ML20041G014

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4420 Re Notification of Unusual event,HNP-4520 Re Alert & HNP-4526 Re Alert Emergency - Rally Point Leader

ML20041G014
Person / Time
Site:	Hatch
Issue date:	03/01/1982
From:	GEORGIA POWER CO.
To:
Shared Package
ML20041G012	List: ML20041G011 ML20041G014
References
PROC-820301-07, NUDOCS 8203190027
Download: ML20041G014 (30)

Text

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GEORGIA PCWER CONPANY HATCH NUCLEAR PLANT PROCEDURE Not i f i cat i on _ o f I.fnue;ua l _ Eyent PROCEDURE TITLE HNP-44?O PROC 500R5~sUMBER

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Lab RESPONSIBLE SECTICN SAFETY RELATED ( X )

NON-SAFETY RELATED (

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NOTIFT

.dN OF UNUGUAL EVENT, A.

CLASS OFSCRIPTION in process or have occurred which indicate a Unusual events are level of safety of the plant, such potential degradation of the releases of redioactive material as those noted in Table 1.

No or monitoring are expected unless requiring oifsite response further degradation of safety systems occurs.

B.

P_U3r!OSE is to (1) assure that the first Purpose of offsite notificationfound to be necessary has been carried later in any response step and bring the operating staff to a state of readiness, (2) out, provide systematsc handling of unusual events information and (3) decision making.

s C.

PLANT ACTICNS NOTE The Shift' Foreman or Shift Supervisor (or higher ranking licensed or certified person present) in consultation with the STA, if feasible, recognizes and declares that the plant is in a state of The Shift Supervisor emergency of Unusual Event Class.

assumes the role of Emergency Director until relieved by the. Plant Manager or his designee.

1.

Inform State and/or local offsite authorites of the nature of the unusual condition within 15 minutes following recognition.

2.

Augment on-shift resources as needed.

3.

Assess and respond.

4.

Escalate to a more severe class, if appropriate.

C3 5.

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

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STATE ANDjCR LOCAL CEESJ.TE_AtJTHCRITY ACTTCN9 1.

Provide fire or security assistance, if requested.

2.

Escalate to a more severe class, i f appropriate.

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Stand by until verbal closeaut.

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INITf AT!!:*, C0';DITIC't

,tryj!PtaFMT STAf tts PARAMETf R YAtt'C_

1.

[CCS inttf ated and discharged to vessel Auto inttf ation of:

' 146.5 inches or 2 psig Core spray, or drywell pressure PJUt (LPCI mode)

-146.5 inenes or 2 pstg drywell pressure -

2.

Radfological effluent tecMical specif t-Main Stack and Reactor Bldg Exceeding ETS 2.1.34 Vent monitors Hi alarm plus cation limits escceded sonitor readings 4

t.lquid Itadwaste Effluent H1 Exceeding ETS 2.1.1a alarm plus monttor readings 3.

ruel dmage indication

s. High off gas at pretreat monitor Pretreat Montter HI Hf alarm 500.000 p Cf/see plus monitor readings corresponding to 16 isotopes decayed to 30 minutes; or an in.

• crease of 100.000

. p Cl/sec within a JO

' minute period.

Lab sample significantly greater

>100 :: Cl/93

b. lifgh ccolant activity sarrple than limit for normal cperating of 1 1J1 equivalent I-131 cquivalent Reactor Yessel litgh Pressurc y,1200 pstg 4.

Ahr.orr.s1 reacter pressure l

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4 of 7 See Titto Pa<tc TABLE 1 (CONT.)

NOTIFICATICN OF I tN'EUA!. FVENT ffyJfPMENT SThTtfS_

PARAMETFR Valt>E

_fritTt ATINF. CO*:DIT!0'1 5.

ft.flure of a rain steas 11ne relief Failure of valve to close Torus and/or CW pressure increase vd*se to close following a reduct'en of Terus Temp >110 F 0

4,ig 11 cal.1e pressure Torus Level Hign >153 in.

Safety Relief valve Tail 0

Pipe Temperature Hign >230 F G.

Loss of offsite pewc: or loss of onsite AC 500 arid 230kV system failurd Zero voltage on all in-cor.is.g out: tde I f rcs or

/ poser capability Loss of all energency diesel zero voltage inoicated on all 4.16 kV buses 4

generators j

7.

