ML20135D952

Forwards Revised Reed Reactor Facility Emergency Plan, Per NRC Request.App a Containing Agreement Ltrs & App B Containing Implementation Procedures Will Be Forthcoming by 851015

ML20135D952
Person / Time
Site:	Reed College
Issue date:	09/09/1985
From:	Kay M REED COLLEGE, PORTLAND, OR
To:	Thomas C Office of Nuclear Reactor Regulation
Shared Package
ML20005D539	List: ML20135D952
References
NUDOCS 8509160237
Download: ML20135D952 (1)

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REED C0LLEGE j 'Pordand, Oregon 9po2 REACTOR FACILITY Mr. Cecil O.

Thomas, Chief Standardization and Special Projects Branch Division of Licensing, NRR U.

S. Nuclear Regulatory Commission Washington,'D.C.

20555 J

Docket No. 50-288 9 September 1985

Dear Mr. Thomas:

The Reed. Reactor Facility has completed the revisions of the text of the Reed Reactor Facility Emergency Plan requested in your letter..Three copies of the revised plan of 15 September 1985 are enclosed.

Appendix A containing the agreement letters and Appendix B containing a copy of the implementation procedures will be forthcoming by 15 October 1935.

A set of agreement letters was submitted to the Offsite Support Organizations on 21 August, and not all i

replies have been received.

If there are any further questions, please contact me at (503) 771-1112 ext 205.

I will be attending the National Emergency Training Center course on accident assessment in Emmitsburg through 13 September, but after that I will be back at my office.

Sincerely, M

MichaelvA. Kay, Sc.D.

Director, Reed Reactor Facility cc:

Dr. M. Cronyn, Provost h

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SAFETY RELATED DOCUMENT Reed Reactor Facility Emergency Plan Docket 50 - 288 License R - 112 15 September 1985 Reed Reactor Fac111ty 3203 S.E. Woodstock Boulevard Portland, Oregon 97202 (503) 771-1112 or (503) 777-8008 The Reed Institute dba Reed CoIIege 3203 S.E. Woodstock Boulevard Portland, Oregon 97202 (503) 771-1112 8509160240 850909 I

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s RRF EMERGENCY PLAN

1.0 INTRODUCTION

1.1 Anolication This emergency plan applies to The Reed institute ea Reed College Reed Reactor Facility (RRF). The RRF is licensed pureuant to Title 10 Code of Federal Regulations, Chapter 1. Part 50, as a Research and Utilization Reactor, Facility Operating License No. R-112 (Docket No. 50-288). This plan specifies the objectives and implementing procedures to be followed for emergency situations occurring at RRF.

1.2 Objective The objective of the RRF Emergency Plan is to establish guidelines and designate areas of responsibility for the RRF staff should an i

emergency occur at RRF that might affect the public health and safety.

The RRF Emergency Plan identifies the Offsite Support Organizations that may be activated if required.

1.3 Site Descriotion The RRF is located on the Reed College Campus in the city of Portiend, Multnomah County, Oregon. The 90-acre canpus property, owned l

by The Reed institute, is in the southeastern section of Portland known as Eastmoreland. The location of the College campus relative to the city of l

Portland and some of the neighboring communttles is shown in Figure 1.

Detailed access to RRF is shown in the map of the Reed College Campus -

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RRf is entirely contained within the reactor building.

The reactor bay and control room comprise the restricted area.

1.4 Reed Reactor Facility Description The RRF reactor is a General Atomics TRIGA Mark I reactor licensed to operate at a maximum power level of 250 kilowatt thermal (250 KWth).

The RRF reactor can be operated using either aluminum-clad or stainless-steel-clad standard TRIGA fuel elements enriched to a nominal concentration of 205 Uranium-235. The reactor core support structure is permanently mounted at the bottom of a 25-foot " swimming pool" tank. The pool structure is located below grade in the reactor bay.

The RRF consists of the reactor bay, mechanical room, control room, ventilation loft, and exit corridor. The reactor building is attached to the southeast corner of the Chemistry Building.

There is access to the radiochemistry laboratory and counting rooms from the exit corridor. Figure 3 is a floor l

plan of RRF.

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1.5 Reactor Utilization and Operatino Freauencv l

t The RRF provides services and facilities for nuclear science

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education and research by the members of the Nuclear Science Consortium i

of the Willamette Valley. The RRF also provides services to industrial and consulting clients and government agencies.

The RRF operates on an intermittent schedule averaging 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week for an average annual output of 50 MWH (2.2MW Days).

l 2.0 Definitions EMERGENCY.

An emergency is a condition which calls for

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immediate action, tayond the scope of standard operating procedures, to l

avoid an accident L' to mitigate the consequences of one.

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EMERGENCY ACTION LEVELS.

Specific instrument readings, or observations; radiological dose or dose rates; or specific contamination levels of airborne, waterborne, or surface-deposited radioactive meterials j

that may be used as thresholds for establishing emergency classes and l

initiating appropriate emergency measures.

l EMERGENCY CLASSES.

Emergency classes are classes of accidents grouped by severity level for which predetermined emergency actions should be taken or considered.

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EMERGENCY PLAN.

An emergency plan is a document that i

provides the basis for actions to cope with an emergency. It outlines the objectives to be met by the emergency procedures and defines the

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authority and responsibilities to achieve such objectives.

EMERGENCY PLANNING ZONE (EPZ).

Area for which offsite h

emergency planning is performed to assure that prompt and effective H

actions can be taken to protect the pub 11C in the event of an accident.

The EPZ size depends on the distance beyond the site boundary at which the Protective Action Guide (PAG) could be exceeded.

EMERGENCY PROCEDURES. Emergency procedures are documented Instructions that detail the inclementation actions and methods required to achieve the objectives of the emergency plan.

HEALTH PHYSICS PERSONNEL.

