ML20011B082

Radiological Contingency Plan

ML20011B082
Person / Time
Site:	07000734
Issue date:	10/31/1981
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20011B083	List: ML20011B082 ML20032A982
References
19804, PROC-811031, NUDOCS 8111040192
Download: ML20011B082 (48)

Text

_.

3

,e

.n r

j/

.._m

.nl

\\

_ n ero,u no una va e v.,

e u. r e.,--, -wa r v.

1.

u m r,v.i ni

,m inwimr>~

wsur m uw.rman

.-~.m.

m

--m General Atomic Company I

I RAD OLOGICAL

~

CONT NGENCY PLAN fr ~i s

N.,/

October 1981

-n

-. =

- - = - -.- -

.m

. -,a

-w

~~-n wn -

3g1

,..,.,+...,

.,,,-1,4

..s

..s g.gW"Q"> k, *.' '

4..

t f.

Ws&

+

~

ppy

<(

j ?:', <,,

~

y J

~

~

g m{.,hV

-a r.

y q$

fY, j.y.

~'

i&R

~ -

5

~

i 'i'--

. i

=

PDR

.)

pG TABLE OF CONTENTS 1.

General Description of the Plant / Licensed Activity.

1-1 1.1 Licensed Activity Description 1-1 1.2 Site and Facility Description 1-2 1.2.1 Facility Descriptions 1-4 1.3 Process Description 1-9 1.3.1 HTCR Fuel Manufacturing.

1-9 1.3.2 Hot Cell.

1-10 2.

Engineered Provisions for Abnormal Operations 2-1 2.1 Criteria 2-1 3.

Classes of Radiological Contingencies 3-1 3.1 Class Introduction.

3-1 3.2 Emergency Classification Scheme 3-2 3.3 Range of Postulated Accidents 3-7 4.

Organization for Control of Radiological Contingencies 4-1 4.1 Organization Within GA 4-1 4.1.1 Staff Functions 4-1 i

4.1.2 Responsibility.

4-1 4.1.3 Notification 4-2 4.1.4 Financial 4-2 4.1.5 Primary Support Groups Within GA.

4-2 I

4.1.6 Secondary Support Groups 4-3 4.1.7 Employees and Other Persons with Special Qualifica-tions for Coping With Emergency Conditions 4-3 4.2 Outside Radiological Contingency Response Organizations 4-4 4.2.1 Emergency Directee 4-4 4.2.2 Emergency Cr.ainator 4-4 4.2.3 h eurity Departnert 4-4 4.2.4 Health Physics Department 4-5 4.2.5 Safety Departner t 4-5 4.2.6 Medical Depare.aent 4-7

( ) ;). f > 4L*1 0s 11 l

-i e

\\

4.2.7 Other Support Groups 4-7 4.3 Offsite Assistance to Site.

4-9 4.3.1 Scripps Iknorial Hospital.

4-9 4.3.2 San Diego Police Department 4-9 4.3.3 San Diego Fire Department 4-9 4.3.4 DOE Radiological Assistance Team 4-9 4.4 Coordination with Participating Agencies 4-10 5.

Radiological Contingency Measures 5-1 5.1 Activation of Radiological Cont +.gency Response Organi-zation 5-1 5.2 Assessment Actions 5-1 5.3 Corrective Actions 5-1 5.4 Protective Actions 5-1 5.4.1 Personnel Evacuation from Site and Accountability.

5-1 5.4.2 Use of Protective Equipment and Supplies.

5-2 5.4.3 contamination and Control Measure 5-3 f-~

5.5 Exposure Control in Esdiolog?. cal Contingencies 5-3 k,-

5.5.1 Emergency Exposure Control Program.

5-3 k

5.5.2 Decontamination of Personnel.

5-4 5.6 Medical Transportation 5-4 5.7 Medical Treatnent.

5-4 6.

Equipment and Facilities 6-1 1

6.1 Control Point 6-1 6.2 Emergency Communications Network.

6-1 6.2.1 Telephone 6-1 6.2.2 Radio 6-1 6.2.3 Public Address System 6-2 6.2.4 Alarms 6-2 6.3 Facility and Assessment Teams.

6-3 6.4 Onsite Medical Facilities 6-3 6.5 Emergency Monitoring Equipment 6-4 6.5.1 Health Physics Department.

6-4 i

111 w

3 1

i r

I 7.

Maintenance of Radiological Contingency Preparedness Capability.

7-1 7.1 Written Procedures 7-1 7.2 Training.

7-1 7.2.1 Operating Personnel.

7-1 t

i 7.2.2 GA Emergency Organization.

7-2

. 2 7.2.3 Non-GA Surort Personnel 7.3 Tests and Drills 7-3 7-3 7.3.1 Evacuation.

7.3.2 other 7-3 7.4 Reviewing and Updating of the Plan and Procedures' 7-3 7.5 Maintenance of Inventory of Radiation Emergency Equipment 7-4 8.

Records and Reports.

8-1 S.1 Records of Incidents.

8-1 8.2. Records of Preparedness Assurance 8-2 8.3 Reporting Arrangements 8-2 9.

Recovery 9-1

%s TABLES Table 1-1 Distance / Population of Surrounding Cornunities.

1-3 IV

t i

AU 1

l 1

)

FIGURES i

Fig. 1-1 Location of Nearby Industrial Parks and Cocanunity Facilities.

Fig. 1-2 Plan View of Site.

Fig. 3-1 10 Min. Dose, 3.0*E18 Fission Criticality.

Fig. 3-2 30 Min. Dose, 3.0*E18 Fission Criticality.

Fig. 3-3 1 Er. Dose, 3.0*E18 Fission Criticality.

Fig. 3-4 3 Hr. Dt

, 3.0*E18 Fission Criticality.

Fig. 3-5 8 Hr. Dos, 3.0*E18 Fission Criticality.

Fig. 3-6 Ganana Dose Facility Due to 12 Pulse 3.0*E18 Event.

Fig. 3-7 Neutron Dose Facility Due to 12 Pulse 3.0*E18 Event.

Fig. 3-8 Total Dose in

ility Due to 12 Pulse 3.0*E18 Event.

l Fig. 4-1 Notification Re.gonsibilities.

Fig. 4-2 Emergency Organization on the Scene.

f N

Fig. 4-3 Dnergency Organ.zation - Security control Center.

l i

i l

l

}

t I

V i

- _ _. _., _, _.,. _.. ~. _,.. _,. -. - _.., _ _. - _ -.. _...,,. _ -..

V('~h 1.

GENERAL DESCRIPTION OF THE PLANT /LICDISED ACTIVITY 1.1.

LICENSED ACTIVITY DESCRIPTION The licensee at its San Diego site has been engaged for over 25' years in both government and privately-sponsored research and development opera-tions, some involving use of special nuclear material (SNM).

SNM activities cover the conduct of both pure and applied research and process development as well as fabrication of fuel materials in the nuclear energy related fields.

The main activity involving SNM pertains to the High-Tempers tore Gas-Cooled Reactor (HTGR) system. The HTGR system involves engino ing and con-

\\--

struction of HTGR reactors, the applicable fuel research, investigations of high-temperature materials, design and fabrication of nuclear reactor system components, and the development and fabrication of nuclear fuel elements.

In the production of HTGR fuel elements, uranium, thorium, and uranium-thorium dicarbide or oxide particles are prepared, pyrolytic carbon coated, blended together, made into compacts, and the compacts are assembled and sealed into specially designed graphite blocks.

The TRIGA research reactor systems involve the design, development, fabrication, and installation of research reactors and their fuel elements.

Other activities using SLDI include the operation of two TRIGA reactors providing the irradiation services for varying types activities involving physics research, activation analysis, and reactor research and deve.

ment.

l 1-1 L

O 1.2.

SITE AND FACILITY DESCRIPTION The main site of the licensee at San Diego is located at 10955 John Jay Hopkins Drive approximately 13 miles north of downtown San Diego. The site occupies 360 acres.

Component and fuel manufacturing, as well as HTGR fuel production pro-cess development, are located in Sorrento Valley at 11220 Flintkote Avenue on 60 acres of property contiguous to the main site.

The site, vacant at the time of selection in 1956, was chosen from within a large industrial research park so our activities could be conducted in a modern university-like environment away from the residentially zoned areas of the city.

The distance from the main site to the closest single residence is pre-sently about one mile with the other nearest housing approximately 1.5 miles.

This degree of isolation will probably continue indefinitely dee to the nature of the surrounding terrain and land use zoning regulations. ihe facilities do not interfere with recreational activities in the area, nor do they pose a threat to cultural or historical sites.

The present population within a one mile radius of the main site is primarily of an industrial and university campus makeup, with an estimated daytime total of up to 14,500 people (about 2300 are the licensee's employees).

The immediate vicinity surrounding the Flintkote Avenue facilities is zoned for industrial activity.

Interstate Highway 5 is located about 1/2 mile to the east of the Component and Fuel Manufacturing building. The location of nearby industrial parks and community facilities are shown in Fig. 1.1.

i l G) l-2 L

O The majority of the present population to the north is in a series of small, unincorporated towns extending to Oceanside, 25 miles nocch with a population of 76,700. Escondido, 18 miles northeast of the site, has a population of 62,500. To the south is the metropolitan area of San Diego.