Loss of contairment integrity recuiring loss of Primary or Secondary See Table la shutdown by technical specifications Contairment Integrity Shif t Supervisor's 8.

Fire within the plant lasting more than 10 fire alarst and observation

. judgement minutes Shif t Supervisor's judge-Observation or valid initiation awnt based on advice of 9.

$ccurity threat or attempted entry or of security alarms Security Shift Superviscr attenpted sabotage Shif t supervisor's 10, ristural phenomenon being experienced or Ctservation or notification -

Judgement projected beyond usual levels.

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NOTIFICATION OF i1.' UsttAl. FVENT IfifTI ATINP. CO*lDITIC!i EQUIPt'ENT STAT 115 PAtutETTR VAtt'!

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a. Any carthquake felt inplant or detected Observation or -

Any finite ceasurement on plant seismic instrumentation Unit 1: Seismic Instrument Triggered alam

!! nit 2: Seismic Switch Tripped alann

b. Any tornadn onsite causing significant

'Chservation damage affecting plant operations C. I.r:y liurri..ane onstte causing significant Observation

>75 eph damage af fectin1 plant operations

d. 50 year (Iced causing significant drage Observation 183.6 ft. f:5L affctting plant cperations

e. Lovt river water Unit 1: Intake Screen or Low Water

~<62.4 f t M5L alam plus observation of level indicators Unit 2: Plant Service Water Intake Structure Low Level alar::i plus observation of level.

Indicators

11. Other hazards being experienced or projected Shift Supervisor's

a. Aircraft crash onsite or unusual aircraf t Cbservation activity over factif ty

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NOT II ICAHON OF UNUSUAL EVENT E!LfAT!hr.C0!;3ITICM EQU!PPENT STATUS PAR /NETER VAtt!E

. !,fonificant onsite texte gas release Chlorine alarm in Chlorine Oldg.

Rupture of chlorine cyltader or ch brine system piping or

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cbskrvation Stanificant onsite flammable gas Observation release

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d. Turbine rotatinq ca.echent failure Turbine trip. turbine internal causir.1 rapid plant shutdewn damage

,12.

0:me p! nt conditions ext:t which Exceeding any safety limit as Shift Supervisor's w rant tr. creased awareness on the required in technical specifica-judgement p..e t of it e plant operating staff er tions i,t te ant /or local of f site authorttles 2

D.

Tr.:nsportation of conta itnated injured High contamination to injured

>10.000 dpc/100cm fontividual frois site to of fsite hospital individual s

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PARAMETER VALLtE FOR LOSS OF CONTAINMENT INTEGRITY REGUIRING SHUTOOWN BY TECHNICAL SPECIFICATIONS Unable to meet one of the following requirements,within time limit set forth by technical specifications:

1 1.

All non-automatic containment isolation valves on lines connected to the reactor coolant system or containment which are not required to be open during accident conditions are closed.

These valves may be opened to perform operational activities.

2.

At least one door in the personnel airlock is closed and sealed.

3.

All automatic containment isolation valves are operable or deactivated in the isolated position.

4.

All blind flange and man ways are closed.

5.

At least one door in each access opening is closed.

6.

The standby gas treatment system is operable.

All automatic ventilation system isolation valves are operable 7.

and are secured in the isolated position.

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PROCEDURE

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SAFETY RELATED ( X)

NON-SAFETY RELATED (

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CCNDITIONS indicate a in process or have occurred which Unusual events are of safety of the plant, such potential degradation of the level tJo releases of radioactive as those noted in HNP-4420, Table 1.

expected material requiring offsite response or monitoring are unless further degradation of safety systems occurrs.

B.

REFERENCE HNP-4420.

C.

6C_ TION 1.

Proceed to control room immediately.

correct operator action has been taken to bring 2.

Ensure that emergency under control.

3.

Evaluate conditions and findings of the control room operator to see if a more severe emergency class should be declared.

Refer to criteria in HNP-4520, 4620, 4720, 4850, 4851 procedures.

j by notifying Health 4.

Activate rescue team if necessary, Physics.

5.

If acting as Emergency Director, establish communications l

with Plant Management as soon as possible.

