Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures S023-VIII-12 Re Unusual event,S023-VIII-13 Re Alert & S023-VIII-14 Re Site Emergency
	ML20039A621
Person / Time
Site:	San Onofre
Issue date:	12/01/1981
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML13308A020	List: ML13308A022; ML20039A621;
References
	PROC-811201-02, NUDOCS 8112180554
	Download: ML20039A621 (400)
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- SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2/3 O

EMERGENCY PROCEDURES 1981 1

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,0 L, J SAN ONOFRE NUCLEAR GENERATINr. STATION UNITS 2/3 EMERGENCY PROCEDURES S023-VIII-11 RECOGNITION AND CLASSIFICATION OF EMERGENCIES S023-VIII-12 UNUSUAL EVENT S023-VIII-13 ALERT S023-VIII-14 SITE EMERGENCY S023-VIII-15 GENERAL EMERGENCY S023-VIII-16 NOTIFICATIONS S023-VIII-17 ACTIVATION AND OPERATION OF EMERGENCY CENTERS AND ORGANIZATIONS S023-VIII-18 NDTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONNEL O

S023-VIII-19 NOT USED S023-VIII-20 NOT USED S023-VIII-21 NOT USED '

S023-VIII-22 SOURCE TERM DETERMINATION S023-VIII-23 DOSE ASSESSMENT S023-VIII-24 DIRECTION OF ONSITE EMERGENCY MONITORING S023-VIII-25 DIRECTION OF 0FFSITE EMERGENCY MONITORING S023-VIII-26 RECOMMENDATION FOR OFFSITE PROTECTIVE MEASURES S023-VIII-27 EMERGENCY ENVIRONMENTAL MONITORING S023-VIII-28 NOT USED S023-VIII-29 NOT USED S023-VIII-30 NOT USED 1

S023-VIII-31 EMERGENCY EXPOSURE CONTROL d("%

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'O S023-VIII-32 LOCAL EVACUATION AND ACCOUNTABILITY S023-VIII-33 PLANT EVACUATION AND ACCOUNTABILITY S023-VIII-34 SITE EVACUATION AND ACCOUNTABILITY S023-VIII-35 TRAFFIC AND ACCESS CONTROL 4

S023-VIII-36 THYR 01D PROPHYLAXIS S023-VIII-37 FIRE FIGHTING S023-VIII-38 CONTAMINATED INJURY ,

S023-VIII-39 RESCUE S023-VIII-40 NOT USED S023-VIII-41 ONSITE MONITORING S023-VIII-42 0FFSITE MONITORING AND SAMPLING O- S07 S023-VIII-43 SAMPLE C00RDINAT:'ON DURING AN EMERGENCY S023-VIII-44 EMERGENCY CONTAMINATION CONTROL i

i S023-VIII-45 PERSONNEL AND VEHICLE MONITORING S023-VIII-46 ONSITE SAMPLING S023-VIII-47 NOT USED

! S023-VIII-48 NOT USED S023-VIII-49 NOT USED S023-VIII-50 NOT USED S023-VIII-51 RECORD KEEPING S023-VIII-52 NOT USED S023-VIII-53 NOT USED S023-VIII-54 NOT USED S023-VIII-55 NOT USED l

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'O 5023-VIII-56 NOT USED S023-VIII-57 NOT USED S023-VIII-58 NOT USED S023-VIII-59 NOT USED S023-VIII-60 NOT USED S023-VIII-61 RE-ENTRY S023-VIII-62 ACTIVATION OF THE RECOVERY ORGANIZATION S023-VIII-63 NOT USED S023-VIII-64 NOT USED S023-VIII-65 NOT USED S023-VIII-66 NOT USED .

() S023-VIII-67 NOT USED S023-VIII-68 NOT USED S023-VIII-69 NOT USED S023-VIII-70 NOT USED S023-VIII-71 EMERGENCY DRILLS S023-VIII-72 EMERGENCY KIT INVENTORY S023-VIII-73 EMERGENCY PLAN MAINTENANCE S023-VIII-74 EMERGENCY PLAN TRAINING I

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EMEKENCY PIOCEIXJRE S023-VIII-11 SAN CNOFRE NUCIEAR GCERATING STATION u Page 1 of 4

%' REVISICN 1 UNITS 2 AND 3 OCT 2 21981

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ION'AND CIASSIFICATION OF EMERGENCIES

1. OELTECTIVE AND RESPCNSIBILITY 1.1 h is procedure describes the immediate actions to be taken to recognize and classify the four energency classifications; Unusual Event, Alert, Site Emergency 4

and General Emergency.

1.2 he Emergency Cbordinator (Watch Engineer, until properly relieved) is responsible for implementation of the actions prescribed in this procedure. He may delegate responsibility for performance of the prescribed tasks except where specifically foroidden in this procedure.

2.0 gFERmCES RECEIVED 2.1 SofG-2 & 3 Emergency Plan. OCT 221981 2.2 SONGS-2 & 3 Operating Procedures. CDM SITE 2.3 Title 10, Code of Federal Regulations Part 50, Appendix E.

2.4 NUREU-0654/ FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Dnergency Ibsponse Plans arrl Preparedness in Support of Nuclear Pcwer Plants.

