ML19309A530

Forwards PSAR

ML19309A530
Person / Time
Site:	05000124
Issue date:	03/19/1980
From:	Parkinson T VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB
To:	Ramos S Office of Nuclear Reactor Regulation
Shared Package
ML19309A531	List: ML19309A530 ML19309A538
References
NUDOCS 8003310406
Download: ML19309A530 (1)

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( ) VIRGINIA POLYTECHNIC INSTITUTE AND STATE UNIVERSITY

'Blacksburg, l'irginia 24061 NucuAR dCUVADON AN M.YMS LABORMORY March 19, 1980

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Mr. Steve Ramos Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Ramos:

Enclosed are two copies of the Preliminary Safety Analysis Report for the VPI & SU reactor (License R-62). This document was prepared for opera-tion at a maximum power level of 500 kw. The PSAR has been reviewed and approved by both the Reactor Safety Committee and the Radiation Safety Com-mittee.

We would appreciate your reviewing the PSAR at your earliest convenience

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so that we can proceed with all the required construction work. Our tenta-

! tive schedule for construction is as follows:

April 1, 1980: Start installation of cooling tower May 1, 1980 : Start installation of new heat exchanger June 1, 1980 : Start modification of primary coolant system Enclosed also are two pre'iminary copies of our Emergency Plan which has also been reviewed by the Reactor Safety Committee and the Radiatior. Safety Committee.

Thanks for your cooperation.

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Sincerely yours,

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T. F. Parkinson, Director Nuclear Reactor Laboratory TFP/fbl cc: A. P. Curtner, Reactor Supervisor g R. H. Miller, Chairman, Reactor Safety Committee #y R. A. Teekell, Chairman, Radiation Safety Committee Y

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VIRGIN 1A TECH REACTOR FACILITY EMERGENCY ?IAN SEPTEMBER 1979 DNAFT l

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VIRGINIA TECH REACTOR FACILITY EMERGENCY PLAN SEPTEMBER 1979 TABLE OF CONTENTS Section Title Pg 1 PURPOSE OF EMERGENCY PLAN 1 2 DEFINITIONS 1 3 EMERGENCY ORGANIZATIONS 3 4 EMERGENCY RESPONSE ACTIONS 5 5 ADMINISTRATIVE CONTROLS 8

• Virginia Tech is the official name of Virginia Polytechnic Institute and State University (Legal Name)

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I. PURPOSE OF EMERGENCY PLAN This document outlines the plan for responding to potential emergencies at Virginia Tech's Reactor Facility to minimize their effect on personnel, the Reactor Facility, and the environment.

To accomplish this goal, the emergency plan defines the emergency organi-zation and general actions to be taken in response to hypothesized emergencies of varying levels of severity. Specific actions to be taken to implement this

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plan in the case of actual emergencies are defined in the VA Tech Nuclear Research Reactors Procedures Manual.

II. DEFINITIONS A. Reactor Room. The room containing the 100 KW Argonaut reactor (Room 10, Robeson Hall).

B. Reactor Facility. The rooms 106, 108, 6, 8, and 10 of Robeson Hall contain work areas, laboratories, offices and the Reactor Control Room and Reactor Room.

C. Reactor Facility Restricted Area. The Reactor Facility and the roof area of Robeson Hall.

D. Affected Area. The area beyond the Reactor Facility restricted area in which the limits for radioactive materials or radiation exposure to individuals are likely to exceed those specified for unrestricted areas by 10 CFR Part 20.

E. Emergency Action Classes. The emergency action classes are methods used to define the relative severity of the emergency condition. The actions necessary to assess, correct and recover from emergencies are based on its severity as defined by these classes.

The Emergency Action Classes are:

Class 1 - Personnel Emergency. A personnel emergency is an acci-dent occurring within the Reactor Facility Restricted Area which requires the emergency treatment of one or more individuals.

These occurrences may be complicated by radioactive contamina-tion or radiation exposure.

This class of emergency does not necessarily have an effect on the reactor and immediate operator action to alter the reactor status is not required unless it is likely that the Class 1 emergency will escalate to a more severe (Class 3 or Class 4) 1 emergency.