In the context of the Emergency Plan: the Reactor Health Physicist, RRF personnel performing radiological sssessment under the direction of the Reactor Health Physicist, and any Offsite Support Organization personnel activated to perform radiological assessment.

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OFFSITE.

The geographical area that is beyond the site boundary.

tl ONSITE.

The geographical area that is within the site l

boundary.

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OPERATIONS BOUNDARY. The area within the site boundary as

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shown in the RRF floor plan (Figure 4) is the operations boundary.

When door 'A' is closed, it consists of the area outlined in black. When door 'A' f

is open, it includes the area outlined in hatched lines.

Within the operations boundary the Reactor Director has direct authority over all i

activities.

The area within this boundary shall have pig r6nged evacuation procedures known to personnel frequenting the area.

PROTECTIVE ACTION GUIDES (PAG).

Projected radiological dose or dose commitment values to individuals that warrant protective actions would be warranted provided the reduction in individual dose expected to be achieved by carrying out the protection action is not offset by excessive risks to individual safety in taking the protective action.

The j

projected dose does not include the dose that has unavoidably occurred i

j prior to the assessment.

RESEARCH REACTOR.

A device designed to support a self-f sustaining neutron chain reaction for research, developmental, educational, I

training, or experimental purposes, and which may have provisions for j

production of nonfissile radioisotopes.

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RRF MANAGEMENT.

The President, Ylce President-Treasurer, and Vice President-Provost of Reed College.

The Director of RRF is the highest level of operational management, and the reactor supervisor is a student Senior Reactor Operator.

l SITE BOUNDARY.

The site boundary is that boundary, not necessarily having restrictive barriers, including the adjoining Chemistry j

Building and extending 250 feet in every direction from the operations i

boundary. Within this area the Emergency Coordinator may directly initiate emergency activittee. The area within the site boundary may be frequented by persons unacquainted with reactor operations.

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SHALL, SHOULD AND MAY. The work *shall' is used to denote a requirementi the word "should* to denote a recommendationi and the work l

• may* to denote permission, neither a requirement nor a recommendation.

l 3.0 Organization and Responsibilities l

l The RRF staff as established by the Director is involved with routine reactor operations, technical support and administration activities, i

and through training and operating experience is capable of handling any j

foreseeable emergency at the RRF.

The Director's Position is the only salaried position at RRF, all other positions are staffed by student licensed j

operatura, off-canpus licensed operators, or professionals in appropriate i

fields auch as Health Physics.

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• 3.1 Emeroency Oroanization i

Several offsite organizations are available to augment the RRF emergency organization for emergency event response. The assistance and support services provided by these organizations include fire fighting, ambulance and emergency medical services, hospital facilities, and police l

protection.

Written agreements with these organizations are renewed biennually (in odd-nuireered years) and are included in Appendix A to this plan. The RRF staff with augmentation from offsite agencies forms the RRF emergency organization.

Figure 5 shows the interface between the elements of the emergency organization.

3.1.1 Emeroency Notification Call List (ENCL)

The Director shall establish the Emergency Notification Call List (ENCL) and determine the personnel order.

There shall be a minimum of five (5) Ilcensed operators on the ENCL which shall include the following: Director, Reactor Supervisor, and Health Physicist.

3.1.2 Emeroency Coordinator Any Reactor Operator (RO) or Senior Reactor Operator (SRO) may initiate emergency action.

The SRO on duty shall be the Emergency Coordinator.

At that time the Emergency Coordinator has ultimate authority over on-site activities and personnel.

The Emergency Coordinator is responsible for:

(1) placing RRF in a safe shutdown condition, (2) terminating or minimizing releases of redlooctive meterials, (3) protecting RRF personnel and visitors, j

(4) assessing severity of the emergency event, and i

(5) notifying the first available person on the ENCL.

To fulfill these responsibilities the Emergency Coordinator shall exercise Judgment and summon medical, ambulance, fire, and police assistance as necessary. If the SRO on duty cannot respond, the Director's office shall be notified, and the Director shell assume the role of Emergency Coordinator. If the Director is not available, then the first available SRO i

shall assume the duties of Emergency coordinator. If an SRO is not able to i

respond, an RO shall assume the duties of the Energency Coordinator and i

immediately ask for assistance.

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BRF Manaaement Reed College President Vice President-Treasurer Vice President-Provost RRF

' Emergency Reed Reactor Coordinator Information Safety (Director or Services Committee Alternate)

Reed Reed Safety and Physical Security Emergency Plant Notfication Personnel Call List Personnel l

I Offsite RRF Offsite Support Operations Support Oroanizations Staf1 and f

(SRO's & RO's)

Regulatory Fire Acencies

. Police Ambulance State of Hospital Oregon Radiation Control Section Oregon DOE Nuclear Insurers of America U.S. Nuclear Regulatory Commission Figure 5 - RRF Emergency Organization

9 The Emergency Coordinator shall direct all emergency actions until relieved by a member of the ENCL.

The ENCL la based upon fast response; it is ordered in usual distance from RRF. The Organizational Hierarchy of RRF personnel shall be:

Director Health Physicist Reactor Supervisor Previous Director Senior Reactor Operator (s) l An Emergency Coordinator on this list shall surrender the position to a l

person higher on the Organizational Hierarchy list.

3.1.3 Reactor Supervisor i

The Reactor Supervisor shall be responsible for reviewing and updating emergency plans and procedures.

The Reactor Supervisor is also responsible for emergency training and for conducting emergency drills and reporting critiques to the Director and Reactor Safety Committee. The Reactor Supervisor shall be a licensed Senior Reactor Operator.

3.1.4 RRF Manaaement The RRF Management consists of the President, Vice President-Treasurer, and Vice President-Provost of Reed College. The Director is the highest level of operational monogement, and a student SRO is Reactor Supervisor.