2.5 SOtCS-2 & 3 Health Physics Procedures.

2.6 SCNGS-2 & 3 Emergency Procedures S023-VIII-12, -13,

-14, -15.

2.7 SCN'3S-2 & 3 Tech Specs.

3.0 PREREUJ ,

3.1 off-no qD 'Tesponding to one of the initi-ihV ' ent 8.1, " Action Level ti ~ 'a

'Y neergency cdtriitions",

0#r ye by ' . redurdant inst cff{ i.

O ari j'o other elated nlant ard f eld measuremeru',

parameters, phye ,Eg as applicable. '" /gg 4.0 PRECAUTIONS 4.1 Continued surveillance and assesment of plant conditions is necessary to ermre that the emergency classification

' ] is aIpropriately revised as conditions change, or as nore definitive information is obtained.

N PN (d SAN (NOFFE NOCLEAR GE2ERATItG STATION UNITS 2 AND 3 e

f 4.2 Wis emergency procedure does not replace any plant operating procedures. During an emergency condition, continue to use the appropriate plant procedures in parallel to this procedure.

4.3 he Emergency Event Numbers that are in Attachment 8.2 in parenthisis to the right of the Emergency Classification, do not necessarily correspond to the TAB nunbers.

Exanple: TAB 8 UNUSUAL E7ENT (UE7) 5.0 CHECKLISTS 5.1 Attachment 8.3, " Emergency Coordinator's Dnergency Classifi-cation Guidance and Checklist".

5.2 Attachment 8.4, " Criteria for Emergency Closeout Checklist".

6.0 PROCEDURE NOTE: We Emergency Coordinator shall declare the appropriate d(~s emergency condition within 15 minutes of the verified off-i normal event, as per step 6.5.

6.1 he Watch Engin oer shall review Attachment 8.1, " Action level Criteria for Classification of Dnergency Corditions",

when he has been made aware of an off-normal event.

6.2 If the off-normal condition is not listed in Attachment 8.1, and the mndition is being corrected using the plant operating Irocedures, the Watch Engineer shall make the decision that the off-normal event is not a cordition cavered by the energency procedures.

6.3 If the off-normal condition is listed in Attachment 8.1, go to the Tab Number irdicated. We Tab Numbers are the locator nunbers for Attachttent d.2, " TAB Descriptions for Classification of Dnergency Cbrditions".

6.4 Match the off-normal information to one of the four Dnergency Conditions listed under the applicable Tab of Attachment 8.2.

2e effects of canbinations of initiating events that individually

> constitute a Jower classi'ication cordition should be considered

- as a possibly higher Emergency Conditier.

6.5 Declare the appropriate Emergency Condition frm the above information.

WJrE: We Dnergency Coordinator is the only individual authorized to declare an Emergency Cordition.

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SAN CNOFRE NUCIEAR CENERATI!G STATICN UNITS 2 AND 3 DEIGENCY PROCEDURE S023-VIII-11 REVISICE 1 Page 3 of 4

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6.0 P10CEDURE (Cbntinued) 6.6 Using Attadynent 8.3, " Emergency Coordinator's Emergency Procedure Implementation Checklist", record the follodng information when applicable:

a. 'Ihe procedures that have been activated.

' b. 'Ihe time ed date that the procedure was activated.

c. 'Ib whczn the procedure was assigned.

6.7 Assessment actions shall be continued, ard if necessary, the emergency classification escalated (or downgra$ed) as

' more definitive information becanes available or if the plant conditions change significantly. Go to the appropriate Dnergency procedure as based on the above information.

S023-VIII-12, Unusual Event S023-VIII-13, Alert S023-VIII-14, Site Emergency S023-VIII-15, General Emergency 6.8 Nhen the Emergency Coordinator has male the decision to terminate the Emergency Cbndition, Attachment 8.4, " Criteria for Emergency Close Out Checklist", shall be conpleted to verify that all necessary conditions exist to terminate the energency condition.

7.0 RECORDS 7.1 Attactsnent 8.3, "Dnergency (brdinator Emergency Classification Guidance ani Checklist".

7.2 Attachment 8.4, " Criteria for Emergency Close Out Checklist".

8.0 ATTACHMENTS 8.1 Attachment 8.1, " Action Level Criteria for Classification of Emergency Corditions".

8.2 Attachment 8.2, " TAB Descriptions for Classification of Emergency Corditions".

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4 DEIGEfCY PIOCEDURE S023-VIII-11 SAN CNOFRE MJCIEAR CENERATING STATION REVISICN l Page 4 of 4 f UNITS 2 AND 3 J

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8.0 ATTACHMENTS (Cbntinued) i 8.3 Attachment 8.3, "anergency Cbordinator's Emergency l

Procedure Implementation and Checklist".

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' 8.4 Attadnent 6.4, " Criteria for Emergency Close Out Checklist".

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DENGENCY PIOCEDURE S023-VIII-ll Q

V SAN CNOPRE NUCIEAR ENERATING STATICN UNITS 2 AND 3 REVISION l ATIACHMENT 8.1 Page 1 of 2 ACTION LEVEL CRITERIA POR CIASSIFICATION OF EMEIGENCY CONDITICNS 1.0 General description of the four Emergency Classifications:

1.1 Unusual Event -

Off-normal Event (s) tnat could irx3icate a potential degra3ation of the Safety level of the plant.