I Direct on-site actions to bring emergency under control.

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NCN-SAFETY RELATED (

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See Title Paqe 1 of 1 NOTIFICATION OF UN!JSUAl EVENT-SHIFT SUPFRVISOR m

A.

CONDITION Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant, such as those noted in HNP-4420. Table 1.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

B.

REFERENCE HNP-4420.

_CTION C.

A 1.

Procede to control room immediately.

I 2.

Assume the duties as Emergency Director and take responsibility for overall management of emergency response until relieved by Plant Manager or his designee.

3.

Evaluate actions of Shift Foreman and operators to bring l

emergency under control.

4.

Afer consultation with Shift Foreman and Shift Technical Advisor determine if a more severe emergency class should be declared.

Refer to criteria in HNP-4520, 4E.20 and, 4720.

5.

The Shift Supervisor is responsible for notificction of l

Plant Management and NRC as per emergency call '.ist and I

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other offsite agancies in accordance with notification i

procedure HNP-4861.

The actual notification process may be delegated to other, specifically trained, shift personnel.

6.

Augment on shift resources as needed to assess and respond i

to the event.

7.

Close out after the emergency with verbal summary to offsite authorities; followed by written summary within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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PRDCEDURE Al.FRT

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HNP-4520 PROCEDURE NUMBER.

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SAFETY RELATED ( X )

NCN-SAFETY RELATED (

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CLASS DESCRIPTTON Events are in process or have occurred which, involve an actual or potential substantial degradation of the level of safety of the plant such as those noted in Table 1.

Any releases are expected to be limited to small f ractions of the EPA Protective Action Guideline (PAG) exposure levels.

P RPOSE J

B.

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

C.

PLANT ACTIONS NOTE I

The Shift Foreman or Shift Supervisor (or higher ranking licensed or certified person present) in consultation with the STA, if feasible, recognizes and declares that the plant is in a state of emergency of the Alert Class.

The person declaring the emergency assumes the role of Emergency Director until relieved.

g 1.

Inform State and/or local authorities of alert status and l

reason for alert within about 15 minutes.

2.

Augment resources and activate Technical Support Center (TSC) and Operations Support Center (OSC).

Bring Emergency I Operations Facility (EOF) and other key emergency personnel to standby status.

l 3.

Assess and respond.

4.

Mobilize onsite monitoring teams with associated i

Communications.

5.

Provide periodic plant status updates to offsite authorities I

l (at least every 15 minutes).

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

7.

Escalat,e to a more severe class, if appropriate.

B.

Close out or reduce emergency class by.Oerbal summary to offsite authoritic: 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 /> of closecut or class reduction.

D, STATE ANOfg3 LOCAL CFFSITE AUTHOR!TY ACTIONS 1.

Provide fire or security assistance if requested.

2.

Augment resources and bring primary response centers, NOAA weather radio, and EBS to standby status.

3.

Alert to standby status key emergency personnel including monitoring teams with associated comthunications.

4.

Provide confirmatory offsite radiation monitoring and ingestion pathway dose projections if actual release substantially exceed technical specification limits.

5.

Escalate to a more severe class, if appropriate.

6.

Maintain alert status until verbal closecut or reduction of emergency class.

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PARAMETER VAttJE_

- INITTATING CO.'iDITIO I Ef)UIPMENT STATIN "

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h. . Severe loss of fact cladding:

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a. high off gas at prc-treat monitor ',s, Pretreat Honitor ill ill I'.

~ >5 ti/sec alam plus monitor readings corresponding to 16 e

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isotcpcs decayed 30 talnutes Lab screple substantially greater '

>300 p C1/ga of

b. Very high coolant activity sample

' than limit for normal operating I-131 equivalent

l 1-131 equivalent Reactor 01d. ARM Ill alarm

>15 mr/hr fit 2.

- Steam line break outside containment with 9

Q a

Turbine Bldg. ARii Ill alam

>15 cr/hr

>200 F

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g significant f451V Icakage liigh flSL Tunnel Tempe:ature

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Drywell equipment and/or floor.

>$0 gpm U.2.

o 3.

Primary coolant leak greater than 50 spra~

Drain Sump 111 lit alarm Q2 O

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Anli's are off scale on high

. >10 mr/hr mh T

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liigh radiation levels or high airborne

, 'end and readings confimed 9.

contamination which indicate a severe

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degradation in control of radioactive Q

roterials 5..