The Director (or highest person on the RRF Organizational Hierarchy in the absence of the Director) will assume responsibility, as Emergency Coordinator, for directing emergency control measures for any incident posing s radiological threat to the health and safety of individuals or the public. The Director will provide news releases when worrented to the Reed College Information Services Office which in turn controls all official news releases.

3.1.5 RRF Health Physics j

The Director serves as the onsite Health Physicist during non-emergency periods.

The Reactor Health Physicist will be i

available during emergencies es needed.

Additional Health Physics i

expertlee and support are avallable from State of Oregon Offsite Support I

IJnits as necessary.

RRF personnel will provide support as requested by the Reactor Health Physicist.

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3.1.6 Facility SuDDort

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r Individuals on the RRF staff may be assigned duties and responsibilities during the course of an emergency event.

All RRF personnel receive basic instruction in radiation safety and emergency l

procedures on an annual basis.

j 3.1.7 RRF Reactor Safety Committee The Reactor Safety Committee is the Review, Audit, and

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Approval organization for RRF. It is composed of two subcommittees with expertise in Safety and Operations respectively.

It provides a source of l

expertise available to RRF during emergencies.

It will review and audit i

emergency preparedness under this plan.

3.1.8 Communications Reed College maintains 24-hour telephone communications.

RRF has a direct dial-in line through the college switchboard (503-777-7222), and a special phone separate from the college j

switchbooi d (503-777-8008).

The special phone is operational any time the Pacific Northwest Bell system is operating and the lines are intact.

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The college electronic switching system is 110 Volt A.C. dependent as well j

and does not function as reactor emergency communications during a power i

j outage.

There is an extension of 503-777-8008 in the Director's Office l

which serves as the Emergency Support Center (ECS).

Reed Security patrols are in radio contact with this base, and have the capability of I

handling phone communications on their radio equipment.

During periods when RRF is unattended, Reed Security patrols RRF, and notice of any alarm condition is cormiunicated to the first available person on the ENCL l

3.1.9 Reed Colleoe Information Services Office The Reed College information Services Office, 212 Eliot Hall, will handle all official news releases concerning emergency events at j

RRF.

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3.1.10 Reed. Security Reed Security personnel may be called to provide RRF i

accurity assistance, emergency radio communications, and traffic control i

as necessary. Reed Security personnel are trained annually in their role in l

RRF emergency procedures, j

3.1.11 Reed Physical Plant Personnel f

Reed Physical Plant Personnel may be called to provide i

assistance with electrical, plumbing, or structural problems encountered

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during an emergency.

i 3.1.12 Portland Fire Bureau f

The City of Portland Fire Bureau will serve as the primary firefighting agency. The firemen are trained annually in their role in RRF emergency procedures.

3.1.13 Portland Ambulance Service h

The City of Portland operates a coordinated Emergency l

Dispr,tching System through the 911-all emergency number, and will provide emrtgency medical assistance and ambulance service for RRF as required.

Because of the presence of a major nuclear generating plant near Portland, the emergency medical technicians have been trained to handle contaminated personnel.

f 3.1.14 Good Samaritan Hosoltal Good Samaritan Hcapital will provide medical facilities and care for contaminated injured Individuals and for individuals suffering from acute radiation exposure.

Good Someritan Hospital is the primary receiving hospital for contaminated injured personnel from a mejor nuclear generating station. Full-scale exercises are held at frequent intervals to train and requalify personnel in the radiological emergency unit.

Good Samaritan Hospital has 50% of its emergency facilities cormletely isolable to handle such emergencies. Good Samaritan Hospital produces videotapes and other meterials as training aids for medical personnel involved in response to radiological accidents and injuries.

3.1.1S Offsite Law Enforcement Aoencies F

The Portland Police Bureau is the primary offsite agency f

for facility security assistance, emergency radio communications, traffic t

control, and riot control as necessary.

PP8 officers and personnel are trained annually in Emergency Response to RRF alarms. The PPB is notified in all cases involving RRF security, and any other requests for assistance may be mode by the ENCL person acting as Emergency Coordinator or by Reed Security.

Additional offsite assistance is available from the Multnomeh County Sheriff's Office and the Oregon State Police as requested by the Portland Police Bureeu.

3.2

c. --aretion with and Notification of Government. Aaancias The postulated credible accidents associated with the operation of RRF's Triga Mark l Nuclear Reactor will not result in a f

radiological hazard affecting the public heelth and safety.

These emergency events will not require the direct involvement of local, state, and federal agencies.

i 3.2.1 U.S. Nuclear Reoulatory Commission Notification of an incident to the U.S. Nuclear Regulatory Commission tshall be in accordance with the requirements of 10 CFR 20 and other applicable regulations. Additionally, RRF will transmit to the NRC all information specified in the Technical Specifications to Reactor License R-112. Notification of the NRC shall be en RRF Management responsibility, if the Director is not available, an Emergency Coordinator who is also a member of the ENCL shall assume this responsibility and notify the Vice President-Provost of this action.

3.2.2 State of Oreoon Deoartment of Enerov (ODOE) and State of Oreoon Department of Health Radiation Control Sections Notification c.~ an incident to the ODOE, Salem, Oregon, and the Radiation Control Section, Portland, Oregon, shall be in accordance with the regulations specified in Oregon Regulations for the Control of Radiation and other applicable State Regulations. Notification of the 000E and Radiation Control Section shall be an RRF management responsibility. If the Director is not available, an Emergency Coordinator who is also a i

menber of the ENCL shall assume this responsibility and notify the Vice President-Provost of this action.

3.2.3 Local Government Aoencies The City of Portland and Multnomah County shall be notified of any incidents which may have caused or threaten to cause an uncontrolled release of radioactive meterials that results in a projected offsite dose of 1 Rem whole body or 5 Rem thyroid.