1.2 Alert - Off-normal Event (s) that indicate an actual degradation of the Safety level of the plant.

1.3 Site Emergency - Off-normal Event (s) that involve

' actual or inninent major failures of plant functions needed for the protection of the public.

1.4 General Emeroency -

Off-normal Event (s) that involve actual or inninent substantial fuel degradation with the potential loss of boundry integrity.

t 2.0 Specific descriptions of Initiatirg condition:

2.1 Radioactive Effluent (Applicable to any release p31nt(s) anS resulting from any initiating Event) TAB 1 2.2 lelease of loss of control of ra3ioactive material within the plant TAB 2 Reactor Coolant System (RCS) Temperature High or Low TAB 3 2.3 2.4 BCS Pressurizer Pressure High or Low TAB 4 2.5 RCS Leak TAB 5 2.6 RCS to secondary Ieak TAB 6 l

2.7 Main Steam Line Break TAB 7 BCS Activity Irt3icating Fuel Claddirg degra3ation TAB 8 2.8 i

2.9 RCS Safety Valve Failure TAB 9 j

2.10 Initiation of SIS TAB 10 2.11 Ioss of Containment Integrity TAB 11

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SAN CNOFRE NUCIEAR GENERATING STATICN ENEIGENCY PIOCEDURE S023-VIII-11 REVISICE I Page 2 of 2 UNITS 2 AND 3 ATTACifENT 8.1 i

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2.0 Specific descriptions of Initiating Cordition (Continued) 2.12 Ioss of Engineered or Fire Protection Features TAB 12 1

2.13 Failure of rea;.: tor protection system to initiate or couplete a trip SB 13 2.14 Ioss of Plant Control TAB 14 l

2.15 Ioss of Indicators, Annunciators, or Alarms TAB 15 i

2.16 Control Ibczn Evacuation M B 16 2.17 Tbxic or Flannable Gas M B 17 2.18 Security (bmprcznise TAB 18 l

' 2.19 Icss of AC Power Supplies TAB 19 2.20 Ioss of All Onsite Vital DC Power R B 20 1

2.21 'IornaSo TAB 21 J i 2.22 Hurricane TAB 22

) 2.23 Earthquake TAB 23 2.24 Fire HB 24 2.25 Explosion TAB 25 2.26 Aircraft TAB 26 2.27 Flood or Tsunane TAB 27 2.28 Contaninated Injury BB 28 l

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DERGENCY PBOCEDURE S023-VIII-11 SAN WOFRE NUCLEAR ENERATIN3 STATIN ATTACIMNTS 8.2 fl

\./ UNITS 2 AND 3 REVISION 1 PAGE 1 OF 33 1

l' TAB 1 RADIOACTIVE EFFIDET UNUSUAL EVENT (UEl, liquid; UE2 gaseous)

1. tenitored Release Exceeds Hi Alam Set Point.

A rMioactivity release in excess of MPC limits for an isotopic mix in a liquid release; or in excess of the technical specifications for a gaseous release.

NorE: he specific MPC limit for a given batch release (liquid or gaseous) is based on prior sapling results which are docmented on the Radioactive Mcste Release Pemit (RNRP). We Hi alam will be set at the a@ropriate calculated limit. If a Mi alarm occurs on one of the instrments listed below, a sample s'oeld be taken of tre affected effluent path (tank or nonitor saple, as applicable) aM the results empared to the pre-discharge sample results. If the sample results differ significantly, If the f

3 L (i.e. 20%) a new IWRP shall be calculeted.

calculated release flow alarm, (or if sum of the individual D MPC fractions exceed 1.0), the release exceeded technical specifications. Similar assessment can be performed for

. continuous release pathways using the last pericdic sanple resul*J.

Monitor Description Alam Unit Location Unit Instrunen*

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HI-Level Ic103 Rl-7804A1 Contm't Airborne Iodine

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Manitor HI-Level Ic103 Rl-7804B1 Contm't Airborne ~

Particulate Manitor HI-Invel Ie103 Rl-7804Cl Contm't Airborne ~~

Gas Pbnitor HI-Ievel Icl03 Rl-7807A2 Contm't Airborne ~

Iodine Manitor HI-Level L-103 Rl-7807B2 Contm't Airborne ~

Particulate Monitor HI-Ievel Ie103 R1-7807C2 Contm't Airborne Gas Pbnitor

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SAN CNOFRE NUCIEAR GENERATItG STATION DEICENCY PIOCEDURE S023-VIII-11 ATTAOD4ENTS 8.2 O, UNITS 2 AND 3 REVISICN 1 PAGE 2 OF 33

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TAB 1 (Continue 3)

UNUSUAL EVENT (Continued)

1. Monitored Release Exceeds Hi Alarm Set Point (Contir.ued)

Monitor Description Alarm Unit Location Unit Instrtsnent i

Plant Vent Stack HI-Ievel 2/3Icl04 2/3Rl-7808A i

Airborne Iodine m nitor Plant Vent Stack HI-Invel 2/3Ie104 2/3Rl-7808B Airborne Particulate m nitor Plant Vent Stack HI-Ievel 2/3Ic104 2/3Rl-7808C Gas m nitor Cond. Air Ejector Gas HI-Level Ie103 Rl-7813A m nitor Oord. Air Ejector Gas HI-Ievel Icl03 Rl-7818B m nitor Contm't Airborne HI-Ievel Ie103 Rl-7804Cl Gas m nitor 2/3Rl-7809A Radwaste Disposal Area HI-Level 2/3Ic104 Vent Particulate / Iodine