The distance and population of surrounding communities is given in Table-1-1.

TABLE l-1 DISTANCE / POPULATION OF SURROUNDING COMMUNITIES Distance (Air Miles)

Community and Direction Population *3*

Del Mar 5 miles north 5,017 Los Penasquitos 8 miles northeast-19,000 Rancho Bernardo 13 miles northeast 16,100 Poway 12 miles east 32,100 Mira Mesa 6 miles east 37,500 University City 4 miles south 28,900 La Jolla 5 miles southwest 27,900 4

l Clairemont 6 miles south 82,400 l

(*) Population data current as of 1980 census.

l l

l l

l No significant fresh water recreation areas exist within the local hy-drological area, nor is there significant agricultural activity. Los Pen-I asquitos Creek flows into an area called Sorrento Slough which is part of Torrey Pines State Park and near to the licensee's site (about one mile in distance). The slough is a game refuge and an area of tidal mud flats.

1 All plants and animals in the area are protected and essentially no human use is made of it.

' O 1-3 l

l

[

' pU l.2.1.

Facility Descriptions The following is a description of the major facilities at'the licensee's site. Fig. 1-2 is a plan view of the site which contains the major facilities.

i 1.2.1.1.

Flintkote Avenue Facilities SV-A Building Located at 11220 Flintkote Avenue in Sorrento Valley north of the main complex, the Component and Fuel Manufacturing building contains offices, shops, and an area used for fuel and component fabrication. Four hundred ft long and 120 ft wide, about two-thirds of the building is of high-bay e

construction. The east side of the building adjoining the high bay area is divided into two floors.with offices, laboratories, storerooms and a 1

cafeteria. Nonradioactive tasks in the facility are performed in a machine I \\

shop, a sheet metal shop and an assembly area for mechanical parts occupy-V ing approximately 2/3 of the building. The remaining building area is de-voted to fuel fabrication activities. The fuel fabrication area is bounded by outside walls, a masonry wall and a structural steel wall, which separ-ate it from other areas and activities. Access to the fuel fabrication area is restricted to limit access to authorized personnel, to control SNM, to maintain control and nonitoring of personnel and to prevent the spread of contamination. Separate ventilation systems are maintained for facilities i

and areas involved in SNM processing.

SV-B Building l

l Process development, pilot scale operations and specialized fabrica-i tion work related to fuel production are conducted in a building adjacent to and north of the Component and Fuel Manufacturing building. Process de-velopment is performed in the east half of the building.

O 1-4 i

I

. -. ~ _, _., -

.~_

O)

IV 1.2.1.2.

Ikdit Site The main site is on Torrey Pines Mesa about one mile east of the ocean

~

at an elevation of 300 ft above sea level. The site extends into the adja-cent Sorrento Valley at an elevation of between 50 and 75 ft above sea level.

The main site contains office and engineering buildings, laboratories, re-search reactors, hot cells, a research reactor fuel fabrication building and a low-level waste processing facility.

Laboratory Building The Laboratory building contains offices, shops and laboratories for work with low-levels of radioactivity. Most of the research activities in metallurgy, chemistry and experimental physics are conducted in this build-ing.

Hot Cell The Hot Cell facility is equipped to perform a wide range of investi-gation of the physical, metallurgical and chemical properties of irradiated specimens, including examinations of full-size power reactor fuel elements.

The facility includes a high-level cell with three operating stations capable of handling activity levels of up to one million Ci of 1 MeV gamma, an ad-jacent low-level cell that can be used separately or in conjunction with the high-level cell and a etallography cell equipped to provide conplete metallurgical investigations including micro, macro-and stereo-photography.

Supporting areas include a service gallery, physical test room, machine shop, manipulator repair, decontamination room and an X-ray room.

v) 1-5

_ _. _., ~... - - _ _ _. - - _.. _ - -. _..... _ _. _.. _. -. _..

d TRIGA Reactors Located north of the Laboratory building, the TRIGA Reactors provide an area for diversified experimental and irradiation studies using the inherently-safe TRICA Ifark I and Mark F reactor facilities.

Included with-in the building area are associated reactor control consoles, a low-level counting room, a small shop, and administrative offices.

Specific uses of SNM in this area generally are governed by the terms of Facility Licenses R-38 and R-67.

Experimentt1 Area Building I (EA-1)

This building typically consists of radio-chenistry laboratories and 2

offices. There are about 1100 ft of area located in a nearby underground bunker. The facility is used for general laboratory activities.

(v TRIGA Building The TRIGA fabrication building, approximately 60 ft x 125 ft, is con-structed of reinforced concrete prefabricated panels. The building contains SNM storage vaults, drum storage area, operations associated offices, locker and restrooms, as well as the fuel fabrication area.

Waste Processing Facility This facility is located 1000 ft east of the Hot Cell facility.

In-cluded in the fccility are service buildings, evaporation ponds, an incin-I erator (currently dismantled), and various storage areas. The evaporation ponds occupy approximately 4800 ft OV l

l-6 l

l

O Experimental Building (E)

This building houses offices, as well as engineering, metallurgical, chemical pilot plant activities. The major activity involving the use of SNM is the chemical pflot plwit activ~.'.ty.

The metallurgical and chemical-pilot plant work areas are subjected to the appropriate controls to mini-mise the possibility of uncontrolled spread or release of radioactivity to other areas. The support personnel for these activities utilize a frac-tion of the offices available. The other offices are used by such groups as the Fusion Project, General Engineering, etc.

1.2.1.3.

Utilities Water Water is supplied by the city of San Diego Department of Utilities.

Sewerage Systems Sewer service is supplied by the city of San Diego Department of Utilities.

Sewage released from the licensee's facilities is processed at the 100 million gallon per day Point Lona Sewage Treatment Plant.

Hold-up tanks are provided for sampling of effluent liquids before release to the sewerage system.

O 1-7

q O

j.

Gas and Electricity Consnercial quantities of gas and electricity are supplied by San Diego Gas and Electric Company.

+

4 Emergency and Auxiliary Power Emergency and auxiliary pover generators are available to assure con-i tinued operation of critical equipment, lighting, security. fire and other

{

safety alarms, and required surveillance.

[

An auxiliary 25 kW(e) power system located near the Administration Building automatically engages in case of a power failure. This systam supplies power to the main site, fire, criticality, and security alarm sys-tems.

In the event of a power failure in the SV-A building, 2 standby electric s

generators automatically become energized. They are capable of producing 75 kW(e) of rated electric power thereafter to designated components. The auxiliary power unit supplies emergency power to criticality fire and secur-l ity alarms, as well as to certain equipment cooling systems.

In addition, wet-cell battery or emergency generator powered emergency lights are located strategically throughout the facility to illuminate evacuation routes and f

equipment that may require surveillance during power outages.

I t

I 6

' O i

1-8 i

f

1 i

j 1.3.. PROCESS DESCRIPTION The detailed descriptions of the processes used in the various facil-ities are included-in detail.in Section 3.0 of the Demonstration Volume of 4

t the SNM-696 license. A briaf description of the processes in the major fac-111 ties is given here.

i j

i 1.3.1.

HTGR Fuel Manufacturing t

]

The HTGR fuel production process begins with uranium and thorium cxide particulate material. These materials are mixed with graphite flour and ethylene binder ta form a slurry which is subsequently dried, sized into i

sand sized particles. The oxides are converted to carbides in a vaccum

\\

j heating step and the particles are spheroidized to form tiny microspheres.

In a fluidized bed furnace, the microspheres are coated with five layers of pyrolytic carbon and silicon carbide which form the primary barrier to fission gas release in the reactor core.

The coated particles are charged to a multi-cavity ir.jection mold where a heated mixture of petroleum pitch and graphite powder are injected into l

the mold, filling the void space around the particles. The mold is then f

cooled and the solidified, 1/2 in. diameter x 2 in. long fuel rods are-

~

ejacted from the mold. The rods are packed in finely-ground aluminun oxide and heated to 800* C to carbonize the petroleum pitch. The carbonized rods are then treated with hcl gas at an elevated temperature to leach exposed uraaium and thorium from the rods. They are then heated to 1700* C to re-

{

move residual hcl and improve heat transfer characteristics of the rods, i

The rods are loaded intc, the fuel holes drilled into graphite fuel elements and the fuel holes sealed with cemented graphite plugs. Each element is then packaged in a sealed double barrel shipping container for f

transportation to the reactor.

4 i

(

j 1-9 3

I i

e4 vv,--

y e -y,vwvr-m-re++w-,-wee

- y

+-, y w

,,e e p r r wwc,

,,_g-g7,..&r-y-m-ee-,--

aw--*--

- 4s,* e e n

~--M=*

vw --+

w - - m r-s e

• s v--***

wv=~1

• • =rw-*

mtr*

i i

a i

i 1.3.2.

Hot Cell The Hot Cell is involved in research on irradiated fuels, irradiated components or other large sources of radioactive material. Such fuels, components, and materials are disassembled, dissected, examined using re-1;-

mote manipulators.

f-

[

e i

4 f-r 4

I' i

s 4

i r

l l

l l

l l

l l

l l

l

?