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Class 2 - Energency Alert. An emergency alert results from situa-tions which can be recognized ds creating a hazard to the reactor or personnel that is not normally present. Examples of this class i

of occurrence are:

a. Threats to or actual breaches of security, civil disturbances or bomb threats affecting the Reactor Facility.

b. Instrumer.t readings or alarms indicating atypical reactor operating condition which does not require immediate shut down of the reactor as defined by the R-62 Technical Speci-

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c. Severe natural phenomena, such as a tornado alert.

While time is available in these situations to prevent or minimize the effect of these occurrences, emergency alert conditions imply a rapid transition to the state of readiness by reactor personnel and the possible changes in normal reactor or facility operation.

Class 3 - Reactor Emergency. Situations which directly affect reactor safety and require immediate corrective action, but are predicted to have negligible radiological consequences outside of the Reactor Facility. Examples of these situations include:

a. Fires or minor explosions in or near the reactor room.

b. Malfunction of a reactor safety system component while the  !

reactor is operating.

c. Sudden or unexpected changes in reactivity, such as a large 4

increase in reactor power with no control rod movement.

Class 4 - Reactor Facility Emergency. Situations which directly l affect reactor safety and indicate that levels of radioactivity '

which exceed the limits specified in 10 CFR Part 20 for unrestricted areas may be released outside of the Reactor Facility restricted area. Framples of these situations are:

a. Measurement of radioactivity dose rates greater than two milli- l rem per hour at the Reactor Facility Restricted Area boundary )

using a portable gamma radiation monitor. l

b. Stack release containing radioisotopes which exceed the concen-i trations allowed for air in an unrestricted area by 10 CFR 20. l

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3 III. EMERGENCY OT Q g ION AND EQUIPMENT A. On-Site Emergency Organization. The on-site emergency organization shall consist of the following persons, listed in order of their position in the chain of conmand in the event of an emergency.

1. Director of the Reactor Facility

2. Deputy Director of the Reactor Facility

3. Reactor Supervisor

4. Reactor Radiation Safety Officer

5. Senior Reactor Operators

6. Licensed Reactor Operators at the Facility The Director of the Reactor Facility shall take charge of all opera-tions and coordinate efforts to assess the severity of an emergency and determine corrective and protective actions to minimize the effects of the emergency.

The Reactor Radiation Safety Officer shall ensure that the emergency equipment is available for use during an emergency, determine whether any radioactivity has been released during the emergency, and recommend to the Director actions to minimize the effect of the emergency.

Other members of the on-site emergency organization shall assist in minimizing the effect cf the emergency as requested by the Director or defined in specific procedures. All reactor operators are qualified in the use of radiation detection equipment.

B. Off-site Emergency Organizations. The following organizations will respond to an emergency at the Reactor Facility if needed:

1. The Montgomery County Hospital has agreed to accept and treat per-sonnel injured at the Reactor Facility. Actions to be taken are identified in a Radiation Emergency Plan which was prepared by the Medical Center. The hospital can be contacted by telephone and two-way radio through the University's Security Division.

2. The Virginia Tech Security Division has agreed to respond to emer-gencies at the Reactor Facility. Actions to be taken are identi-fled in the department. The University's Security Division can be contacted by telephone.

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3. The Blacksburg Volunteer Rescue Squad has agreed to provide on-site medical aid and transport injured personnel to Montgomery County Hospital. The Rescue Squad can be contacted by telephone.

4. The Blacksburg Volunteer Fire Department will respond to emergen-cies at the Reactor Facility. The Fire Department can be contacted by telephone.

5. The Blacksburg Town Police Department will respond to emergencies at the Reactor Facility. The Police Department can'be contacted by telephone.

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6. The Montgomery County Sherriff's Department and Virginia State Police can also be contacted if additional police assistance is needed. The organizations can be contacted by telephone.