! m nitor 2/3Rl-7899B Radwaste Disposal Area HI-Ievel 2/3Ic104 i Vent Gas 2nitor Ra3 waste Discharge Line HI-Level 2/3Ie104

2/3Rl-7813 m nitor Waste Gas Hea3er mnitor HI-Level 2/3Ie104 2/3Rl-7814A Waste Gas Hea3er mnitor HI-Level 2/3Irl04 2/3Rl-7814B Radwaste Cordensate HI-Level 2/3Ic104 2/3Rl-7812 leturn m nitor tieutralization Sumpdine HI-Invel' Ie103 Rl-7817 DCGH. 2 ni*wr Rl-7821 Turbine Plant Area HI-Level __Icl03 O s'1"e ~#itor

SAN WOFRE NUCLEAR GENERATING STATION DERENCY PIOCEDURE S023-VIII-11 REVISION 1 ATIACHMENIS 8.2 UNITS 2 AND 3 PAGE 3 OF 33 TAB 1 (Cbntinued)

UNUSUAL EVENT (Continued)

1. Monitored Release Exceeds Hi Alarm Setpoint (Continued)

Monitor Description ' Alarm Unit Iocation Unit Instrument Fuel Hardling Area Vent HI-Level Ir103 Rl-7822Al Particulte/ Iodine Monitor Fuel Handling Area Vent HI-Invel L-203 Rl-7822B1 Gas m nitor Fuel Hardling Area Vent HI-Level L-103 Rl-7822A2 Particulate / Iodine Mnitor Fuel Handling Area Vent HI-Level Ie103 Rl-7822B2 Gas m nitor bup 2. Unplanned or Urmonitored Belease: .

Any liquid or gaseous radioactivity release via an urnonitored path; or an unplanned release via a nonitored path; either of which is estimated or suspecte3 to exceed technical specifications limits following dilution.

ALERT (Al liquid; Al gaseous)

1. Liquid A liquid release which is nonitored ard excesis 10 times *Je Hi Alarm Setpoint, or an urnonitored gaseous release which is suspected to have exceeded 10 times Technical Specification limi+J as determined by field sampling ard radioanalysis, or an urmonitored liquid release which is suspected to have exceeded 10 times MPC as determina3 by sampling ard radioanalysis.

2. Gaseous A gaseous release which is monitored and exceeds 10 times *Je Hi Alarm Setpoint.

SITE EMERGENCY (SEl)

An airborne release correspordire to greater than 50 mr/hr whold-s tody for 1/2 hour or 500 mr/hr wolebody for 2 minutes for a3 verse meteorology at the site boundry as irdicated by:

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EMEFGENCY PROCEDURE S023-VIII-ll SAN ONOFRE NUCIEAR GENERATING STATION REVISICN I ATTAOIMENTS 8.2

' \ INITS 2 AND 3 PAGE 4 OF 33

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TAB 1 (Continued)

SITE EMERGENCY (Continued)

Description Unit Instrument RI-7865-1 Containment purge &

Plant Stack Wide Range Gas RI-7870-1 Steam Jet Air Ejector Wide Range Gas RI-7874- Main Ste aline Al&-B1 RI-7875- Main Steanline Al& -B1 O( GENERAL EMEKIENCY (gel)

Airborne Release Corresponds to:

a. Offsite dose due to the event is projected to exceed 0.5 rem to the whole txx1y, or 25 rem to the diild thyroid as determine 3 by dose calculation, or

b. 'Ihe above dose is projected based on radioactivity released to contairment as irdicated by:

Description Unit Instninent RI-7820-1 In Containment High Range RI-78720-2 In Containment High Range RI-7858-1 Dnergency Padiation Pbnitoring System RI-7859-2 Dnergency Radiation Pbnitoring System RI-7860-3 Dnergency Pa3iation bbnitoring System

DERGEPCI PIOCEDURE S023-VIII-11 p)

SAN CNOFRE NUCIEAR GENERATIW3 STATION UNITS 2 AND 3 REVISICE 1 PAGE 5 OF 33 RITACHMENTS 8.2 RB2 i r IN-PIRTT RADIATICN LEVEIS UNLSUAL EVENT let Applicable ALERP (A3)

Unexpected Increase in In-Plant Radioactivity Levels or a Fuel Handling Accident or another verified uncontrolled event that increases radiation levels by a factor of 1000 or higher; as indicated by:

Monitor Description Emergency Action Ievel Iocation Unit Instrment 1000 X Nomal (TAB 1)

(All Instrments Listed in TAB 1)

Auxilisry Building 1000 X Normal L-90 2/3 RISH-7842 Area El. 9 Feet Auxiliary Building 1000 X Normal L-90 2/3 RISH-7843 Area El. 37 Feet g