1-10

D. hM N'T ***

I $ ( #; M @ 9 4 ', <

Y' \\ sk, ' ~ - ('dd_

N f.3,,,,,<.b

,a IND..

Qv' es. qi f

w

,y

/

r

g. k ?Q h,.:

fV,l,Q. *.'

5 v

,,,. " ~

c o

t

,.w.g 1 n

- ' - [..f 4* D g.

SCH00 r IND.

[4eb' Y] t SANP IEGp-7

..1...g..,

4 N E- -k ( M U I

AN(FlffE

,d,

i.

O',.

c'

/'

I ~

II Il c

4. 4,

, cf g j

onanocRam nut

.I 4 h' kSi NTI AS ' '* f f.

s i

Y.

,/

[

A l

um imigrg o,F,UMANWRAP i

,e -

t g

s

..-m I

SCALE IN MILES l '~ 'd h,

~ ' ^ ^ *

(F I

I 0

1/2 1

(.;m g 3

r a

'3-y a

= _ = _

=,

['#

1967 PHOTO REVISED 1975 l4 *

j p j s

Figure 1-1 Location of nearby Industrial parks and community facilities l

P I

f r^

w t

L

r I

~

I

{

I R[SNNTIA$.C '

.',fiI, k'

"-~ \\

25 1,%

'{,..._....t_._

x nw

.N

/

,. e -

\\

\\

y

~

s.

q

.s

( '

%. Q( e N= ~; p. g L y3iW

..,%. y i

k.

i. s_,.

y, 1

qst) *$

i 8

m x

~.luf f _;p. 8-Ty % f.q;g v.

ps

, l-i e

Il d g

~'

yjG,,_s.Bp

'O 6

r,'

]

M1 co

'a.

~

Iif%

(

k$$N L

O NevetR F Atil Tv 1

ADMIMSTRATICN q'

2 LA8 ORATORY 3

SERV 1CE D

4 EXPEntMENTAL

\\g d

s 5

T O.

'kg 6

LrNAC 7

ECF t

\\'

,r-- i

(

wi 9

TRIGA REACTORS g

n v

10 HOT CELLS 3

j I

11 TRIGA FUEL F A8 j

gg'b el-,N16, 12 WASTE YARD s,#

g

,5 13 TEST TOWER r

}

l 14 SV-A I

II_

k

\\ g )

[

15 SV-8 8

g

\\v>

i 16 SPECIAL PRODUCTS l

IS DOUBLETT m k

17 RECEPTION CENTER g

94 "i g.

\\,

QT

\\

\\

'N;

_ mx'b'v,%h s,

s,'s 1

\\

M~C

\\

s,

/

'l//

. ~,

f*jlny j

/

\\ \\t o'

\\

ll h f':

s

\\'

'y

• ' //

l

\\ p;3

___,//"

A; '

/

iq

~

O

\\

//

,12 &

t

,y

/.4 SECURITY g

g 4

0

,//

8

1. '/

l

• .M) p' 6

\\g

, g

(

FENCE p

st

/

PERnMETER j

ko

\\

j

/,

3 I

i,

-'2 I!

l fh e

!:l

/ssb,y.

3'l Y

i

/

s

,,a-s n

t l

D

• -t

/ j

//

T

.i j o

1 g,#

i(

O 250 500 750 1000 C

// I h

SCALE IN FEET

-- FENCING

- ! [

==== PROPERTY UNE Fig. 1-2 Plan View of Site 1

ww,2,--~-w--rwmt-

,w~wv,v-,-rw-y,-e,p---o,v-~

e r,

,,e n,w m n -e- -na- --e v

--w - f e n wee

-m e-w w -e e v e - ~ e v-~ - w e-er

- wn-w w w---m - sw *

-wr-ws-~~--wo--e-~e-m--.wmar-~e-oe.~,'~r=~~-m-*

s

["

i 8

Q,!

2.

ENGINEERED PROVISIONS FOR ABNOR"AL OPERATIONS 2.1.

CRITERIA Facilities and equipment are designed such that abnormal occurrences will not likely result in the uncontrolled release of significant radio-active material or radiation. This is accomplished by designing facilities such that they can withstand anticipated earthquakes, fires, windstorms or other such occurrences.

Facilities containing significant radioactive material are designed to protect the processes, process material, and process equipcent from adverse conditions caused by cocoon environmental hazards. The facilities are equipped with specialized shielding, fire suppression equipment, specialized air control systems fitted in most cases with IIEPA filtiation or other cleaning systems, e.g.,

fume scrubber, etc.

Facilities and laboratories

(

)

which routinely generate radioactive liquid wastes are equipped with separate v

holdup tanks or piping to assure such liquids are disposed of under planned and controlled conditions.

Process equipment or stations are limited to quantities of material which assure criticality safety in any credible situation.

In addition such equipment is limited to material inventories which also assure the radio-logical safety of workers in the area.

In sone cases, access restrictions are imposed to assure that individuals are not exposed to hazardous radiation or radioactive material.

GA maintains a respiratory protection program.

Process equipment and/or their enclosures are designed to contain the inprocess material through normal process upset conditions. Their designs do not allow individual components of process equipment to adversely affect the effluent conditioning or containment features of the respective labora-tory or facility. Certain equipment will be fitted wish prefilters, dampers, etc., to provide localized containment and assure that facility containment

[)

facilities are not compromised.

J 2-1

l lO l

1 i

j 3.

CLASSES OF RADIOLOGICAL CONTD;GENCIES i

3.1. Class Introduction The classification scheme is described in Section 3.2.

In it, amer-1 gency situations are classified into the four categories specified in Sec-l tion IV of appetidix E of 10 CFR Part 50.

1 The ratianale for the notification and alert classes is to provide early 1

and prompt notification of n# or events which could lead t > more serious con-sequences given operator erros or equipment failure or might be indicative of more serious ccnditions which are act fully realized.

4

}

i I

I i

f i

i l

l I

t 3-1 i

..~.

O 3.2.

EMERGENCY CULSSIFICATION SCHEME Class - Notification of Unusual Event Class Description. - Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.

No releases of radioactive material requiring offsite response or monitor--

ing are expected unless further degradation of safety systems occurs.

Purpose. - Purpose of offsite notification is to (1) assure that the first step in any response later found to be necessary has been carried out.

(2) bring the operating staff to a state of readiness, and (3) provide sys-tematic handling of unusual events irformation and decisionmaking.

Licensee Actions s

1.

Promptly inform State and/or local offsite authorities of nature of unusual condition as soon as discovered.

2.

Augment on-shift resources as needed.

3.

Assess and respond.

4.

Escalate to a more severe class, if appropriate.

or 5.

Close out with verbal sursaary to offsite authorities, followed by written sutsnary within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

O 3-2

O Class - Alert Class Description. - Events are in process or have occurred which in-volve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guide exposure levels.

Purpose. Purpose of offsite alert is to (1) assure that emergency per-sonnel are readily available to respond if situation becomes more serious or to perform confirmatory radiation monitoring if required and (2) provide offsite authorities current status information.

Licensee Actions 1.

Promptly inform State and/or local authorities of alert status and reason for alert as soon as discovered.

2.

Augment resources and activate onsite operational support emer-gency facilities and equipment. Bring key emergency personnel to standby status.

3.

Assess and respond.

4.

Dispatch onsite monitoring teams and associated communications.

5.

Provide periodic plant status updates to offsite authorities.

6.

Provide periodic meteorological assessments to offsite author-ities and, if any releases are occurring, dose estimates for actual releases.

7.

Escalate to a more severe class, if appropriate.

or 8.

Close out or recommend reduction in emergency class by verbal summary to offsite authorities followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

O 3-3 I

O Class - Site Area Emergency Class Description.

Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Offsite releases are not expected to exceed EPA Protective Action Guideline exW sure levels except near site boundary.

Purpose. Purpose of the site area emergency declaration is to (1) as-sure that response centers are manned, (2) assure that monitoring teams are dispatched, (3) assure that personnel required for evacuation of the site areas are at duty stations if situation becomes more serious, (4) provide consultation with offsite authorities, and (5) provide updates for the public through offsite authorities.

Licensee Actions 1.

Promptly inform State and/or local offsite authorities of site O-area emergency status and reason -for emergency as soon as dis-covered.

2.

Augment resources by activating onsite emergency response or-ganization.

3.

Assess and respond.

4.

Dispatch onsite and offsite monitoring teams and associated com-munications.

5.

Dedicate an individual for plant status updates to offsite auth-orities.

6.

Ikke senior technical and management staff available onsite for consultation with NRC and State on a periodic basis.

7.

Provide meteorological and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data transmission.

3-4

8.

Provide release and dose projections based on available plant condition information and foreseeable contingencies.

-9.

Escalate to' general emergency class, if appropriate.

10.

Close out or recommend reduction in emergency' class by brief-ing of offsite authorities follound by written summary within.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of closeout or class reduction.

Class - General Emergency Class Description.- Events are in process or have occurred which in-volve actual or inmiinent loss of confinement integrity.- Releases can be-reasonably expected to exceed-EPA Protective Action Guideline exposure levels offsite for more than the itsnediate site area.

Purpose. Purpose of the general emergency declaration.is to (1) ini-tiate predetermined protective actions for the public, (2) provide contin-uous assessment of information from licensee and offsite organization meas--

urements, (3) initiate additional measures as indicated by actual or poten-tial releases, (4) provide consultation with offsite authoritias', and (5) provide updates for the public through offsite authorities.