Notification of local government agencies shall be an RRF Management responsitillity.

If the Director is not available, an Emergency Coordinator who is tino a member of the ENCL shall assume this responsibility and notify the Vice President-Provost of this action.

3.2.4 American Nuclear Insurers (ANI)

ANI shall be notified as soon as presible after declaration of a nuclear Alert. Site Area Emeroencv. or fagog 'al Emeroency as required by their contract.

Notification of ANI shall be an RRF Management rasponsibility. If the Director is not available,.m Emergency Coordinator who is also a menber of the ENCL ahall assume this i

roeponsiblitty and notify the Vice President-Provost of this action.

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I 3.3 Termination of an Emeroency The Emergency Coordinator who is a member of the ENCL shall j

be responsible for the termination of an emergency.

Prior to termination of an emergency the Emergency Coordinator shall conclude that there exist

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no foreseeable subsequent events that could cause damage to the reactor or render its operation unsafe.

He shall verify that all areas to be reopened to personnel or the general public meet the requirements of 10 CFR 20 for occupancy. He shall also confirm that areas restricted to entry or that require controlled access are clearly posted.

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t' 3.4 Authorization for Reentrv I

The Emergency Coordinator who is a member of the ENCL shall authorize any reentry into the reactor building or portions thereof previously evacuated during the course of an emergency.

It shall be the responsibility of the Health Physicist to establish reentry requirements, provide personnel monitoring, and insure that protective clothing and proper respiratory protection is utilized when required.

3.5 Authorization of Radiation Expaatres in Excess of 10 CFR 20 Limits An Emergency Coordir.ator who is also a member of the ENCL with the concurrence of the Health Physicist, or a quellfled alternate, may authorize exposures to emergency team mer2ers and radiation workers in l

excess of normel occupational limits as specified in 10 CFR 20.

The l

exposure limits are 100 Rem whole body for life saving and 25 Rem whole body for corrective action that mitigates the consequences or reduces the severity of the emergency event.

In either case, the exposure is i

authorized on a once-in-a-lifetime basis with preference given to the i

eldest able-bodied volunteers.

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4.0 Emoroency Classification System l

The emergency classes described for the RRF are based upon credible accidents associated with reactor operations and other emergency l

situations that are nort-reactor-related and have less severe radiological l

l consequences than the least severe claims.

An Emergency Classification Guide is presented in Table 1.

lenplementing Procedures for the emergency

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classes of credible accidents are listed in Appendix B.

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4.1 Non-Reactor Safety Related Events i

i These events are separate from riector operations and do not necessarily indicate changing of the reactor status.

Advisories to Reed

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Security or Portland Police may be warranted, and conditions may require auch local services as areulance and medical.

There may be a nood to shut down the reactor to reallocate personnel or because of injuries to a key individual.

TABLE I Emergency Classification Guide Emergency Class Action Level Purpose Non-Reactor Civil disturbances or Alert staff to a possible Safety Related receipt of bomb threat escalation Event non-specific to reactor Personnel injury with initiate Assessment and or without radiolo-Provide Treatment gical complications Minor fire or explosion non-specific to the reactor, its control system, or facility power lines in the Chemistry Building Facility or individual contamination Notification of Receipt of bomb threat Assure that emergency Unusual Event with possible radiolo-personnel are readily gical release implica-available to respond if the tions situation becomes more serious or to perform Pool level alcrm and confirmatory radiation visual observalton monitoring if required.

l Indicating abnormal l

loss of water or abnormal increase in water level.

Fire or explosion in Provide offsite authorities basemon+ of Chemistry current status information l

Butiding (radiochemistry laboratory, counting rooms, pneumatic tube terminal, or reactor storeroom), reactor boy, or control room.

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l TABLE I (continued)

Esseency Class Action Level Purpose Notification of Major fire, explosion, or Unusual Event any event requiring (continued) evacuation of any part l

of the Chemistry Building Radiological effluents at the site boundary I

exceeding 10 MPC when I

averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or I

15 mrem whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t Failure of an experiment or fuel cladding as indicated by alarms on one or more of the facility monitors:

Air Particulate Monitor Continuous Air Monitor Gessous Stack Monitor Radiation Aree Monitor Alert Radiological effluents at the Assure response centers site boundary exceeding are menned 50 MPC when averaged over i

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 75 n1 Rem whole Assure that monitoring I

body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> teams are dispatched Radiation levels at the site Assure onsite evacuation l

boundary of 20 niRem/hr for capability i

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole body or i

100 mrem thyroid dose Provide for consultation in I hour with offsite authorities l

t 1

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P TABLE 1 (continued)

Emergency Class Action Level Purpose j

i Alert Severe fuel damege Provide information for i

(continued) or experiment failure the public through the resulting in significant Reed College Information j

releases of radioactivity Services Office as determined by observing j

the following radiolon levels i

on the facility air monitors l

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Air Particulate Monitor:

100 x alarm level Gaseous Stack Monitor:

100 x alarm level j

Continuous Air Monitor:

l 100 x alarm level i

Radiation Area Monitor:

An alarm lasting I hour from an unexplained source l

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4 The following action levels shall be used to initiate emergency measures associated with this emergency class.

1.

Civil disturbances or receipt of a bomb threat non-specific to the reactor or adjoining chemistry building.

2.

Personnel injury with or without radiological complications.

i 3.

Minor fire or explosion non-specific to the reactor, its control system, or facility power lines in the chemistry building.

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4.

Facility or individual contamination.

4.2 Notification of Unusual Events

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This class of emergency may be initiated by either msnmode events or natural phenomena that can be reco@lzed as creating a j

significant hazard potential that was previously non-existent.

There is usually time available to take precautionary and corrective steps to prevent the escalation of the accident or to mitigate the consequences i

should it occur.

No releases of radioactive meterial requiring offsite responses are expected.