Auxiliary Building 1000 X Normal L-90 2/3 RISH-7841 Area El. 63 Feet Iocal Sa ple Lab 1000 X Nomal L-90 2/3 RISH-7854 High Radiation 1000 X Normal Ie90 2/3 RISH-7844 Storage Area 1000 X Nomal Ie90 2/3 RISH-7852 Radiochem. Lab Area 1000 X Normal Ie90 I 2/3 RISH-7851 Control Rxm (Auxiliary Bldg)

Hot Machine Shop 1000 X Normal Ie90 2/3 RISH-7853 1000 X Normal Ie90 2/3 RISH-7845 Contaiment Access Hatch Contalment General 1000 X Normal Ir90 2/3 RISH-7848 Area Safety Equipent Bldg. 1000 X Normal Ie90

2/3 RISH-7847 General Area Spent Fuel Cask 1000 X Normal te90 2/3 RISH-7850 O Load ing Area 1000 X Normal N/A N/A Field Measurement: with Fortable Survey Instr ments

l SAN OtOFE NUCIEAR GENERATI!C STA'.:' ICE EMER3ENCY P10CEDURE S023-VIII-11 REVISION 1 KPIACHMENTS 8.2 INI"S 2 AND 3 PAGE 6 OF 33 TAB 2 (Continued)

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SITE EMEEENCY (SE3) i 1. Spent Fuel Damage:

Major damage to spent fuel due to fuel handlire accident; 2 Instrument and Description Alarm EAL N/A N/A

' Area ard Ventilation monitors identified above (Alert)

Field Measurements with portable survey instrunents N/A 50 mrerr/hr*

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At Site Boundary. (Must Continue for at least 1/2 hour)

2. Spent idel Pool Ievel Decrease:

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' Uncontrolled decrease in fuel p3ol water to below level of fuel.

Description Alarm Alarm Spent fbel Pool Hi/Im Level Iow 61-C #3 1

Spent Fuel Pool Linear Visual i Observation Leak Detection GENERAL EMEME2CY Ioss of 2 of 3 Fission Product Barriers i

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SAN WOFRE NDCIEAP GENERATING STATICN , DEFGENCY PROCEDURE S023-VIII-11 e ATTACHMENIS 8.2

(, REVISI N 1 WITS 2 AND 3 PAGE 7 OF 33

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~ RCS TEMPERA'IURE HI OR IDW a

UNUSUAL EVENT (UE4) i

1. RCS T Iess than 520 F while critical (Modes 1 ard 2) f ave Description i

Instrument TR0lli A/B T ave TR0121 A/B T ave TFS100 A/B T,y, 4

2. RCS T we Greater than 588.05 F (Mode 1)

Description Instrument (Same as above) T,,

3. BCE (Pressure /Tenperature) Iess than 50 F Subcooled Instrtrnent RCS Subcooling Margin Monitor I

j ALERP (A6)

R3 Tenperature Greater than 588.05 F (T ) and RCS I-131 Activity greater than 300 uCi/8Y* Determined l by Ietdown Radiation Monitor ard/or Isotopic Analysis l

1 SITE ES'ERGENCY (SE6)

Degraded core with gossible loss of coolable geometry, evidence j

of uneven core temperature distribution from incore thermocouples, i

Increasing High RCS '1bmperature RCS Flcw Decrease with RCS I-131 Activity greater than 300 uCi/ml ard increasing.

GENERAL 1FSIGENCY (GE2)

Ioss of 2 of 3 Fission Prcduct Barriers (Clad, BCS, Cbntairrnent) with a potential loss of the third barrier.

SAN CNOFRE NOCIEAR GENERATIIG SEATION DEIEENCY PROCEDURE S023-VIII-11

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v INITS 2 AND 3 REVISION 1 ATTACIIENTS 8.2 PAGE 8 OF 33 TAB 4

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BCS PRESSURS HI OR IDW UNUSUAL EVENT (UES)

1. RCS Pressure Exceeds Safety Limit (2750 PSlA)

Instrument Description PR 0100 A/B Pressurizer Pressure P 1100 X cr Y Pressurizer Pressure

2. INBR Itw Pressure Trip has occured (variable pressure, minima 1806 PSIA) indicated by RPS Trip Bigtables, concurrent with ICS (Pressure / Temperature) less than 50 F subcooled indicated oy j

ICS subcooling margin monitor.

ALERP (A6) p 1. RCS Pressure High (at or above safety

alve setpoint of 2500 PSlA) concurrent with increasing RG temperature

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, i frca TR0lll A/B or TR0121 A/B (Tave) .

l 2. RG Pressure Low with SIAS initiated (1806 PSIA) and RCS I-131 activity greater than 300 uCi/ml determined by letdown ra3iation monitor and/or isotopic analysis.

SITE EMEICENCY (SE6)

Degraled mre with possible loss of coolable geometry, evidence of uraven core temperature distribution frcn incore thermocouples, Increasing /High RG 'Ibmperature RCS Flcw Decrease with RCS I-131 Activity greater than 300 uCi/ml and increasing.

GCNERAL EMERGENCY (GE2)

Ioss of 2 of 3 Fission Product Barriers (Cla3, RCS, Contairnent) l with a potential loss of the third barrier.

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l SAN CNOFRE NUCIEAR GENERATING SMTION D1ER3ENCY PIOCEDURE S023-VIII-ll S REVISION 1 ATTACHMDfIS 8.2 (V LNITS 2 AND 3 PAGE 9 OF 33 RB5

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RcS IE;sAaE I NOTE: Were are no ins *mts which directly measure RCS leakage.