Licensee Actio q 1.

Promptly inform State and local offsite authorities of general emergency status and reason for emergency as soon as discovered (Parallel notification of State / local).

2.

Augment resources by activating onsite emergency response or-ganization.

3.

Assess and respond.

4.

Dispatch onsite and offsite monitoring teams and associated com-munications.

5.

Dedicate an individual for plant status updates to offsite auth-orities.

O 3-5

_~._ _ _ _ -... _ -

i i

4 ii.

6.

Make senior technical and management staff available onsite for i

consultation with NRC and State personnel on a periodic basis.

7.

Provide meteorological and dose estimates to offsite authori-j.

ties for actual releases via a dedicated individual or automated.

data transmission.

l

.8.

Provide release and dose projections based on available plant condition information and foreseeable contingencies.

j or 9.

Close out or reconsaend reduction of emergency clac.s by briefing 1

of offsite authorities followed by written sunnnary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> I.

of closecut or class reduction.

1 1

I I

d I

4 4

i

?

3 L

1 l

4 I

e 1

I 3-6

\\

p)

L 3.3.

RANGE OF POSTULATED ACCIDENTS A range of postulated accidents is analyzed in Section 7 of the Demon-stration volume of the SNM-696 license. The one with the greatest poten-tial offsite radiological consequences but lowest probability is a criti-cality in the Fuel Fabricrtion Facility in Sorrento Valley (Building 37).

The greatest potential radiological consequences from this accident would be 0.86 Rem whole body, 0.26 Rem thyroid, 0.015 Rem bone, and 0.023 Ram lung. These doses are well within the protoctive action guides (PAGs) of the Environmental Protection Agency (1 Rem whole body, 5 Rem thyroid, and 3 Rem other critical organ). Figures 3-1 through 3-5 give the time-dose-distance relationships.

The same accident, i.e. accidental criticality at the process liquid dumping statior., has the greatest potential for employee exposure as well.

The range cf doses received by a worker located at various distances near the accident for five minutes, assuming the more reasonable multiple pulse model, are:

Distance namma (R) Neutron (Rem)

Total (Rems) 3m 262.

613.

875.

10m 23.

53.2 76.2 20m 5.6 12.6 18.2 In actuality the doses will be smaller since evacuation alarms will sonind and evacuation from the facility rapidly decreases the exposure as distante is increased. Time-dose-distance data are shown in Figures 3-6 through 3-8.

More than adequate personnel capability and instrumentation are avail-able to assess and mitigate the consequences of the range of accidents pos-tulated. An emergency would be declared based on the classification scheme of Section 3.2. if a minor event could lead to more serious consequences.

l 3-7

i. %c ! p rrc.c,tqt.! roiTirp iTy r i p3 7_t In P T e,t p.,nc r 1,.

v i..-

v.

a o -i.

.ss

.w

.v 1

e~

(v!)

'; h

/ ~_

c TGTRL SGDY DGSE 0

CLGUG IMMERSIGN CGSE b

a INHRLRTION, THYRGIO

+

INhSLRTIGN, SUNE

[

x INhRLRTIGN, LUNG 1

Z PRGMcT TGTRL GCSE b

7 FRGM T NEUTRUN GGSE

=x j

0 PRGMcT GRMMR CUSE s

4

-ex x

h,,

\\

g

(

z m

u :-

% g cc o

x e

.~

=

's es

\\

'\\ \\

x xx u,

g w-a

.x s

\\

\\\\e Q~

\\

\\

c a 'o __

i N

- su ~ :

~,m,..

(*

.s s

x y

.x

• 4

.._1

\\.

\\

A z

\\ \\W%

\\

~'

\\\\ \\

N W

9

\\

N\\

27 A

V..

a_

8 Q \\\\

i

~'

c3 x w

\\

o

\\

\\\\ N

(

4)- \\

\\

Jr

^

c.o_

z~

0 1

cc x

x i

e i

s T i

\\

h

\\

\\

\\ \\

\\\\

} \\

r

o. -

.I 1

I

\\

\\

\\

k

\\

\\

o_.

\\

r

~

l 1

1

-k I

1

\\

k h

• d

\\

t

\\

\\

\\

,o a

~

10' IG" 10~

I C' DISTANCE IN KILCMETERS

.is

.v

._ s.<

T i.p 7, __,

3p rsi pqcc q

c. _ c ;;; r r c, c. i rj. r r-T T..T r @. m. w..

ci c.,

s t

) "a v

1

~

i O

TOIRL SCDY 03SE o

CLCUD It1ERSIGN 00SE a

A INERLRTICN, THYRGID

~

+

INHRLRTION, SUNE i

i i

i i

x INhBLRTION., LUNS

~

Z FROMcT TCTRL SUSE b_

7 FROMcT NEUTRGN CGSE o

FRGMcT CW'Nei GGEE

[

w.

-ex w

i i

i j

I n

n N

ua N

l c::

~

'~_

I

^

c N

c<

i

~

i 7%

i i!I A

Ai\\

i g

A N i l l e

% N~

h

!\\'N N

<_w -

(

J

. x 'i x

s

()'9

_.X, i

NN

~

5 i

x xv w

vs i 6 K\\

i i l

N\\\\

l i Ni

~

l g

s s

q o

h.

\\ \\

G=7

\\ \\A 0

v h=_

i I

s.

i N !

I a

t x

i 3

\\su A

x!

O

\\1 \\\\

l

\\

i\\ l l

Jr

'\\ k N N l

c. c r-o i

i i

1

.+

Oc i

+

i i

i N

4 i

i i_

a c

i i

i Ai

• i i

ti I

i 15

\\

I i

\\

l!

\\\\

ll

<o s,

3 l

i 1

t t

i i

l i

\\

\\

t

?

I i i I

I I

1

\\

kI i

i I

1

\\

\\

i i

l

\\,

l i

c l

1 I

l 1

i t

1

\\

t 8

8 e

i e

4 j

[

l I

\\.

k k

I i

5 i

v<

i !\\

l j

t i

i TI\\

l hl eO 10

10' 10~

I G'

,h. w. 4

r. r.e e

7. cue m 1 F.. h -

1.,

m re J.J 4i1 w w

~

FIG 3-3, i HR DOSE, 3.0*E18 FISSION CRITICALITY n/\\v) b

~

C TGIRL SGDY DGSE o

CLGUD IMMERSIGN DGSE A

INHRLRTIGN, ThYRGID

~

o, _

+

INhBLRTION, SONE E

x INhSLATION, LUNG 2

FRGMcT TOTAL DGSE "o _

v FRGM"'T NEUTRGN DGSE o

FRGM T GRMMR DGSE E

w d\\

\\

N W

a b '-

h \\\\

e: o A N N._

-. ~

O

's a_.

s

's mcx x

x xx d

A N

xx g-;

\\\\

o x

\\

d,.y-

'L'iN

'N

'i Z

\\ \\\\

N

\\1

~

\\

4.

\\

k

\\\\\\

N N LA X

L X

~'

\\

\\\\

\\

J

\\

\\ i N

i o

g gg x

y

\\

\\

gr

'\\

\\

\\

L o

co

r. -

o s

a.

\\\\

fa i

\\

\\

\\

\\

\\

r

\\

\\

o

\\

(

l

\\

k

\\

\\

\\

,'o

\\

i i

n r

s

(

\\

\\

i

'L/

\\_

\\

?o I

1 i

10

10" 1C 1 G*

DISTRNCE IN KILGMETERS

p n n u r' J n=r '3 rTScrv rpiT.1vT nci i Ty F.T G

'J J

its v<>~f

.- %i i

J.uw u.

o.

/

x.

t

b V

O TOTRL BGDY DGSE o

CLGUD IMMERSIGN DGSE I

a INhRLRTION, THYRGID

~o

+

INhSLRTION, SONE

{

x INhnLSTIGN, LUNG 1

2 FRGMcT TGTRL DGSE v

FRGM T NEUTRCN DGSE b_.

~'Jc i,

o PRGMPT GRMM9 GGSE s

- x s

ex x

s i

s I

i N N 6

4 \\

\\

7 c

~

s ea n

-, ~ *

's

's

's N -

1 x

x x,

s s

x s

s x

x i x

\\

\\

N

'N g

N N

ES,

%L c-Q K

^

o o.

~

~

emu-

~_

y (vd s 's

-is !'s t

s r

xx x

i x x

z

\\ \\\\

'N N

\\\\\\

xN

^

~

h

\\\\\\

t ui d

~

D 3

p 3

~\\

\\1 o

\\

(\\

,_.r

\\ %'

e o_

r-0 i

i 1,

w

_4 _

e

\\

\\

\\

\\

\\

'o

\\

\\

i.

i 1

\\

\\

\\

Y L-

\\

\\

\\\\

,'o

.k i

~1 r

t r

(

\\

\\

\\ v )'

\\

\\

\\\\

o 6

6 6

DISTRNCE IN KILGMETERS

r [ g a _ t-p Ho s nner.