Loss of offsite pcwcr and loss of all Undervoltage alams on al'14.16'. -. 4.16 LV buscs voltreeter

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o cnsite AC power (see la5Te 0-3 kV buses and loss of control, reading zero and failure

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roca normiT lighting and-of Diesel Generators output forextendedloss) inability to energize C16 breaker to close into 4.16 kV buses with Diesel Generators,

kV buses.

Loss of all onsite DC power (see T'able Loss of all Oc buses D-3forextendedloss)

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Corplete loss of any function needed '.

Loss of Shutdown Cooling !! ode of 2

3 z8 RllR and all cmcrgency core cooling 5

9 ?j N., --. s for plant cold shutd.w n 5,A systems

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fu tn5 Inability to shutdcun with Control yd3 Rods y

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' PARAMETE t VAttR '

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EOUIPMEt1T STATUS filITIATit:G C07:DITIC1 Reactor is indicated

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Valid scram signal and neutron critical by at 1 cast ene

8. ~ Failure of the reactor protection system count rate indicates reactor is of the following neute;.1 to inttfate and cc plete a scram which critical o

o brings the reacter subcritical conitoring sysicais:

SR!1. IR!ts, or API'!:s

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Fuel handling accident wtth release of Any of the.following plus confirmation by analysis of.

9.

' radioactivity to reactor butiding air sampic:

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>15 r.r/hr Refueling Floor ARM 111 alam h

Refueling Floor Vent Exhaust

• I,, ~ >20 r.r/hr T-2 lit 111 Radiation alarm s.

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Fire alam and observation,,

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Fire potentially affecting ECCS O

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Observation or failure in alam * '

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Most or all alams (annunciators) lost check or transient notice'd with

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out alam 3

Exceeding 10 times ETS.

' Radiological gaseous eff tuents great,er

.. !!ain Stack or Reactor Bldg.

2.1.3a Vent monitors lit til alara 12.

i thsp 10 tiees technical specification plus raonitor readings Shif t Supervisor's rinstantaneous limits y,, 3 Observation

.;13. t On poing security ccmproatse Judgement based on

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.A!.ERT(tontinued)

PARMETER VAtt!E_

1 fit!TTATIflG CC?m!TiO?l EQUIP!!EliT STATIG

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Shif t Supervisor's 14.

Severe natural phencmena being experienced judgement o

g ca co or projected:

a. Earthquake greater than 03E Icyc1

' Unit la Setsnic Instrument

>0.08 g j

j Triggered alam Unit 2: Seismic Switch. Tripped alam

b. ficod near design level liigh river water elevation 4100 f t !:SL

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c. !!urr! cane winds near design basis level liigh winds

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d. Tornado' striking factitty incurring Observation I i-4 y'.a.

.o reg damage affecting safety systems i-

$ r-U Unit 1: Intake Screen or Lcw '

- <61'.7 ft MSL 2m U

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e. Low river water trater alam plus dl-9 C

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observaticn of level indicators im r,a Structure Low Level alam lO

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D Unit 2: Plant Service flater intake

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15.

Other hazards being experienced 'or..

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a. Aircraft crash on facility Observation z,;

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b. tilssile tcpacts from whatever source on facility incurring damage affecting

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PARAMETER VALUE

. Tit!TTATIt:G C0';DITIO:1 EQUIPl:ENT STATUS

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c. Knot <n explosive damage to facility Observation affecting plant cperation

'd. Entry into facility er.virons of Control Roo:a Out' side Air Inlet,

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toxic or flar.uhle gases alarra m

O Ir-penetration

. casing l-t Q

g Turbine cociponents penetrating 8@

e. Turbine failure causing casing

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Other plant conditions exist that Observation Shift Supervisor's warrant precautionary activation of

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TSC and placing E0F and other key p8~

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c.erger.cy personnel on standby.

5 d

17.