BCS leakage is determined by a leak rate surveillance procedure. We instrunents listed below may be indicators

.I that a significant leak exis*a.

Inrarument Description i R7819 Conporrnent Cbolirq Water knitor T1107 PZR_E087 Relief Line Temperature T1108 PZR E087 Relief Line Temperature LI116 QueEch Tank Ievel Pill 6 Quench Tank Pressure TIl16 Quench Tank Tenperature Pressurizer E087 Level Recorder PI-351-1 Containment Pressure Containment Pressure PI-351-2 PI-351-3 Containment Pressure PI-351-4 Containment Pressure

! PI-352-1 Contaiment Pressure PI-352-2 Containment Pressure O

. PI-352-3 Containment Pressure l j PI-352-4 PI-353-1 Containment Pressure Contaiment Wide / Wide Range Pressure l' LI-5853-1 Contairunent Normal Strnp Level FR-5805 Containment Strnp Inlet Flow Narrow Barge FR-5802 Contairrnent Sump Inlet Flcw RP-6759 Steam Generator Blowdown Ra31ation Manitor l

Unit Instrument Monitor Description Unit location l

Rl-7804A1 Contm't Airborne L-103 tbnitor R1-7804B1 Contm't Airborne Icl03 Particulate Ponitor R1-7804Cl Contm't Airborna Icl03 Gas Ibnitor R1-7807A2 Contm't Airborne L-103 Iodine Monitor Rl-7807B2 Contm't Airborne Ie103

' Particulate tenitor Rl-7807C2 Contm't Airborne Ic103 o = *"it r O

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4 EMERGENCY PROCEDURE S023-VIII-11 p SAN CNOFRE NJCIEAR GENERATING STATION UNITS 2 AND 3 REVISICN 1 ATTACHMENTS 8.2 v PAGE 10 OF 33 TAB 5 (Cbntinued) f Unit Instrtsnent Monitor Description Unit location Eles Ie103 Rl-7858-1 Ie103 Rl-7859-2 ERMS Ie103 Rl-7860-3 ERMS i

I AnnunciaCors Pressurizer Safety Valve Outlet TWnp Hi 50A31 Contairunent Pressure High 56A35

] Pressurizer Ievel Io-Io 50A3 Beactor Vessel Seal Leak Detection 50A35 7

Contairunent Stanp Hi and Hi - Hi Level 56A56 ard 56A55 j UNUSUAL EVENT (UE6a)

1. Unidentified Leakage Greater than 1 gpm j

2. Identified Leakage Greater than 10 gpn T~

1 3. RCS to Secondary Leakage Exceeds 0.5 gpn (720 gal / day) Throtgh Any One S/G

4. Ste.rn Generator activity Exceeds 0.10 uCi/ml Dose Equiv. I-131 a-i ALERT (A4a)

Ieakage Exceeds 50 gpn l

d SITE EMERGENCY (SE4a) j Icakt:ge Exceeds Make-up Capacity (IOCA)

GENERAL EMERGENCY (GE4) i 1. Ioss of Coolant Accident with failure of SIS. *

2. Icss of (bolant Accident with subsequent failure of the heat rencnal system and the likely failure of contairinent.

toes or coo 1emt accide=t ita roet reitere e,a pro 8eete immimeat O 3-failure of containment.

SAN CNOFRE WCIEAR GENERATING STATION EMEMENCY PROCEDURE S023-VIII-11 REV. ISION 1 A'I'IACHMENIS 8.2 UNITS 2 AND 3 i

PAGE 11 OF 33 TAB 6

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RcS m SEONARY LEAKAGE NOTE: Were are no instrtments which directly measure RCS to Secordary leakage. ES to Secondary Ieakage is determined by a leak rate surveillance procedure. We instrtnents listed below are indicators that a significant leak exists.

Instrument Description R7818 Main Cordenser Air Ejector Gas Pbnitor 1 R6759 Steam Generator Blowdown Radiation

R6753 LR-0110A&B Pressurizer Ievel Recorder j

UNUSUAL EVENT (UE66)

1. RPS to Secondary Imakage Exeeds 0.5 gpn through any one Steam Genera *wr

2. Steam Generator Activity Ex eds 0.10 uCi/ gram Dose Equivalent I-131 p

N _

ALERT (A4b) -

E S to Secondary Leakage Exceeds 50 gpn.

SITE EMERGENCY (SE4b)

1. RCS to Secondary Leakage Exceeds BCS Make-Up Capacity With Ioss of l Offsite Power j

i

2. RCS to Secondary Leakage Exceeds 50 gpu Concurrent with Main Steam Line Break and Indication of Fuel Failure.

I GENERAL EMEMENCY

1. Ioss of Coolant Accident with a failure of *Je SIS.

2. Ioss of Coolant Acident with subsequent failure of heat renoval systems, likely failure of contairrnent integrity.

j

3. Ioss of (bolant Accident with fuel failure and probable inminent

-- failure of containment integrity.