J'. n u o

.s s i tg p J c c J. q. r i r p T T..T r pL I T Y.

r a _;

4 m

i u,.

a im ~,

(.

a

\\

)-

j 1

v 0

TOTAL SODY DOSE o

CLGUD IMMERSIGN DOSE

'o a

INHRLRTION, THYRGIO

+

INhBLRTION, SONE E

x INhSLRTICN, LUNG Z

FRGMRT TOIRL GCSE h

i 7

PRGMcT NEUTRGN DOSE

~:

1_.

A ;

o PRGMPT GRMM9 DOSE s x 43 x x A %

'x 'w h

4 m

s g) 5

• g \\'N N

o q

N ea s

_Z,

~

x

~

'\\ 's x

s is i s

i g-x x

x x'

c x

h,%

N k

\\

?g y

y.

..~,

f~'

.[

9 x;

xs s

y

\\ \\\\

~

\\\\\\

\\

a

-N z-

<r 'o

\\

~

a t

s x

-)

i

\\\\

g

_a

\\

w a

\\

\\\\

3

\\

sr co

\\

r:

2_

1 '.-

I x

e xx

\\

\\

\\

\\

\\

.'o

\\

\\

i i

\\

\\

1

\\

k

\\

\\

\\

\\

,'o

\\

\\.;

T 1

"s.

~

i i

g g

i,

/

\\

\\

I I

t

\\

\\ !

o.

a s

s s

s i

10

10" 10*

10' DISTANCE IN KILOMETERS

(

F I c 3 -6, r;m. w,.c.

n r e r_,

.P.i Fc.r T. :m.ry CiL;c T.0 m7 r i

.e ru m _,_~.n.r.o' r_e, rot t

i a

s.

u s

_u.

i.

m m

s

(

/

~

v q

- y.my o

5 MINJTES

- - * ~

a 10 MINJTES "o.

+

30 MINJTES

s.

j x

60 MINUTES E

x s WN o

120 MINJTES

~_

R'\\\\\\

16 INCH CONCRETE WRLL N NNN 4NNN

~

r s

'qi xx x

'xX \\ \\\\

NNNNN

%\\\\'\\

N d_

xx,'s x - s

.x x x x

\\\\ \\

'x \\

NNNN N

%\\\\'\\

U N\\NN

\\

\\

\\

ub_ -

cc TN

,x x x x

g I e-

• x V,'

\\u yx o

xXN xx b

%':\\\\\\

"o s _.

g xx x x.

\\\\\\\\\\

N(~\\ \\. \\

%W\\k\\

c_.

-(c s

\\'t\\\\ \\

\\\\\\ 'i. \\

'K\\M c_

~

L \\,

k\\1

\\.O\\

\\

\\\\\\}

-y

'a_.

p)

's-I re.g

~~

11 ld 10 11 DISTRNCC IN METEMS

FIG 3-7, NEUTRON 00'iE IN FRCILITY DUE TO 12 CCu5E 3.D*E15 E'!ENT s

)

~

v o

5 MINUTES a

10 MINJTES d_..

b_s.

+

30 MINUTES A,s xox,

x 60 MINUTES s

"d'5 2x o

120 MINJTES

~

' %D 16 INCH CONCRETE WRLL b..

\\

s's'.'s s xxxxx xxN N N

\\\\'\\\\\\NN u,

x

-, s's'sN

\\x'<\\

\\

NNNNN

\\\\\\\\'N s

NsNNN s

s E

NN ' \\ \\

ub-x f w) =

n xx

(

%\\\\

L/ g-vsxxx 8

\\\\'N\\\\

b c.

c.

E

'GNs1

\\\\\\\\\\

'\\\\ \\\\ '(

WN c_.

i b

t'

\\

51'\\ \\

\\\\\\\\\\

%\\

e o_.

5 M\\i t\\\\\\

@\\\\

D....

fe, f, -

-o I_.

n 4

%)

<a.

~~

10' 16 IN Id DISTANCE IN METERC 4

-~

FIG 3-6, TCTRL 00"E IN FRClulTY DUE TO i2 CUujE 1.0-E'S EVENT

/Q) d.

~

o 5 MINUTES A

a 10 MINUTES d_..

f.

.\\

+

30 MINJTES

?s x

60 MINJTES sss x

s "xi'R\\

o 12G MINJTES T

N 16 INCH CGNCRETE WRLL d_.

\\\\

m s

m

\\\\N \\

\\

\\\\\\

\\\\

YW\\

\\NNb 3_..

\\

\\

w u

\\

\\\\\\\\\\

T\\Y\\

s s

\\

s Su hss\\

,, e -

1 ib.

\\

v.s um J

\\\\\\\\\\

E5

\\\\\\\\\\

L_.

'M m

m ua

\\\\ \\ \\\\

\\\\s\\\\

SW s t

o_.

T i1

.I

\\xx t

s

\\\\\\\\

I,

\\h-ec.

&\\

(

<sfi

(\\O:

)

t

'c..

ex i

IU fc

• • g

,p

, et e 'eJ Q

&V eV

• U C! STANCE IN METERS

G 4.

ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES This chapter describes the radiological contingency organization to be activated for events resulting in abnormal radiological releases from the license facilities. The augmentation and support frem offsite services and local agencies is also described.

4.1 ORGANIZATION WITHIN GA 4.1.1.

Staff Functions Each facility at GA is staffed with experienced opercting personnel, one of whom is designated as the facility emergency director. These in-O dividuals are well qualified to recognize conditions that may result in an U

emergency situation and are capable of instituting remedial actions to miti-gate the abnor=al condition.

If these remedial actions would be insufficient to deal with a situation, the employees have been trained to make energency notifications and to perform those planned emergency actions that provide for the immediate control over most situations.

4.1.2.

Responsibility i

Senior operating employees present in a facility are responsible for actions during normal operations and during any emergency condition at the facility.

Each operating organization designates its own responsible per-sonnal and their internal notification requirements. The responsible en-ployee present notifies the Security Department (Ext. 2000) and his super-visor immediately, and directs appropriate remedial actions and/or evacua -

t tion until the responsibility is transferred to the Facility Emergency Dir-tor or the designated GA Emergency Director.

p i V 4-1 i

f~h.

(j 4.1.3.

Notification The basic sequence of notification is shown in Fig. 4-1.

The Security.

Supervisor is the focal point for the notification sequence.

4.1.4.

Financial All support groups assigned to the emergency organization consider their particular needs for equipment and supplies for emergencies. These needs are reflected in their budgets, and items are procured by the individual l

1 support groups. The responsibility for the readiness of the equipment and supplies for each group is assigned to the manager of each group.

4.1.5, Prie:cy Support Groups Within GA 4.1.5.1.

Security Department O

This department includes the Manager of' Security, two security admin-istrators, three captains, five sergeants, and security guards, plus an administrative staff. Security guard service is provided for the entire site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, 7 days a week. The tianager of Security takes charge in civil disturbances and bomb threats. Calls for outside assistance are hand-led by a Security Supervisor.

i 4.1.5.2.

Health Physics Department This group consists of the Manager, Health Physics Department, profes-sional personnel, H6alth Physics Technicians, and administrative personnel.

During routine operations, technicians are assigned to separate facilities or work as roving technicians.

O 4-2

_ _..,. _ _.. _... _ _.., _., _ _ ~... _. _ _ _. _ _ _. _,. _ _. _. _, _,

O O

DIAL 2000 RATING ANY y- - -

J FACILITY l

l MANAGEMENTj l

I i

4 SECURITY SUPERVISOR p

T

/

N J

/

\\

/

\\

/

N

/

\\

/

\\

\\

"^ "

EMERGENCY EMERGENCY MEDICAL SAFETY

\\

PHYSICS DIRECTOR COORDINATOR CONSU LTANT DEPARTMENT

\\

DEPARTMENT

• I OTHER SUPPORT G ROUPS REQUESTED l BY EMERGENCY C00 hDIN ATO R t

Fig. 4-1.

Notification Responsibilities 4

1 O

O O

l

?

I j

i i

OPERATING I

EMERGENCY FACILITY i

DIRECTOR PERSONNEL I

I i

l EMERGENCY C00RDIN AiOR j

OUTSIDE SUPPO RT j

GROUPS CALLED BY

}

\\

SECURITY I I M

SUPE RVISO R:

POLICE DEPARTMENT IIEALTH NUCLEAR FIRE: ENGINEER MEDICAL CRSC INDUSTRIAL NMM FIRE DEPARTME NT PilYSICS SAFETY TECHNICIANS CONSULTANT CH AIRM AN tlYGIENIST DEPARTMENT SCRIPPS MEMORIAL HOSPITAL DEPARTMENT DEPARTMENT RADIOLOGICAL ASSISTANCE TEAM i

Fig. 4-2.

Emergency Organization on the Scene I

l I

O O

O i

i i

EMERGENCY COORDIN ATO R i

i i

1 P I

l SECURITY 4

SUPERVISOR i

]

i ALTERNATE FACILITIES PUBLIC CRSC OFFICE TELEPHONE &

"O

^'

C0 NATOR i

Fig. 4-3.

Emergency Organization - Security Control Center 4

l l

1 4.1.5.3.

Medical Deportment This department is staffed with a medical consultant, a registered nurse, and a medical technician. These individuals are available on the site during normal working hours and are on call for emergencies.

4.1.5.4.