Evacuation of control room anticipated Observation Shift Supervisor's, 6,

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3 systcas estabitsbed fro:a local I

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control rod drop accident

!!SL liigh Radiation alarg

., >3000 cir/hr

>120% full power '

2U APR!! Upscale Ti1p of 4.4 Channel: A and/or B

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HATCH NUCLEAR PLANT PROCEDURE

....e Actions for All Pere,onnel in Alprt

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PROCECURE T5TLE HNP-4921__

PROCEDURE NUMBER-Lab RESPONSIBLE SECTION SAFETY RELATED ( X 3 NCN-SAFETY RELATED (

)

.-------------_---_--__---_a__--_-__---_---_..--_-_---_-_-_---.

APPROVED APPROVED REV.

DESCRIPTION DEPT.

PLANT DATE HEAD MANAGER 3

Pages 1 &2 M

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..m.o See Title Pace 1 of 3 ACTIONS FOR ALL PERSONNEL IN ALGRT A.

CONDITIC.NS Events are in process or have occurred which involve actual or potuntial substantial degradation of the lev'el of safety of the plant.

Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline (P.A.G.)

exposure levels.

B.

REFERENCES HNP-4520 C.

ACTION 1.

Persons discovering an emergency condition shall immediately' notify the, Control Room by the most expeditious means avail-able.

2.

As soon as an emergency. condition of the Alert Class is con-firmed, Control Room Operators shall announce the nature of the emergency on the public address system and specify that personnel initiate Alort procedures.

3.

Control Room Operators shall place the plant in a' safe con-dition as the emergency warrants.

4.

If possible, person (s) in immediate area take appropriate rapid action to limit the extent of the incident with available means, and then retreat to the rally point.

5.

Persons involved in radiation incidents report to Health Physics at Security or at Operations Support Center as soon as possible after decontamination for further evaluation of dose received.

6.

Persons called in from offsite should report to their assigned locations and, if unassigned, to the Operations Support Center for assignments.

7.

If the emergency occurs during a regular day shift, members of the plant operating organization on site will report as follows:

a.

Control Room Operations Supervisor - All onshift operators, Shift Foremen. shift Supervisor, and Shift Technical Technical Advisor.

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Emergency Operations Facility,

( Af't e r checking through the-cally point:)

Assistant Plant Manager. HP Superintendent, three RET members, and four communicators.

c.

Technical Support Center (TSC)

Assistant Plant Manager Superintendent of Plant Engineering and Services Superintendent of Maintenance Superintendent of Operations Reactor Engineer Engineering Supervisors Laboratory Supervisor (Health Physics)

Four Communicators d.

. Operations Support Center (OSC) 1 Shift Supervisor or Foreman 1 Maintenance Supervisor 1/2 crew instrument technicians w/ foreman (pre-designated) 1/2 creu electricians w/ foreman (pre-designated) 1/2 crew mechanics w/ foreman (pre-designated)

All RET members 4 laborers w/ foreman (pre-designated) 8.

Personnel assigned to work locations outside the protected area and who have not been assigned to the Control Room.

TSC, OSC, or ECF will remain at their work location and await further instructions.

9.

Members of the Radiological Emergency Team report to the OSC if on site when the emergency begins.

If team members are called in, they report to the CCC for ass gpmgtt4s

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Georgia Power c.A o

3 of 3 See Title Page 10.

Members of the plant organization and contractors inside the protected area and who do not have specific emergency assignment locations, go immediately to your report area, or Instru-i.e. Maintenance Department to Maintenance Shop ment Shop, Administration Department-to Service Building offices, contract workers to contract office areas, Ware-house workers to Warehouse area, etc.

Remain in these areas until further instructions are given.

11.

Members of the plant organization will comply with appli-cable procedures to effect orderly coordinated actions in the emergency.

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GEDRGIA PO'RR CCMPANY HATCH MUCLEAR PLANT.

PROCEDURE

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_- SHIFT FORFMAN ALERT PRCCEDURE TITLE HNP-4523 PROCEDURE NUMGER

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LAB RESPONSISLE 5ECTICN

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SAFETY RELATED ( X )

NON-SAFETY RELATED (

)

..-_--------_--_--.a_--_

APPROVdD APPROVED REV.

DESCRIPTION DEPT.

PLANT DATE HEAD MANAGER 3[g.7

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2 Page 1 1

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ALERT - SHIFT FOSFMAN r

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Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.

Any releases aregxpected to be limited to small fractions of the EPA Protective Action Guideline (P.A.G.)

exposure levels.