5 O

i DEIGENCY PIOCEDURE S023-VIII-11 A SAN CNOFRE NUCIEAR ENERATING STATION ATTACHMENIS 8.2 REVISICN 1 l V INITS 2 AND 3 -

PAGE 12 OF 33 j TAB 7

(

MAIN STEAM LINE BREAK d

i 1

(NUSUAL EVEN_T l

Steam break causing rapid depressurization of secondary steam pressure- and associated primary cooldown.

? ALERr (A51 Main Sterm Line Break detennined by MSIS actuation at less than or equal to 729 PSIA Steam Generator pressure concurrent with 10 gpn RCS to Secondary Leakage determined by ICS Imak Rate Surveillance.

Instrument Description PI-1023 A1, A2, A3, A4 Steam Generator Pressure PI-1012 Al,A2,A3,A4 Steam Generator Pressure SITE EMERGENCY (SES)

Main Stean Line Break Concurrent with 50 gpn RCS to Secordary

'( ~'

Isakage concurrent with RCS I-131 activity greater than 300 uCi/ml determined by isotopic analysis.

GENERAL EMEIGENCY (GE4)

Ioss of Plant Control 1

O

DfEIGDCY PROCEDURE S023-VIII-11

/7 SAN CNCGE MJCIEAR GENERATING STATION REVISION 1 ATTACHMD?rS 8.2 V LNITS 2 AND 3 PAGE 13 OF 33 TAB 8

(

FUEL CIADDIbG DEGRADATION l UNUSUAL EVENT (UE7)

1. 1-131 Dose Equivalent Exceeds LCD (100/E uCi/ml) Tech Spec Limit, Instrument Description Grab Radiochemistry analysis Sanple

2. Specific Mtivity Exceeds LCD (100/E uCi/ml) SteMy State, Tech Sp w Limit Analyses as above.

ALERP (A6)

RCS I-131 Dose Equivalent Ex eds 300 uCi/ml.

Analyses as above.

f SITE EMEIGENCY (SE6) 1 Degraded Core with Possible Ioss of Coolable Gecretry:

Evidence of uneven core temperature distribution (thernoccuples) or RCS Terperature Hi, ICS flow decrease; in acklition to RCS I-131 Dose Equivalent Activity Exceeding 300 uCi/ml.

GENERAL EMEIGENCY (GE2)

Ioss of 2 of 3 Fission Product Barriers:

Fuel clMding failure with ILCA and with potential loss of contain".ent integrity.

b) v

DEH:ENCY P10CEDURE S023-VIII-11

! SAN CNOFRE NUCLEAR GENERATI?G STATICN REVISION 1 ATTACHMENTS 8.2

(N) im UNITS 2 AND 3 - PAGE 14 OF 33 TAB 9 f

SAFEIY RELIEF VALVE UNUSUAL EVENT (UE8)

Safety relief valve fails to close (leakage exceeds primary leakage LCD 10 gpn) . Indications of leakage are:

Description Instrunent PZR-2E087 Relief Line Temperature i _TI-107 TI-108 PZR-2E087 Relief Line Ibmperature

_LI-105 Quench Tank _T011

-TI-ll6 Quench Tank _T011

_PI-ll6 Quench Tank _T011 Acc3ustic Flow Pbnitor i

O ALERP (A4a) r Isakage exceeds 50 gpn.

4 SITE EMEIGENCY (SE4a)

Ieakage exceeds the make-up capacity to the RCS, Ioss of Coolant Accident (IDCA)

GENERAL EMERGENCY (GE4)

1. Ioss of Cbolant Accident with failure of +Jie SIS.

i

~

2. Ioss of Cbolant Accident with subsequent failure of heat renoval systems; likely failure of contairnent integrity.

3. Ioss of Coolant Accident with fuel failure and probable imminent i

failure of containment integrity.

~

4 e p

)

i O

I

SAN CNOFRE NUCIEAR GENERATING SIATION DtEEDCY PROC!?d3E SO23-VIII-ll

/ REVISION 1 ATIAONENTS 8.2 i UNITS 2 AND 3 i PAGE 15 OF 33 TAB 10 I

SIS INITIATION f UddSUAL EVENT (UE 11)

Initiation of SIS:

Valid safety circuit trip (s) or necessary manual initiation.

'Ihe follwing insrtunents are irdications that SIS has initiated:

Instrunent Desc-iption PI-0308 HPSI Pmp,_P017 Dish Pressure PI-0309 HPSI Pep P019 Dish Pressure t

' FI-0311-2 Safety Injection Flw to Cold Iegs FI-0321-1 hPSI Fl w to Cold Legs FI-0331-1 HPSI Flw to Cold Legs FI-0341-I HPSI Flw to Cold Leg j

HS-9391-2 HPSI Pmp _P016(N)

HS-9391-1 HPSI Pump _P015(E)

HS-9395-1 Contairunent Spray Pump E-9396-2 Contairrnent Spray Pump i Annunciators j SIAS Actuation Train B 57B01 SIAS Actuation Train A 57A01

Trips Im Pressurizer Pressure 1806 PSIA, minimm (variable trip point)

Containment Pressure Hi (2.95 PSIG)

ALERP Not Applicable SPrE EMEMENCY Not Applicable GENERAL EMEEENCY (GE4)

O Ioss of <nntro1 of the P1ent

D4EICDCY PROCEDURE SO23-VIII-ll O

V SAN ONOFRE NJCIEAR GENERATING SIATION LNITS 2 AND 3 REV, ISICN 1 ATTAONENTS 8.2 PAGE 16 OF 33 TAB 11

(

IDSS OF (INTAI! MENT INTEURITY UNUSUAL EVEh'T (UE12)

Contairrnent leak rate exceeds surveillance starv3ard 4.6, as discovered during surveillance test; or inability to maintain contairunent pressure.