Safety Department 1

i This department includes the Manager, Safety and Accident Prevention, a fire chief, four technicians, and a volunteer fire brigade. This department provides fire protection services.

4.1.6.

Secondary Support Groups k

Other support groups are available within GA which augment the normal operations and also may be assigned to the emergency organization if needed.

These groups include but are not limited to: Facilities Engineering. Cri-ticality and Radiation Safeguards Committee, Public Cornunication, Indus-trial Hygiene, Decontamination Services, and Nuclear Material Managene-c.

i 4.1.7.

Employees and Other Persons with Special Qualifications for Coping With Emergency Conditions l

I A list of employees, other than those assigned to the emergency organi-zation, and a similar list of other persons whose assistance may be needed and who have special qualifications for coping with emergency conditions are maintained by the Deergency Coordinators.

i k

4-3

f\\

4.2.

OUTSIDE EADIOLOGICAL CONTINGENCY RESPONSE ORGANIZATIONS 4.2.1.

Emergency Director The Emergency Director for a facility is a senior staff member of the operating organization managing that facility.

In facilities that do not t

contain work involving toxic, fissionable, or radioactive caterials, the Manager, Facilities Engineering, has been designated as the Emergency Director.

The Emergency Director is responsible for the overall direction of all activities at the scene of the emergency (See Fig. 4-2).

He acts with the full authority of the President of the Cocpany. He determines when the facility or area may be re-entered and accounts for all personnel present in the facility at the time of the emergency.

N 4.2.2.

Emergency Coordinator The Emergency Coordinator is the Manager, Health Physics Department.

Four alternate Emergency Coordinators have been designated. The E=ergency Coordinator is responsible for coordinating the activities of the various emergency response groups (see Fig. 4-3).

When informed that an emergency condition exists, he reports to the Emergency Director at the scene of the emergency arl assists the Emergency Director-in controlling the situation.

All support groups report to the Emergency Coordinator. The alternate Emergency Coordinators report to the Control Center.

1 4.2.3.

Security Department 2

4.2.3.1.

Manager The Nanager of Security reports to the Control Center as an alternate Emergency Coordinator.

If required, he directs the establishment of road 4-4 i

e O

blocks at the entrance of the site and provides for traffic control on the site and at the scene of the emergency.

4.2.3.2.

Supervisor A Security Sopervisor is continuously on duty at the Control Center (Ext. 2000).which fA located in the A M nistration Building, Room 0-103.

During the initial phases an emergency the Security Supervisor acts as the Emergency Director _ until the designated Faergency Director arrives at the scene. He institutes the notification and emergency procedures required to I

cope with the situation until re?.ieved by the Emergency Director at the scene. Fig. 4-1 presents the notification responsibilities.

4.2.4.

Health Physics Department The Health Physics Technicians are assigned to the emergency operations during an emergency. They report to the Emergency Coordinator at the scene of the emergency.

4.2.5.

Safety Department 4.2.5.1.

Manager The Manager of Safety reports to the Control Center as an alternate Emergency Coordinator. He provides coordination between the Control Center and areas, departments, and personnel not directly involved with the ener-gency.

4.2.4.2.

Fire Department The Fire Chief, fire technicians, and Fire Brigade are assigned to the emergency operations during an emergency.

1 t

4-5

-e n e.

w%s-eww,.c.-

..r,m,3,n-we.,_,,

e g-e,,-,

,.w--.7,-

,r--

,,-u,-.,

,,-,y,,

,W4

,.nr ve r-g

,.--m

-w e-, g, 7 y w r

.r.-------iw r, - ry

--,, r g-.

,- my tw--

i l

f Fire Chief The Fire Chief reports to the Emergency Coordinator at the scene of the emergency to evaluate fire hazards. He notifies the Control Cen-ter to have the Fire Brigade report to the scene or requests that they summon the SDFD.

Fire Technicians Fire technicians report to the scene with the fire fighting vehicles and equipment.

If no Health Physics personnel are present and entry 4

into a Controlled Area is necessary, the technicians shall determine the extent of the radiation hazard with appropriate radiation detec-tion equipment prior to facility entry.

If radiation levels exceed 5 R/hr at the facility entrance and no lifesaving actions are re-quired, no entry shall be made until Health Physics personnel are

(

present to evaluate hazards.

If radiation levels at any location within the facility exceed 5 R/hr and no lifesaving actions are re-quired, all personnel shall immediately withdraw from the facility until Health Physics personnel are present to evaluate the radiation hazards. If lifesaving actions are required, personnel effecting the rescue shall limit their dose to 75 Rems.

Scott Air Packs or equivalent self-contained breathing devices will be worn on all entries until airborne radioactivity or other air-borne hazardous materials have been evaluated by Health Physics and Industrial Hygiene. Hazard evaluation shall be relayed to the Control Center as soon as possible.

O 4-6

m 4.2.6.

Medical Department The Medical Consultant reports to the scene of the emergency.

He dir-ects all medical activities and advises the Emergency Coordinator as to the medical aspects of the emergency.

4.2.7.

Other Support Groups 4.2.7.1.

Industrial Hygienist The Industrial Hygienist reports to the Emergency Coordinator at the scene of the emergency. He evaluates health hazards of toxic nonradioactive materials and recommends controls to prctect personnel.

4.2.7.2.

Facilities and Plant Engineering

/)

The Manager of Facilities Engineering reports to the Emergency Coordi-

%- /

nator at the Control Center and directs all Yacilities Engineering personnel who are available for assignment to the emergency organization if they are needed. These include electricians, plumbers, maintenance engineers, and-laborers.

4.2.7.3.

Public Communications The Director of Public Relations and Advertising will establish a pub-lic information office at a designated location and shall be renponsible for all public relations aspects of the emergency.

I 4.2.7.4.

Criticality, Radiation. and Safeguards Committee The Chairman of the Criticality and Radiation Safeguards Committee re-i ports to the Emergency Coordinator at the scene of the emergency. Other members of the Criticality and Radiation Safeguards Committee report to the i

Control Center, pending instructions from the Chairman.

-~

'% )

1 4-7

Os 4.2.7.5.

Manager. Nuclear Safety The Manager, Nuclear Safety reports to the Emergency Coordinator at the scene of the emergency.

4.2.7.6.

Office Services The Manager, Office Services reports to the Emergency Coordinator at the Control Center, where he makes arrangements to perform decontamination and/or other cleanup services as required.

4.2.7.7.

Telephone and Teletype Communications The Supervisor of Telephone and Teletype Conmunications is responsible for expediting telephone communications.

Only those outside calls directly related to the emergesey are put through to the Control Center. Calls from

(N the news media will be put through to the Manager of Public Communications.

4.2.7.8.

Nuclear Materials Management The Manager of Nuclear Materials Management reports to the Emergency Coordinator at the scene of the emergency.

I f

O 4-8

O j

4.3.

OFFSITE ASSISTANCE 'IO SITE 4.3.1.

Scripps Memorial Hospital Scripps Memorial Hospital has agreed to accept victims of accidents.

Scripps, however, relies on GA to provide the necessary health physics equipment and personnel to assess and monitor radiation and contamination levels of their facilities, personnel, and patients.

4.3.2.

San Diego Police Department 4

4 The San Diego. Police Department has agreed to provide assistance to GA '

1 in an emergency. This assistance includes coordination with other civil authorities as necessary, traffic control, and additional service if needed.

4.3.3.

San Diego Fire Department The San Diego Fire Department responds to emergency calls at GA.

If I

j the response is for a fire involving radioactive material, the GA Health Physics Department provides the necessary monitoring to protect Fire De-partment personnel.

1 4.3.4.

DOE Radiological Assistance Team i

The DOE Radiological Assistance Team for the San Diego-Imperial County area is comprised of health physics, medical, and public information spec-

{

ialista. All merbers of this team, except the medical personnel, are en-playees of GA and belong to the GA emergency organization. During an emer-1 l

gency at GA, they would function as part of the GA emergency organization.

The medical members of the San Diego Radiological Assistance Team would be L

available, however, and additional assistance would be rendered by the Los Angeles based Radiological Assistance Team should it be necessary.

O 4-9

j i.

4 d

4.4.

COORDINATION VITH PARTICIPATING AGENCIES l

Training is provided to the participating agencies. This training is usually a simulated accident with simulated accident victims. A scenario 1

j is prepared and the participating agencies are requested to take part as f

players or observers.

Approximately once each year, senior members of the participating agen-cies are invited to General Atomic Company for a program update.

'i t

{

t I

i-I A

i i

?

I h

9 1

i T

,I 4-10 l

}

s, U

5.

RADIOLOGICAL CONTINGENCY MEASURES.

5.1.

Aa IVATION OF RDIOLOGICAL CONTINGENCY RESPONSE ORGANIZATION The Emergency Coordinator is responsible for activating the radiologi-1d1 Contingency personnel for each Class of radiological Contingency as defined in Section 3.1.

5.2.

ASSESSMENT ACTIONS 7or each class of emergency the radiological contingency personnel will determine the extent of the problem assisted by the applicable facility per-sonnel.

5.3.

CORRECTIVE ACTIONS The response actions that will be taken will be determ.4ed by the facil-ity and extent of the ettergency.

5.4.