One or more elements of the emergency organization are likely to be activated or notified to increase the state of j

readiness as warranted by the circumstances. Although the situation may not have caused damages to the reactor, it may warrant an immediate l

shutdown of the reactor.

l The following action levels shall be used to initiate emergency l

measures associated with this emergency class:

i 1.

Receipt of a bomb threat with' possible radiological release implication.

2.

Pool level alarm and visual observation indicating abnormal loss of water or abnormal increase in water level.

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3.

Fire or exploelon in the basement of the Chemistry Building (radiochemistry laboratory, counting rooms, pneumatic tube terminal, or reactor storeroom), reactor boy, or control F**

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4.

Major fire, explosion, or any event requiring evacuation of any part of the Chemistry Building.

5.

Radiological effluents at the site boundary exceeding 10 MPC when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 15 niRem whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.

Failure of an experiment or fuel cladding as indicated by alarms on one or more of the facility monitors:

Air Particulate Monitor (APM)

Continuous Air Monitor (CAM)

Gaseous Stack Monitor (GSM)

Radiation Area Monitor (RAM) 4.3 Alert Events leading to an alert would be of such radiological significance as to require notification of the emergency organization and response as appropriate for the specific emergency situation.

During an alert it is unlikely that offsite response or monitoring would be necessary.

However, substantial modification of the reactor operating status is a I

highly probable corrective action with shutdown (as described in the i

Technical Specifications to Reactor License R-112) the goal.

Protective i

evacuations, or isolation of certain areas within the operations or site boundary may be necessary. The following action levels shall be used to initiate emergency measures associated with this emergency class.

1.

Radiological effluents at the site boundary exceeding 50 MPC when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 75 neem whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Radiation levels at the site boundary of 20 neem /hr. for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole body or 100 neem thyroid dose in one hour.

3.

Severe fuel damage or failure of an experiment resulting in significant releases of radiactivity as determined by observing the following radiation levels on the facility air monitors:

i Air Particulate Monitor - 100 x alarm level Geseous Stock Monitor - 100 x alarm level Continuous Air Monitor ~ 100 x alarm level t

i 4.

A Radiation Area Monitor Alarm lasting one hour from en l

unexplained source.

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4.4 Site Area Eine eeiicy No credible accidents attributable to the reactor or its i

operation are postulated which can cause emergency conditions beyond the operations boundary; therefore, this emergency class is not addressed in this plan.

4.5 General Emergency No credible accidents attributable to the reactor or its operation are postulated which can cause emergency conditions beyond the operations boundary; therefore, this emergency class is not addressed in this plan.

5.0 Emeroency Action Levels (EAL's)

There are no postulated credible accidents associated with the operation of the RRF Reactor that lead to exposures exceeding the Protection Action Guides (PAG's) of 1 Rem whole body or 5 Rem Thyroid beyond the site boundary.

The action levels specified in Table I

• Emergency Classification Guide

• and described in Sections 4.1, 4.2, and 4.3 are EAL's for activating the Emergency Organization and initiating protective actions appropriate for the emergency event.

6.0 Emeroency Plannino Zone The operations boundary for the RRF Reactor (defined as the 1

reactor bay or reactor containment area) is established as the Emergency Plarming Zone (EPZ) for the RRF.

Areas within and adjacent to the EPZ l

are large enough to support emergency actions beyond the EPZ if necessary.

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1 7.0 Emeroency Reeponse 7.1 Activation of the RRF Emeroency Oroanization The Emergency Coordinator shall be responsible for initiating the emergency procedures and for notifying and mobilizing the emergency organization.

During periods of time when RRF is unattended and an emergency is detected by Reed Security, appropriate RRF staff wlil be l

contacted as per the Emergency Notification Call List (ENCL) by the Reed l

Operator. There is an operator on duty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day insuring that in the event of an emergency RRF personnel on the ENCL will be notifled.

Additionally, the Offsite Support Organizations are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. Communication during emergency situations may be by telephone, word 3

of mouth, short wave radio, intercom, or public address system, as l

appropriate.

7.2 Protective Action Values Every attempt shall be mude to meintain radiation exposures to emergency personnel within the limits of 10CFR20 and/or the Protective l

Action Guides (PAG's) of 1 Rem whole body or 5 Rem Thyrold. Mc.,; var, an Emergency Coordinator who is also a member of the ENCL with the concurrence of the Reactor Health Physicist or a quellfled alternate may J

authorize exposures in excess of these values to facilitate rescue of 1

injured personnel or take corrective actions which will mitigate the j

consequences of the emergency event.

The exposure limit for life-saving shall be 100 Rem and for corrective actions 25 Rom. In either case, these exposures shall be on a voluntary basis and restricted to a once-in-a-lifetime exposure.

7.3 Health Physics Emergency Response Proaram The Reactor Health Physicist shall be responsible for 1

determining radiation dose rates and contamination levels both onsite and offsite.

The Reector Heelth Physicist may request assistence from RRF personnel and Offsite Support Organizations as necessary to carry out radiological assessment of the accident.

This information will be relayed by face-to-face consnunication, telephone communication, intercom, or short wave radio to the individuel responsible for accident assessment. In l

addition, these individuels shell provide for isolation and supervise access control to restricted areas to minimize personnel exposures and the apread of radioactive contamination.

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7.4 Reporting of Emeroencies Copies of the ENCL are posted in the facility, the Emergency Support Center (ESC), and the Chemistry Secretary's Office.

Telephone nureers are listed for RRF personnel. Copies of this plan with notification l

procedures for all offsite support agencies are located in the control room, emergency grab bag, ESC, and Chemistry Secretary's Office.

Initial and follow-up emergency messages to the MtC and, if appilcable, to other i

offsite government egencies should, to the extent known, include the following:

1.