B.

REFERENCE HNP-4520 C.

ACTION 1.

Proceed to control room immediately.

2.

Ensure that correct operator action has been taken to bring emergency under control.

3.

Evaluate conditions and findings of the control room operator to see if a Site Area or General Emergency should be declared, based on performance of HNP-4850 and HNP-4851 and on criteria in HNP-4E.20 and 4720.

4.

Activate' Internal Survey Team by contacting Operations Support Center Manager when staffed.

Direct Internal Survey.

Teams to areas to be surveyed as appropriate.

5.

Activate Rescue Team as necessary by contacting Operations Support Center Manager when staffed.

6.

Establish communications with the Security Force, Technical Support Center, and Plant Management as soon as possible and discuss declaring a Site Area or General Emergency and/or the need for outside assistance.

7.

Direct onsite actions to bring emergency under control.

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CECRGIA PCWER COMPANY HATCH NUCLEAR PLANT PROCEDURE-e.

A ALERT EMERGFNCY - RALLY POINT LEACFR

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HNP-452E.

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PROcEc0RE NUMBER

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L__AB RESPONSIBLE SECTICN SAFETY RELATED ( X )

NON-SAFETY RELATED (

)

APPROVED APPROVED REV.

DESCRIPTION DEPT.

PLANT DATE HEAD MANAGER d'[~ g 3 /[8,L 2

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1 of 3 ALERT _EMERGFNCY - RALLY _ POINT _ LEADER A.

CONDITTON Events are in process or hcve occurred which involve an actual nr 4

pctential 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 Guideline (PAG) exposure levels.

B.

REFERENCE l@P-4520 C.

ACTION 4

1.

After the RET assembles in the OSC, the CSC Manager will send some RET members to.the Rally Point and designate a Rally Point Leader to take charge of the Rally Point.

2.

Have personnel gather at the Rally Point.

If personnel involved in the incident are present or anyone is dressed in protective clothing, segregate them from the others.

3.

Take survey meters and determine background of the Rally Point and proceed as follows:

a.

Dose rate less than 0.5 mr/hr or contamination less than 100 CPM above background.

(1)

Survey or have RET member survey pm sens involved

.in the incident first, those wearing protective clothing second, and then the remaining personnel at the Rally Point.

(a)

Have any person that is contaminated (greater than 100 CPM above Rally Point background) remain at the Rally Point, separated from the others, and notify the Health Physics Supervisor.

(3)

Begin decontamination and exposure evaluation of affected personnel as quickly as possible.

(a)

Set up change station.

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(b)

Supervise self-decontamination of personnel.

(c)

Using available information, estimato each person's exposure and record data.

(d)

Take TLD badges off persons involved in the incident.

Arrange for reading of the TLD badg'es.

(e)

Arrange for urine samples and nasal smears from persons involved in the incident to be taken.

Evaluate them as time permits.

(f)

Do not release any person who has received gre.ater than 25 rem whole body dose or is suspected to have ingested significant amounts of radioactive materials.

Such persons are to be taken to the hospital for examination and further evaluation of exposure.

(g)

Confer with the Emergency Director before l

releasing any personnel involved in the incident.

b.

Dose rate greater than or equal to 0.5 mr/hr or contamination greater than or equal to 100 CPM above background.

(1)

Notify Shift Supervisor of dose rates.

(2)

Proceed with everyone to an area outside the protected area where the dose rate is less than or equal to 0.5 mr/nr or contamination is less than or equal to 100 CPM.

(3)

Conduct or assist RET members in conducting individual surveys.

(4)

Any person that is contaminated (greater than or equal to 100 CPM above background) have him remain for decontamination and notify the Health Physics Supervisor.

Assist the H.P. Supervisor when time permits in performing step C.3.a.(3).

(5)

Release uncontaminated personnel to their emergency work locations.

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Do not release members of the Radiological Emergency Team except to go to the ECF until directed to do so by the Emergency Director or Shift Supervisor if the Emergency l

Director cannot be contacted.

5.

Assist in routing ambulance to pick up any injured personnel.

Assure ambulance driver and attendant are provided with TLD badge and pocket dosimeter on entry.

6.

Assist Emergency Director in bringing emergency under

{

control.

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