PROTECTIVE ACTIONS

%e nature of protective actions and the criteria for implementing ac-tion are discussed in the following sections.

5.4.1.

Personnel Evacuation from Site and Accountability, Where criticality alarms are involved, personnel ovacuation routes and reassembly areas are specified. Health Physics personnel check the af-facted areas and radiological monitoring of evacuees is handled by trained individuals. Decontamination and selection for medical attention are done by GA personnel 01.P. and 1!edical Dept.).

5-1

a 5.4.2.1, On-Site Personnel In the event of an incident, the safety of personnel is the primary con-sideration of the emergency staff. Evacuation of all personnel not directly involved with emergency operations will, in most cases, provide adequate pro-tection. The site is sufficiently large that evacuation from any facility can be accomplished by utilizing facilities not affected. Shielding from radiation associated with a nuclear incident can be provided on~the site by using features of the natural terrain.

5.4.1.2.

Routes The primary evacuation routes and control points have been established and posted. Alternate routes and control points would be designated by the emergency coordinator if required.

(

5.4.1.3.

Off-Site Personnel An incident which would create radiation' levels sufficient.to become a health hazard to individuals at an off-site location is improbable. Should an incident occur, however, which could possibly create any external or i

internal radiation hazard to the general public, they would be subject to evacuation as a precautionary measure.

i 5.4.2.

Use of Protective Equipment and Supplies l

The Health Physics Department maintains an emergency van with maintained and inventoried equipment such as radiation detection and measurement equip-ment, respirators and protective clothing.~ This vehicle has a radio communi-cations system and is kept in a central location.

O 5-2 l

l

4 1 V 5.4.3.

Contamination and control Measure Any unusual event involving radioactive materials is evaluated by the responsible Health Physics personnel and a determination is made on isola-tion and area access control on the basis of the applicable NRC linits for controlled and uncontrolled areas.

5.5.

EXPOSUF_ CONTROL IN RADIOLOGICAL CONTINGDICIES 5.5.1.

Emergency Exposure Control Program 5.5.1.1.

Exposure Guidelines The EPA Emergency Worker and Lifesaving Activity Protective Actions Guides (EPA 520/1-75/001) are the basic guidelines for exposure control I

in emergency situations. Lifesaving dose is limited to 75 rams whole body

)

and 25 rams where it is desirable to enter an area in order to protect facil-ities, eliminate further escape of effluents, or to control fires. The basic abs is to stay within the dose limits of 10 CFR Part 20 wherever feasible.

5.5.1.2.

Radiation Protection Program I

The Emergency Coordinator with the advice of Health Physics personnel will authorize workers to receive emergency doses.

5.5.1.3.

Ibnitoring GA has Health Physics personnel on duty whenever work with radioactivity is in progress. Monitoring instruments, dosimeters, wipes, as well as the I

Health Physics Counting Room are available whenever needed. An in-vivo total body counter is also available onsite. Records are kept of any measurements made.

O 5-3

i.

5.5.2.

Decontamination of Personnel Any contaminated individual is decontaminated to natural background.

Any seriously injured personnel are transported to the hospital in the com-pany of Health Physics personnel. Lifesaving takes precedence over decon-tamination.

5.6.

MEDICAL TRANSPORTATION CA maintains its own onsite ambulance which is used for transporting injured personnel who may be contaminated.

Concercial ambulance service, in-cluding paramedics, is also available.

i t

5.7.

MEDICAL TREATMENT Arrangements have been made with Scripps Memorial Hospital to treat con-taminated or irradiated accident victins.

(

l 1

1 1

J 4

5-4

+

i

..--,._-r_.-..-,-.,

y...,,,,,,.....

, _.. - - -, ~..,_ _ _,....., _ _ _...

. - _ - ~-

c 1-

) [)

V i

6. -EQUIPMENT AND FACILITIES 6.1.

CONTROL POINT The principal emergency control point for radiological emergencies is the Health Physics Laboratory which has communications links with the other onsite emergency facilities and vehicles.

6.2.

EMERGENCY C0121UNICATIONS NETWORK Emergency communications at GA consist of telephone, FM radio, evacua-tion alarms, and sound power horns and public address systems on emergency vehicles.

1 i

6.2.1.

Telephone Extension 2000/2001 are the emergency numbers at GA.

These telephones are uniquely connected to the Control Center, Medical Department Safety (Fire) Department, and Health Physics Department.

6.2.2.

Radio

,1 f

GA maintains a private line, frequency modulated radio network for i

emergency communications. This radio communications network has fixed l

l station transmitter / receivers in the Control Center, Medical office, Health l

Physics office, Safety (Fire) office, and the Security stations. Mobile transmitter / receivers are available to Emergency Support groups, This 1

i system is routinely used and tested on a daily basis.

A i

i O 6-1

l f

I.. -, _.,. _ _,,.. _. _,, _, _ _ _.,..,, _ _.. _ _ _ _. - - -.. -. _, _. _ _ _ _. - - _. _ -

6.2.3.

Public Address System Public address systems are installed on the Health Physics and Fire -

Department emergency vans. Portable power sound horns are available on the fire truck and at the Control Center.

6.2.4.

Alarms 6.2.4.1.

Criticality Each facility that uses or has authorization to use fissionable material has ra?.iation sensing devices that automatically alarm at the preset level as required by 10 CFR 70.24.

These monitors activate klaxon horns which are audible throughout the interior and exterior of the particular facility.

Each of these monitors is connected to a separate alarm at the Control Cen-ter which identifies to the Security Supervisor the facility and area af-A fected.

6.2.4.2.

Fire i

All facilities at GA are equipped with fire alarm systems which code into the Control Center. These alarms may be activated manually or by heat sensing devices, special detectors, or the activation of the sprinkler system.

I s

6-2

.~

O

\\

/

U 6.3.

FACILITY FOR ASSESSMENT TEMIS Adequate laboratory and office space exists on the site for use by staff assigned to post-accident and recovery assessment and protective action func-tions.

I i

6.4.

ONSITE MEDICAL FACILITIES See Section 4.1.5.3. for a discussion of the onsite medical facilities.

Supplies and equipment routinely on hand for emergency first aid are given below:

For team personnel:

Identification tags for injured persons (on which will be listed the I

victim's name, nature of injuries, contamination information, res-cuer's initials, and the date and time).

Dust respirators with suitable filters. Extra filters should be pro-vided.

f t

f a

l l

l 6-3 I

l L-

/^\\

"]

6.5.

DIERGENCY MONITORING EQUIPMENT 6.5.1.

Health Physics Department The Health Physics emergency vehicle has a custom designed interior which carries all major necessary items of equipment for cc.,,ing with a major nuclear emergency. This equipment includes, but is not limited to, self-contained breathing apparatus, portable air samplers, portable radiation monitoring equipment, and the necessary protective clothing for members of the emergency team. Health Physics also maintains an environmental survey vehicle equipped with a 70 W transmitter / receiver. A 2.5 kW gasoline powered portable generator is available to be towed by the survey vehicle.

Other monitoring equipment is available from onsite operations which can be shutdown or are not critical to the-operation. The use of this monitoring equipment would depend on the extent of the emergency.

OU Maintenance and calibration of monitoring equipnent is done on a rou-tine schedule determined by past experience and manufacturers ~ specifications.

This maintenance and calibration of the monitoring equipment is a license required activity.

A typical inventory of emergency monitoring equipment and supplies is given below:

Ob 6-4

m

(%.)

\\

Anticontamination clothing (per team member):

1.t:5 Coveralls (anticontamination)

Gloves (rubberized)

Shoe covers (rubber)

Head covers (hoods)

Self-contained breathing apparatus 2-inch masking tape (Additional quantities of anticontamination clothing may be kept in large plastic bags placed near the control point, main gate, etc.)

Radiation Detection Instruments and Accessories (per team)

Item Alpha detection instruments Low-energy gamma detector Low-level beta-gamma detectors Head phones High-level beta-gamma detectors (at least 1000 R/hr full scale)

Air samplers Filter paper (Whatman No. 41)

Dosimeter charger Dosimeters (0-200mR and 0-200 R)

Neutron activation detectors, (indium foils)

Flashliebts with batteries Spare flashlight batteries O

6-5

O Area and Personnel Control Equipment Item Health Physics handbcok (with reference tables)

Notebook Retractable pens Grease pencils Area access leg Survey log Survey grid map Rand-McNally Road Atlas (U.S. A.) or equivalent (for offsite monitoring)

Telephone list for control and evaluation point (s)

Nasal swabs Swab containers

~'%

Smear papers Envelopes for samples Reel of barricade ribbon (bright color, 5000 feet)

Contaminated material stickers Radiation area signs Large plastic bags First aid kit Antifog solution Radiation signs:

j Caution: High Radiation Area.

Caution: Radiation Area.

f Caution: Radioactive Materials.

l Caution: Airborne Radioactivity Area.

l l

t I

l f

6-6

=.

t

'500 feet of rope.

Personnel dosimeters and dosimeter charger,-200 mR and 200 R levels.

j Ilashlight and batteries, screwdriver, pocketknife, pliers.