7. The Virginia Office of Emergency Services and Oak Ridge Region Coordinating Office for Radiological Emergency Assistance can also assist in the event of a Reactor Facility Emergency. These offices j can be contacted by telephone. l 1

C. Emergency Equipment. Equipment which can be used in the event of an ,

emergency is available at the Reactor Facility and other sites as follows:

1. Reactor Facility

a. Fixed radiation monitors as required by Virginia Tech's R-62 Technical Specifications.

b. Portable radiation monitors for detecting neutron, gamma and charged particle radiation.

c. Multichannel analyzers for determining specific radioactive isotopes present and absolute level of radioactivity.

d. Assorted anti-contamination clothing.

e. Emergency first aid equipment.

f. Portable fire extinguishers.

g. Telephones.

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2. Rescue Squad Ambulance

a. Emergency first aid equipment.

b. Basic life support systems.

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, 3. Health Physics Laboratory, 100 W Randolph Hall (located about 500 feet northeast of the Reactor Facility).

a. Portable radiation monitors.

b. Multichannel analyzer.

c. Fixed gm counters and NaI counters.

4. Montgomery County Hospital (located about 4 miles from the Reactor Facility).

a. Complete medical' facilities.

b. Portable radiation monitor.

5. Security Divisions Office, Building 201, (located about 1000 ft.

from the Reactor Facility).

a. Portable radiation monitors and dosimeters.

b. Anti-c clothing, signs, barrier material, etc.

IV. EMERGENCY RESPONSE ACTIONS A. Class 1 - Personnel Emergency. Immediate action will be taken to determine the number of people injured, the nature and severity of the injury, provide medical aid, and determine whether the accident has any potential for affecting operation or safety of the reactor.

The person first aware of a personnel injury should immediately con-

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tact the Reactor Supervisor or Facility Director using the Facility's internal communications system or ther method. The Reactor Supervi-sor or Facility Director will notify the Reactor Radiation Safety Officer and Rescue Squad. If necessary, emergency first aid will be administered pending arrival of the Rescue Squad. The level, if any, of radioactive contamination will be measured by the Reactor Radiation Safety Officer or other person qualified in radiation detection.

Actions to be taken in the event of a personnel emergency are defined in Virginia Tech's " Emergency / Abnormal Nuclear Reactor Procedures, Section V.".

B. Class 2 - Emergency Alert. Immediate action will be taken to deter-mine the nature and possible consequences of the potential emergency.

Based on this information, corrective action necessary to minimize the l

. adverse effects of the situation will be defined.

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To accomplish this objective, anyone aware of a situation which may I affect the reactor safety or safety of personnel at the Reactor Faci- i lity will notify the Facility Director and Reactor Supervisor. The l Director will determine response actions, such as securing the reactor and monitoring for radioactive effluents, based on the available in-formation and consultation with members of the emergency team as con-sidered necessary.

While the broad spectrum of emergency alerts precludes definition of specific actions in all cases, procedures for several possible situa-tions which may affect reactor or personal safety are contained in

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Virginia Tech's Nuclear Reactor ProceduresSection V. , " Emergency /

Abnormal Procedures." The Reactor Facility Security Plan and Contin-gancy Plan also includes procedures for possible alert conditions.

C. Class 3 - Reactor Emergency. Immediate action will be taken to shut down the reactor.

After the reactor is shut down the reactor operator will notify the Reactor Supervisor or Facility Director who will notify other members of the on-site emergency' organization if necessary.

In the event that an evacuation is necessary, the criteria for re- I entering the Reactor Facility are defined in Section E, below.

Specific procedures to follow in the event of a Reactor Emergency are included in Virginia Tech's Nuclear Reactor's Procedures,Section V., " Emergency / Abnormal Procedures."

D. Class 4 - Reactor Facility Emergency. Action will be taken to deter-aine the source, magnitude and affected area by the release of radio-active material. Personnel within the affected area will be informed that radioactive material has been released and protective ac'tions defined. Access to the affected area will be controlled by the Security Division. If the source of the radioactive release is the reactor, it will be shut down and the building evacuated.

The on-site emergency organization, the Radiation Safety Office, and the University's Security Division will be notified in the event of a Reactor Facility Emergency. Members of the Radiation Safety Office, or other qualified personnel will make radiation measurements to deter-mine the extent and level of airborne and other radioactive releases and to determine when the levels of radioactivity released have decrea-sed to acceptable levels.