Nemo, title, and telephone number of caller, and the j

location of the incident.

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2. Description of the emergency event and emergency class.

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3. Date and time of incident initiation.

4.

Type of expected or actual release (alrt>orne, watert>orne, i

surface spill) with estimated duration times.

5.

The quantity of radionuclides reloosed or expected to be released.

i 6.

Projected or actual dose rates outside of the operations boundary.

l 7.5 Emeroency Reanonae for Non-Reactor Safety Related Events 7.5.1 Activation of the Ea eency Oraanization for Non-Reactor Safety Related Events The cor@lete activation of the emergency organization for this Emergency Class would not normally be required.

The Emergency Coordinator shall activate that portion of the Emergency Organization necessary to respond to the emergency event.

In any case, RRF Management shall be notified and kept informed of the emergency status.

7.5.2 4 - =.-it Actions for h *---tor Safety Related D5111 Civil disturt> onces or bonib threats shall be essessed to the Emergency Coordinator for validity and specificity using Portland Police Bureau experience, Reed Security experience, and the information source.

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For personnel injury the Emergency Coordinator shall i

assess the extent of the injury and with Health Physics assistance shall j

determine if radioactive contamination is present.

Portable and fixed radiation monitoring devices are available for this assessment.

In the f

absence of contamination, the assessment shall consider the nature of the f

l Injury, the appropriate first aid, and the need for ambulance transport.

i The Emergency Coordinator shall Insure the suitable l

monitoring of potentially contaminated individuals or facilities. The Health l

Physicist shall be notified in all cases of mejor personnel contamination (a j

i positive survey after washing shall constitute mejor personnel r

contamination), and in the case of any contaminetton incident rendering i

any part of the facility a restricted aree until decontaminated.

7.5.3 Corrective Actions for Non-Reactor Safety Related i

Events In the event of a civil disturbance or receipt of a bomb

)

threat non-specific to RRF, the Portland Police and Reed Security shall be notified.

The Portland Police will initiate the appropriate controls to

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insure the protection of personnel and property in accordorce with their j

Emergency Plan.

In addition the Emergency Coordinator shall notify a j

monter of RRF Management and keep him informed of the emergency status.

l For cases of personnel injury with or without radiological complications, the Emergency Coordinator shall be responsible i

for notifying RRF Management and a member of the ENCL.

In addition, the Emergency Coordinator shall provide medical assistance including a request l

for ambulance transport.-

If the injured individual is contaminated, l

decontamination will be attempted only if it is judged that this will not f

further aggrevate the injuries. The contaminated injured individual shall be i

transported using contamination control and reverse isolation methods to j

the extent possible.

7.5.4 Protective Actions for Nord- - -tor Safety Related Events i

Protective actions at this level of emergency are i

generally distinguishable from corrective actions.

Some cases may l

necessitate the evacuation of the containment ares (reactor bay) in which case persunnel shell assemble in the designated assenbly aree and be vertfled by roll call.

Evacuation shall be initiated by sounding the l

evacuation alarm, and notifying all personnel by way of public address system and word of mouth. Should personnel evacuation be necessary, the l

Emergency Coordinator shell control access to the Facility, and will be j

responsible with health physics support for the segregation of potentially l

r,antaminated personnel.

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7.6 Emeroency Ramaanse for Notification of Unusual Events

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7.6.1 Activation of the E.

ssiicy Oroanization for Notification of Unusual Events The Emergency Coordinator shall activate that portion of i

c the emergency organization necessary to respond to the emergency l

1 situation. In addition, RRF management shall be notified and kept informed of the emergency status.

7.6.2 Amamaament Actions for Notification of unusual Events Minor fuel damage, experiment failure, or any event I

l manifested by unusual radiation or radioactivity levels within the j

1 containment building or the release of effluents at the site boundary shall i

be immediately assessed by the Emergency Coordinator with assistance from the Reactor Health Physicist. Additional support is available from the Offsite Support Organizations.

The assessment will consist of an observation and l

evaluation of facility air and/or radiation monitors in the control room and j

l the use of portable survey instruments.

Excessive levels may require i

evacuation of the RRF and future assessment will be made from the ESC.

Hand and foot monitors and pocket dosimeters can also be used for j

accident assessment.

Collected filter paper and swipe samples can be counted in a laboratory removed from the RRF.

Levels observed on the i

stack air monitors are used to assess release levels at the site boundary.

i Civil disturt>ances and bomb threats shall be assessed by the Emergency l

Coordinator for validity and specificity using Portland Police Bureau and Reed Security experience and the information source.

Pool Level Alarms and visual observation indicating abnormal loss of water or abnormel increase in pool level shall immediately be assessed by the Emergency Coordinator and the source or sink of water identified.

Fire cc explosion in the besement of the Chemistry Building or RRF shall immediately be essessed by the Emergency Coodinator I

and mognitude of the event shall be determined.

Appropriate Offsite I

Support Organizations (Fire, Police, Rescue, Ambulance, Hoolth Physics) shall be summoned.

The Emergency Coordinator shall remain in the designated assembly area to brief Offsite Support Units upon arrival.

Health Physics personnel will monitor as necessary to determine if radioectivity is present.

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Because of the physical location of RRF in relation to the rest of the Chemistry Building, any major fire, explosion, or event requiring evacuation of any part of the Chemistry Building may present a serious threat to the RRF (eg. vapor, water, fire, chemical, electrical).

When RRF is notified of such an event, the senior person on duty shall become the Emergency Coordinator and inwnediately assess the magnitude of the event and the nature of the threat to RRF. The Emergency Coordinator shall initiate appropriate protective actions (eg. shutdown, evacuation, sandbagging) and shall brief responding units. The Emergency Coordinator shall activate that portion of the RRF Emergency Organization necessary to respond to and minimize potential or actual damage to the Facility.