Scissors Clean clothes Blankets Foot covers Cloth or plastic bags - large Tags and gunned labels I

Crayons, pencils, and chalk Notebook, paper 1-pint and 1-quart containers Swabs, cotton with envelopes

(

Survey meters:

Pcrtable beta-gnm a <tsvey meter Portable alpha detector Portable air sampler i

Extra batteries for each instrument. Extra Geiger-muller tubta.

Screwdriver I

i l

I l

l l

t l

l I.

I i

I 6-7

O 7.

MAINTEN/.NCE OF RADIOLOGICAL CONTINGENCY PREPAREDNESS CAPABILITY 7.1.

WRITTEN PROCEDURES A manual of " Emergency Procedures" has been published at GA to guide the etercene.y staff in handling emergencies. Members of the emergency ore ganization are issued a copy of this manual.

7.2.

TRAINING 7.2.1.

Operating personnel All individuals at GA who routinely work with radioactive material are Q

required to attend a Radiological Safety Course and pass an examination at

\\d the ead of the course. Typical course content is as follows:

1.

Definitions and Units of Radiation Dose and Quantity of Radioactivity.

2.

Types of Radiation, etc.

j 3.

External Radiation Hazards 4.

Internal Radiation Hazards 5.

Biological Effects of Radiatics 6.

Permissible Exposure Levels 7.

Protection from External Radiation a.

Time b.

Distance c.

Shielding 8.

Fatection from Internal Radiation a.

Dtclose the Source b.

Enclose the Individual 9.

Contamination / Decontamination u) 7-1

9 10.

Protective Clothing and Equipment a.

Purpose and Use b.

Demonstration c.

Limitation 11.

Criticality 12.

Radiation Instrumentation a.

Use of Radiation Survey Instruments (1) Maintenance and 0411bration (2) Operation (3) Limitations b.

Radiation Survey Technigru; Using Sources c.

Characteristics and Use-of Personnel Monitoring Equipment (1) Film Badges (2) Self-Reading Pocat Dosimeters (3) Finger F. tin Badges 13.

10 CFR 19, 20, Regulatory Guides, Title 17, CAC.

14.

Respiratory Protection a.

Self-containc.d Breathing Apparatus (1) Policy and Procedures (2) Fitting and Use i

7.2.2.

CA Emergency Organization Personnel in the emergency organization receive on-the-job or addi-tional specialized periodic training particular to their discipline.

1 7.2.3.

Non-GA support personnel Off-site support organizations or personnel are periodically briefed on site activities.

\\

=,

.i 7-2

7.3.

TESTS AND DRILLS 7.3.1.

Evacuation Evacuation drills cre conducted at each facility that uses special nuc-lear material. The f.nterval between drills is dependent on the inventory of material te do;c not exceed six months.

7.3.2.

Other Fire drills are conducted periodically at each facility.

Special drills are scheduled

't various times to provide training for the emergency organi-zation in ig g menting procedures for incidents at GA.

7.4.

REVIEWING AND UPDATING OF THE PLAN AND PROCEDURES The primary Emergency Coordinator is responsible for an annual review and updating of the Emergency Plan and a semiannual review and updating of the Emergency Procedures.

The t:sual method of updating will be to publish revision pages for distribution to all holders of the GA Emergency Plan and Emergency Pro-cedures Manual.

7-3

O 7.5.

IfAINTENANCE OF INVENTORY OF RADIATION DIERGENCY EQUIPM21T The schedule for maintenance and inventory checks for equipment and supplies required for responding to a radiological contingency will be:

1.

Radiation detection it. ruments will be operationally checked monthly, inventoried quarterly, and calibrated quarterly.

2.

Auxiliary lighting vill be checked quarterly.

3.

Protective breathing equipment and protective clothing will be checked quatterly for proper function and intact inventory.

4.

Other supplies designated for emergency use will be checked quarterly.

5.

All equipment and supplies will be immediately replaced or re-paired if found missing from the inventory or not functioning properly.

6.

Essential emergency equipment will be kept secured to prevent pilfering and misappropriation.

~~

I l

l l

l 7-4

s.

8.

RECORDS AND REPORTS 8.1.

RECORDS OF INCIDENTS-Records of radiological contingencies as defined-by the classification system of Section 3.2.~ will~ be retained until the license is terminated.

The records will include at least the following:

1.

The cause of the event. This record will include both the direc't cause as well as any indirect cause.

2.

The extent of any injury and/or damage.

3.

Radiological data such as area surveys, effluent releases, calcu-lated and measured doses, and contamination measured on surfaces and personnel.

4.

The number and type of personnel and/or equipment irvolved.

5.

The corrective action taken to terminate the event and an iden-tification of personnel responsible for making those decisions.

6.

The offsite support assistance that was requested as well as ac-tual assistance received.

7.

The extent to which response equipment was used.

8.

The dates and times that any accident situation is reported off-site and the names of organizations and individuals contacted.

/N 9.

The personnel and their titles who are designated to be respon-sible for maintaining records will be identified.

8-1

. ~

._._., =. _._.

'tV 8.2.

RECORDS OF PREPAREDNESS ASSURAliCE Records will be kept confirming that preparedness is maintained to respond to radiological contingencies. The following records vill be kept:

hcords of training (including the type and time spent during the training, and names of individuals trained).

Records of drills and tests (including the results' of critiques and l

any consnitment to change the plans).

Records of inventories and locations of emergency equipment and sup-plies.

Records on_the maintenance, surveillat:e, and testing of equipment.

and supplies.

Documentr ion of the reviews and updates of the radiological contin-gency plan, as well as any personnel changes.

8,3.

REPORTING ARRANGDH2iTS I

The Emergency Coordinator is responsible for reporting accidents and reporting to local, state, and federal agencies. The Director of Public Rela.on is responsible for reports to keep the public informed.

I J

8-2

. - _ _ _ _ _,. _... _..,.. _ ~,...

m 9.

RECOVERY The procedures for recovery and re-entry in the event-of an emergency situation are as follows:

1.

A complete analysis of the circunstance leading up to and re-sulting from the situation, together with recommendations to prevent a recurrence, shall be prepared by Criticality and Redi-ation Safeguards Committee.

2.-

Although an emergency situation transcends the normal require-ments of limiting exposure, there are suggested levels for ex-posure to be accepted in eLergencies. However, every reason-able effort to minimize exposure must be made, even in emergen-cies.

a.

Four categories of risk versus benefit must be considered:

Saving human life.

Recovery of the dead.

Protection of healtn and safety of the public.

Protection of property.

b.

In order to avoid restricting actions that may be necessary to save lives, it shall be lef t to the judgment of the Emer--

gency Director to determine the amount of exposure that will be permitted in order to perform the emergency mission. How-ever, in no case will the exposure be permitted to exceed 75 rem.

OG 9-1

s d

c.

In situations where the bodies of accident victims are in areas inaccessible because of high radiation fields, special planning and remote recovery devices should be used to re-trieve the bodies. Expccure of recovery: personnel should not exceed 12 rem.

d.

When emergency en-site action is necessary to reduce a hazard potential to acceptable levels or to prevent sub-stantial loss of property, an exposure up to 12 ren may be received by participating individuals. However, volunteers, under special circunstances,.may receive up to 25 rem expo-sure.

When the risk of hazard is such that life would be in jeopardy or there would be severe effects on the health of the public, volunteers may receive up to 75 rem.

e.

Once the hazard potential has passed, steps shall be taken to recover from the incident. All actions shall be preplanned

(

in order to limit exposures. Areas will be roped off and posted with radiation levels and stay times based on results of surveys. During any plant restoration operations person-nel exposures to radiation will be maintained with 10 CFR Part 20 limits and as low as can be reasonably achieved.

Portable shielding material should be used whenever possible.

Access to the area shall be controlled and exposures of per-sonnel documented.

f.

The Criticality and Radiation Safeguards Committee shall be the designated technical group responsible for evaluating re-entry advisability depending on existing conditiens.

j s

9-2 i

n 4

I g.

Current operating records and other essential information necessary for evaluating the emergency shall be readily available.

i h

Site documents and plans which may be necessary for recovery /

1 t

re-entry may be obtained from Facilities Engineering.

1.

Vehicles or equipment which may be needed to effect recovery /

re-entry are also available from Facilities and Plant Engi-neering.

t J

a f

l M

i 4

a f

f a

1 3

1 i

i 4

4 i

9-3 1

i

I "M

. y,3 Y, UG. i M.:. '1 Wa'Enfk -M WT:W f

M.'r'.nF'. "r

.i < 7_7 ~~i' Ld?T ' '

':.".~~^

A'

_i""_

V-i,L {'j u a.

O l

,,-.t.,

% 51 y

l e.e w

.ENE RAL ATOVihe**~~ daw **wa

- e-*e- * ~ *~~~-+~ e e **rm" I

_._.. _,,,... _ -r

. u ;z _,,.,,,_,;,.

\\>>,

f.'-

l

>l

.f

, s "

ggg y

3.,

.=. c

- g)y_

4,

' gj. jp li

.94

~.

• (-ke I

{ ~

4 s

_,_y "% 9: v9,._y[.?"

_ _f:.. @,

ti

~L

';/:

~,;g; ;-

l

.'. y, %g y :.;W' A' ll,. g ?0 1

~_ y ', 9' 1

.,; y '

.? --.: s,.

.a

~. ' -

8 M.