The University's Security Division shall notify all personnel within the area where radioactivity levles in excess of two millirem per hour exist or areas where other limits for unrestricted areas are likely to l be exceeded. In the event of a major release which precludes timely I l

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determination of the affected area, personnel within 500 feet of the

l. Reactor Facility in the downwind sector (one sector covers 22.5 ]

degrees) and the two adjacent sectors will be notified. l l

The most likely protective action to be taken will be to inform personnel to remain inside with all windows and doors closed and ventilation systems turned off. The need to evacuate specific areas will be evaluated. Access to the affected area will be controlled by the University's Security Division.

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Criteria for re-entering the Reactor Facility are defined in Section E below. Specific procedures to follow in the event cf a Reactor Faci-lity Emergency are provided in Virginia Tech's Nuclear Reactor's Pro-cedures,Section V., " Emergency / Abnormal Procedures."

E. Criteria for Re-entering the Reactor Facility. Following a reactor emergency or Reactor Facility emergency in which an evacuation is necessary, the Reactor Radiation Safety Officer and the Reactor Super-visor shall re-enter the building as described in Virginia Tech's Nuclear Reactor's procedures. Once a determination of the actual i radiation levles has been made, areas of the building having radiation levels below the limits established for unrestricted areas by 10 CFR 20 may be entered and used.

Entry into areas having high radiation levels for the purpose of radiation surveys, clean-up or other actions not judged to be neces-sary to the safety of the reactor or personnel should be planned and performed to limit the total dose to the whole body of any person to less than one rem. Both a TLD and a pocket dosimeter should be used to record the actual exposure.

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F. Methods Used to Account for Personnel. Following evacuation of the facility, it is important to account for all personnel. This will be accomplished by the following methods:

1. Discussions with personnel who have evacuated the Facility to con-firm that all personnel in the Facility prior to the evacuation are accounted for.

2. Check the TLD racks to determine that all TLD badges are either on the rack or on evacuated personnel. Personnel will be instructed to keep their TLDs during the evacuation instead of placing them on the, storage racks. Personnel in the Reactor Facility will either have TLD badges or be escorted (visitors only). Since the TLD badge storage rack is near the Reactor Facility exit, the radiation level should be low enough to allow determination of which TLD badges are stored on the rack following facility evacuation.

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3. During the initial re-entry to determine radiation levels, a visual check of all accessible areas .will be made to detect personnel within the facility.

G. Emergency Control Center. A central location for directing the emer- I gency actions will be established. The Facility Director win normally 4 be at the control center, unless it is necessary to be another location I to provide better control of the emergency actions. The emergency con- l trol center shan be established as follows:

1. Personnel emergency. As near to the accident location as possible while ensuring that acceptable radiation levels and adequate com- I munications are present. j l

2. Emergency alert and reactor emergencies in the Reactor Control Room. If evacuation is necessary, proceed to item G, 3. 1 i

3. Reactor Facility emergency. At a location having acceptable radia- l tion levels as determined by the Reactor Radiation Safety Officer, '

or other authorized person, and'having adequate communications. l

• l V. ADMINISTRATIVE CONTROLS The foll.owing administrative controls will be used to ensure that the Emergency Plan and Procedures are useable in the event of an emergency.

A. A summary of emergency actions will be posted in the Reactor Facility and another copy in one of the emergency kits stored at Security. The purpose of this summary is to provide an up-to-date listing and phone i numbers of key personnel on the emergency organization and off-site l

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personnel and organizations who would participate in a reactor or I Reactor Facility emergency.

B. The Emergency Plan and Procedures for implementation of the plan will I be reviewed and, if necessary, updated by the Reactor Safety Sub-Commit-tee during even numbered years. Changes considered necessary based on the results of drills or other experience will be made as soon as practical.

C. Practica emergency drills will be undertaken at leace once each calendar year to test the response of the on-site emergency organization. The Facility Director will be responsible for defining the objective and details of each drill. Following the drill the on-site emergency

, organization will meet to critique the drill and determine whether changes to the procedures or additional personnel training are warranted.

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