7.6.3 Corrective Actions for Notification of Unusual Events In the event that a Notification of Unusual Event is

]

dictated by assessment of radiological levels, the reactor facility may be evacuated pending an evaluation of the problem and identification of the probable source. The Emergency Coordinator shall confer with the Reactor l

Health Physicist and shall control access to the reactor facility until radiation and airbome activity levels have been restored to normel.

All personnel will be verified present at the designated assembly area and unnecessary personnel will assemble in the training classroom to be available for assistance.

For bomb threats with possible radiological release j

implications, RRF Management, the Portland Police Buroeu, and Reed Security shall be notified. The police will initiate appropriate procedures following l

their Emergency Plan to insure the protection of personnel and property.

The reactor shall be shutdown and all personnel evacuated to the ESC.

t i

in case of prolonged fire or explosion within the i

facility, the Portland Fire Bureau shall be summoned, the first available member of the ENCL and RRF Management shall be notified.

The Reactor 1

i Health Physicist shall be notified of fire in areas where radioactive meterials are located.

In addition, the Emergency Coordinator shall shutdown the reactor and evacuate personnel from the RRF and the basement of the Chemistry Building. Teams will be dispatched to check for Injured personnel.

The Emergency Coordinator will monitor the extent of l

the fire and brief fire bureau personnel upon their arrival.

in case of Pool Level Alarm and visual indication of abnormal loss or gain of pool water, the Emergency Coordinator shall shutdown the reactor, secure the primary and seceridify water systems, and isolate the pool through appropriate value changes.

The Emergency Coordinator shall insure that a preliminary radiation survey is performed and appropriate personnel protective measures instituted (eg. evacuation, r

l radiation area warning, protective clothing required, electrical hazard).

The Reactor Health Physicist, the first available member of the ENCL, and 1

RRF Management shall be notified.

7.6.4 Protective Actions for Notification of IJnusual Events For this emergency class the reactor facility may be l

evacuated and shall be done in aces-derice with facility Emergency Procedures.

All personnel shall be verified present by roll call in the j

designated assen1bly

area, and those individuals who exited the containment building will be surveyed for contamination using portable instruments from the Emergency Grab Bag or the ESC.

Those who are j

contaminated shall be segregated.

The Emergency Coordinator is j

responsible for controlling access to the containment buildingl such access shall be limited to rescue and emergency response operations.

1 Facility air and area radiation monitors shall be used to assess the radiological emergency. In addition to these, other sources of information are available from Offsite Support Organizations.

The Emergency Coordinator with support from Health Physics personnel is responsible for minimizing personnel exposure and spread of contamination.

4 Emergency exposure levels for personnel shall be in accordance with i

Section 7.2.

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7.7 Emeroency Resoonse for an Alert j

l 7.7.1 Activation of the Emeroency Oroanization for an Alert

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The Emergency Coordinator shall activate that portion of l

the emergency organization necessary to respond to the emergency l

l situation. In addition, RRF management shall be notified and kept informed j

l of the emergency status.

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7.7.2 Assessment Action for an Alert Any severe fuel demoge, experiment failure, or event manifested by excessive radiation or radioactWity levels within the reactor facility or the release of effluents at the site boundary shall require immediate evacuation of personnel from the reactor facility and assessment action will be made from the ESC using portable radiation monitors available there. Assessment will be mode by the Reactor Health Physicist-with support from RRF personnel. Additional support is available as needed from Offsite Support Organizations.

Further assessments can be made using portable survey meters, air sar@lers, and personnel dosimetry.

Filter paper and swipe samples can be counted in a laboratory separate from the ESC. Release levels at the site boundary are levels observed on the stack air monitors.

7.7.3 Corrective Actions for an Alert For an alert that l as been dictated by assessment of radiological levels, the reactor fac.lity shall be evacuated following Emergency Procedures pending an evaluation of the problem and identification of the probable source.

The Emergency Coordinator shall control access to the containment bJilding until radiation and airborne activity levels have been restored to normal.

In addition, teams will be dispatched to seal doors to,the facility which are non-essential to access for emergency control.

The Emergency Coordinator shall notify the first available member of the ENCI., the Reactor Health Physicist.

Additional assistance may be summoned from Offsite Support Organizations.

7.7.4 Protective Action for an Alert Protective actions for alert emergencies will be in accordance with Section 7.6.4.

8.0 Emeroency Facilities and Eautoment 8.1 Emeroency Suncort Center (ESC)

[

The RRF Director's Office (RoorT RB Chemistry Building) ahall be the Emergency Support Center for emero% actions. Because of its close proximity to the reactor building tM UC ilows for timely evacuation of i

personnel and emergency actior, TF.g hone and access to radio

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communications are ave 11able in the i.dC.

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8.2 Asset. ament Facilities The RRF has area radiation monitors and facility air monitors l

with readouts and alarm indications in the reactor control room.

in addition, RRF maintains counting laboratories and portable survey l

Instruments in the reactor and laboratory buildings, and if necessary, i

additional counting equipment and survey instruments are available from I

the Reed Radiation Safety Officer (RS0) and Offsite Support Organizations.

A hand and foot monitor is located at the principal exit from the radiochemistry lab. There is also avellable in the laboratory building a j

gamme ray spectrometer for radioisotope identification.

In addition, the j

following alarms and indicators provide non-radiological information in the j

event of an emergency:

e Alarm j

Monitor 1.

High-Low Water Alarm Red light in evacuation corridor and on roof of Chemistry Building, and buzzer in Console Room 2.

Pool Tenperature Alarm Buzzer on console 3)

Isolation cycle indicator Red lights in reactor and Cunsole Roms. Both visible from evacuation corridor.

l 4)

Secondary Water Low High Pitched Howler in Reactor i

Pressure Alarm Bay; audible outside RRF l

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Fire Alarm Pull Station Alarm bells throughout adjacent Chemistry Building i

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6)

Evacuation Alarm Klaxon in Reactor Bay. Red i

light in radiochemistry lab.

