Doors 6 and 7 (Figure 5).

Each of these access points to the Radioactive Material Area is monitored i I

as described in section 3.1.

Radioactive Material Area Interior.

Not applicable with no SNM at Fixed Site.

Radioactive Material Area Microwave System Operation.

Not applicable wit'h no SNM at Fixed Site.

g-') 4.0 ACCESS CONTROL AT A FIXED SITE V Access to the Radioactive Material Area is directly controlled by the NTR i Facility Manager, through her designees. Any person not so designated, _ l who is in the NTR Facility, is under the direction of an NTR staf f member. Access to the Radioactive Material Area for these persons is  !

directly controlled by an NTR staff member.

4.1 Pre-authorization Screening Not applicable with no SNM at Fixed Site.

4.2 Badging System Not applicable with no SNM at Fixed Site.

4.3 Lock System Types and Kinds of Locks The Radioactive Material Area entry door has a high quality 5 pin lock s with more than 10 key cutting levels 9er pin. The lock meets U.L.

Standard 437 and has U.L. approved hardware with a 2-1/2" deadbolt. The .

lock will capture the key when unlocked. The Radioactive Material Area emergency door has a crash bar which can only be opened from the inside.

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v 4.4 Personnel Entry Control System Access Authorization I

The NTR Facility is sufficiently small and the normal access (Door 6) to l the Radioactive Material Area is free of obstruction to enable an NTR l staff member performing other functions in the Facility of effect physical l access control to the Radioactive Material Area by' monitoring entry of j unauthorized persons into the area. ]

The entrance doors (Doors 6 and 7) to the Radioactive Haterial Area are closed and locked at all times the Radioactive Material Area is not occupied.

In addition, the main entrance door to the Facility is posted " Restricted Area, Authorized Personnel Only" to deter casual passersby.

Every NTR Staff members personally knows all other staf f members and can easily recognize unauthorized persons in the Facility.

i NTR Staf f Members eiercise their own mature judgment in authorizing access to only those individuals who have legitimate reasons for entering the  !

Radioactive Material Area. 1 Access Registration Unauthorized persons are required to register upon entry into the NTR Facility (See Figure 6). No additional registration is requir:J for entry into the Radioactive Material Area.

I Radioactive Materials Area Access Points.

Door 6 is main'tained shut and locked when access is not required. The hours per day and days per week that the Radioactive Material Area is open depends upon the maintenance and work schedule and may vary widely f rom day to day and week to week.

Access Controls.  ;

NTR staff members are authorized to approve access of other persons to the Radioactive Material Area, and exercise their own mature judgment in authorizing access to only those individuals who have a legitimate reason for entering the Radioactive Material Area.

Vehicle Access Points There are no vehicle access points to the Radioactive Material Area.

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. l O 4.5 ESCORT SYSTEM Personnel Escort NTR Staff Members control access to the Radioactive Material Area. They I will exercise their own mature judgment in limiting the number of persons authorized access at any one time to a number easily controlled to ensure no activity takes place that could lead to the unauthorized removal of radioactive materials or reactor components.

4.6 Search Not applicable with no SNM at Fixed Sites.

5.0 SECURITY ORGANIZATION AT A FIXED SITE 5.1 Manaaement Oraanization The management structure for operation of the NTR Facility is shown in the organization chart on Figure 8. Individuals in this organization structure share the responsibility for the physical security of the NTR Facility. No guards or watchmen are employed.

Responsibilities for security of the positions shown in Figure 8 are provided below. A single individual may occupy more than one position, and individuals assigned to positions in Figure 8 may have other duties at the WNTC besides those described below.

5.1.1 NTR Facility Manaaer The NTR Facility Manager is responsible for the operation, decommissioning, and maintenance of the NTR Facility.

5.1.2 Security Officer The Security Officer is responsible for and reports to the NTR Facility

' Manager for matters pertaining to NTR Facility security.

5.1.3 NTR Coordinator The NTR Coordinator is responsible for the administration of the NTR Facility with respect to training, compliance with the Facility operating ]

license and Technical Specifications, related documentation and records, i and facility reports; including those pertaining to NTR Facility security. )

i 5.'1.4 NTR Lead Enaineer  ;

The NTR Lead Engineer is the individual with the technical knowledge to perform maintenance on all reactor systems, including security systems, o e 1

O. 5.1.5 Licensed Operators Not applicable with no SNM at Fixed. Site.

6.0 RESPONSE PROCEDURES AT A FIXED SITE Communication System Telephone service is provided between the NTR Facility and local law enforcement authorities, i

7.0 RESPONSE PROCEDURES AT A FIXED SITE 7.1 General Procedures Whenever the NTR facility is occupied, the NTR Staff Member present is responsible for ensuring security to the Radioactive Material Area.

7.2 Bomb Threat to Facif j;y 1

When a bomb threat is received at the NTR Facility, as mucti information as possible is to be otti.ined by the recipient of the information. The .

- following procedures will be initiated by the on duty NTR Staff Member. I (1) The NTR Facility Manager, WNTC _ Manager and Emergency Coordinator are notified. The NTR Facility operations are terminated.

(2) If deemed necessary, the Training Center staff and all building I occupants are alerted, assembled and evacuated. J (3) The Zion Fire and Police Departments are notified. The Fire Department has access to a trained bomb squad.

(4) A systematic' search of the NTR Facility is performed by the NTR Manager' and/or selected staf f personnel.

(5) Any unusual packages or boxes found will be considered suspect.  ;

They will not be touched until the area is cleared and trained bomb disposal personnel are present to remove and dispose of them.

(6) The finding of a possible bomb does not mean that the search is  ;

stopped. It will continue u til the complete facility has been

. searched and cleared.

f (7) The decision to terminate the bomb threat emergency is that of the TOS-W Manager or designated alternate.

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7.3 Civil Disturbances l In the event of a civil disturbance which could involve the NTR Facility, the following steps will be taken:

(1) The WNTC Manager, the NTR Facility Manager, and the Security Of ficer are notified immediately.

(2) The NTR Facility is " closed" and the NTR Facility staff members and visitors on duty move to a secure area in the Training Center.

(3) The decision to terminate the emergency and return to normal operation is made by the NTR Manager or designated alternate.

7.4 Eauipment Out of Service Any of the detection and alarm subsystems described in section 3.1 may be placed out of service for maintenance or repair, or may be found to be out of service during routine periodic testing. No special action is required when the Facility is manned. If the facility is not manned, the Radioactive Material Area should be entered once per week to inspect for unauthorized entry.

n The failure of an individual component does not necessarily render an entire subsystem out of service. Rather, an evaluation of the situation should be made by the NTR Facility Manager and the Security Officer to determine the degree of degradation of the affected subsystem.

Documentation'of such evaluations, including the basis for the resulting conclusions, shall be retained in the Security File.

l 7.5 Local Law Enforcement Authorities Not applicable with no SNM at fixed Site.

8.0 MATERIAL TRANSPORTATION RE0VIREMENTS Not applicable with no SNM at Fixed Site.

9.0 RECEIVER REQUIREMENTS TRANSPORTATION Not applicable with no SNM at Fixed Site.

10.0 IN-TRANSIT PHYSICAL PROTECTION REQUIREMENTS Not applicable with no SNM at Fixed Site.

11.0 EXPORT REQUIREMENTS Not applicable with no SNM at Fixed Site.

12.0 IMPORT REQUIREMENTS Not applicable with no SNM at fixed Site. W 0084N 8

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