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7)

Primary Water Conductivity None l

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I 8.3 first Aid and Medical Facillilea I

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Onsite first aid and medical supplies are located in the l

emergency grab bag located in the evacuation corridor. Additional first aid l

i supplies are available in the cabinets in the corridors of the Chemist"y l

Building.

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Accidents resulting in personal injury without contamination will be handled by administering first aid and summoning on ambulance with paramedics if needed.

In the event of injury with contamination, the l

Individual will be transported to Good Samaritan Hospital, Portland.

Each i

ambulance is staffed with two emergency medical technicians and is capable of transporting contaminated victims. Good Someritan Hospital has i

emergency procedures for this situation.

Written agreement letters with respect to arrangements made l

for hospital, medical, and other emergency services shall be filed and i

attached to this plan as Appendix A.

I

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8.4 Derontamination Facilities Decontamination of personnel at the RRF can normally be i

handled using sinks at the facility. The Reactor Health Physicist shall be l

responsible for decontamination of all individuals involved in any emergency.

8.5 Communications Systems RRF telephones, and the facility intercom system located j

throughout the facility, may be utilized during emergency conditions.

The l

Intercom system links the reactor control room with the bridge and laboratory building. In addition, word of mouth communications will provide a backup for internal communications to

campus, and emergency l

radiotelephone communications.

Also there is a semi-annual update and verification of the emergency notification call list.

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9.0 Recovery Ooerations Restoring RRF to a safe operating condition after an emergency shall be the responsibility of the Emergency Coordinator. In the l

event that recovery procedures are necessary, they shall be written by j

the Emergency Coordinator and reviewed by the Reactor Safety Committee.

f Any operations necessary to restore RRF to operational status shall be under the direction of the Emergency Coordinator.

The Reactor Health j

j Physicist shall survey, direct decontamination operations, and ascertain i

that contamination and radiation levels within the affected area are within l

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appropriate limits. RRF management with the advice of the Reactor Safety Committee shall assess resultant damages, direct repairs, review the j

emergency, and authorize continued operation of the reactor.

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s 10.0 Maintainino Emeroency Preparedness 10.1 Trainino The RRF personnel with emergency response responsibilities shall complete an initial training program and an annual retraining program to include classroom training and practical drills. The training is designed to demonstrate an individual's ability to perform assigned functions such as accident assessment, decistory-making, radiological monitoring, i

contamination control and first aid and rescue of personnel.

In addition, Reed Security, Portland Police Bureau, Portland Fire Bureau, and Good Samaritan Hospital emergency room personnel are l

trained on an annual basis in radiation safety and RRF emergency procedures.

10.2 Conduct of Drills and_Ezer. class i

Onsite emergency drills shall be conducted annually to test the adequacy of emergency procedures and to ensure that emergency organization personnel are familiar with their duties. These drills shall be executed as realistically as possible and shall include the use of appropriate emergency equipment.

At least every two years the conynunication links and notification procedures with offsite agencies and support organizations shall be tested.

Accident scenarios shall be developed for conducting drills to include:

1. Medical emergency drills involving a simulated contaminated individual.

2.

Radiological monitoring including contamination control methods, dose rate measurements, nort-essential personnel evacuation, and record keeping.

3.

Communication drills designed to ensure reliability of the system (s) and correct transmission and receipt of messages.

10.3 Critia= of Drills and Exercises At the conclusion of each drill a critique to identify deficiencies shall be held by the participaing RRF staff and all drill observers and may include members of other support and emergency groups.

Observer and participants comments concerning areas needing

'wrceig,at shall be evaluated and consideration may be given to possible m

changes in the plan and procedures.

Results shall be evaluated by the l

Reactor Safety Committee (RSC).

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I 10.4 Emeroency Plan Review and Llodate The Emergency Plan shall be revised and updated as required based on drill results or changes in the facility and shall be reviewed annually by the RSC to ensure the plan is adequate and up to date.

l AppIlcable portions of the plan, agreements, and if@lementing procedures shall be distributed to authorized agencies and support organizations, and any revisions to implementing procedures affected by the plan shall be approved by the RSC and sent to authorized recipients within 30 days ofter the revised plans have been lasued.

10.5 Emeroency Eautoment Maintenance Surveillance Surveillance of emergency supplies insures availability and proper condition for immediate use.

The RRF operations staff is responsible for surveillance of emergency supplies. Emergency suppIles at the RRF are verified to be operational and complete on a semi-annual basis, and fire extinguishers located throughout the facility are checked i

approximately semi-annually by Car @us Physical Plant personnel. The pool level alarm system is verified operational on a bimonthly basis and is maintained by the RRF and Reed Physical Plant.

Telephone and radio communication maintenance is provided by the utility company or the

(

manufacturer of the equipment.

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10.5.1 inventory of Emeroency mmalies and Eautomant l

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The emergency kit is located in the evacuation corridor from the RRF facility.

The kit is inventorlod on a semi-annual basis or af ter each use and contains such items as portable survey instruments, protective clothing, flashlights, survey maps, swipes and barrier ropes and t

i signs.

Firefighting facilities at the RRF include CO2 fire extinguishers distributed throughout the site.

The condition of these extinguishers is checked and certified by the Reed Physical Plant or Contracted Service annually.

Additional emergency equipment la avellable from the Reactor Storeroom ESC, and Offsite Support Organizations.

10.5.2 Radiation Monitorino Eautoment Checks and Calibration Portable health physics instruments, including l

doelmeters dedicated for emergency use shall be inapected and checked for operability and calibrated semi-annually.

The RRF Operations staff 1

conducts routine checks and calibrations of facility air and arm radiation l

monitors.

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