Instranent Description PI-351-1 Contairinent Pr&ssure PI-351-2 Contairrnent Pressure

PI-351-3 (bntairunent Pressure PI-351-4 Contairunent Pressure PI-352-1 Contairunent Pressure PI-352-2 Contairunent Pressure PI-352-3 Contairrnent Pressure PI-352-4 Contairrnent Pressure PI-353-1 Cbntairunent Pressure Cbntainment Pressure High (2.9 PSIG) - 56A35 1

ALERT Itt Applicable SITE EMEICENCY Not Applicable GENERAL EMERGENCY (GE3)

Failure of contairment is inminent concurrent with IDCA ard fuel cla3 ding damage O

I O

n DEICENCY PIOCEDURE S023-VIII-11 SAN WOFRE! NUCLEAR GENERATING S'IATIN REVISION I ATTACHMENIS 8.2 pd UNITS 2 AND 3 PAGE 17 OF 33 TAB 12

?

IDSS OF ESF's l.

UNUSUAL EV9FF (UE13, Ioss of ESF; LE14, Ioss of Fire Systems)'

j Loss of Engineered SaSty Features (ESF), or fire protection j (Reftence 2,7, !DGS-2 & 3 equipnent, requiring shutdown by IE.

i Tech Specs.

i

?

i ALERP

)

Not Applicable 4

1h I -.

SITE ENERGINCY Not Applicable 2

GENERAL EMEIGENCY (GE3) i O( Ioss of Plant Control l

1 l

4 e .e lO

--.. , + , _ , v - -

SAN OOFRE MJCLEAR GENERATING STAT.ON I DiEEDCY PROCEDURE S023-VIII-11 REVISION 1 AMAGMENTS 8.2 UNITS 2 AfD 3 PAGE 18 OF 33 TAB 13 I

PM>nunVE SYSTEM FAIIURES UNUSUAL EVENT l

l Not Applicable I

ALERT (A7)

Beactpr Not Suberitical After Va3id Trip Signal (s)

Instrument Description l

N actor Trip MIMIC CEA ke3 Switch Position Indicating Ibds Not fully inserted Panel CEA bottom 119 at-O Retctor power level irrlicaors not downscale JI007&B SITE EMERGENCY Any transient requiring operation of shutdcun systems with a failure to trip (continued power operation with no core damage immediately evident) .

GENTRAL EMEEENCY (GE4)

Reactor Protection System fails to initiate or complcte a trip, followed by a loss of cre cooling and make-up systems, which results in fuel degra3ation as determined by Post Accident Sanplirg System Activity Determination.

9 4

O

"'"""""' "'"""2-'"'-'

" ^ " ' " ' " " " ' " ^ " " ' * * " ^ " " "'^ " REVISICN l ATIACHMDfIS 8.2

' CD LEITS 2 AND 3 FAGE 19 OF 33 TAB 14 4 /

IDSS OF PLANT OCNTIOL c'

UNUSUAL EVDFT

1. Any plant condition that warrants increased stareness on the part of the plant operatirg staff or State ard Iocal of fsite authorities or both.

2. Any plant condition that requires plant shedown under technical specification requirements or irriolve other than normal controlled shutdcwn.

ALEIU' (AB)

Ioss of Capability to Achieve Cold Shutdown 5

SITE EMERGENCY (SE7)

Ioss of Capability to Achieve Hot Shutdown

(

GENERAL EMERGENCY (GE4 Ioss of Physical Control of Plant 4

l k

5 O

i e SAN ON05'RE NUCIEAR GENERATING STATION DETGE!Cf PIOCEDURE S023-VIII-11 REVISICN 1 ATIACHMDfIS 8.2 UNITS 2 AND 3 PAGE 20 OF 33 TAB 15

(

4 IDSS OF INSTRUMEffrATICN UNUSUAL EVENT (UE15)

Ioss of Vital Indicators, Annunciators, or Alarms in Excess of LCD:

1. Ioss of vital irdicators, annunciators on effluent paraneters during release.

2. Inoperable ESF Activation Systen Instrumentation per Table 3.3-3 of SWGS-2 Technical Specifications.

ALERT (A9)

Ioss of (bntroll Ibczn Alarms (Annunciators) Sustained for greater than 5 minutes.

SITE EMEIGENCY (SES)

Uncontrolled Transient Occurs mile All Alarms are Lost GENERAL EMERGE!K.Y (GE4)

Ioss of Cbntrol of Plant ego a

O -

e

SAN CNOFRE NUCIEAR GENERA 7tG SIATICN DEICENCY PIOCEDURE S023-VIII-11 UNITS 2 AND 3 ,REVISICN I ATTAOiMD7TS 8.2 PAGE 21 OF 33 TAB 16

(

CONT 10L,FOOM EVACUATION UNUSUAL EVENT _

Not Applicable ALERT (A10)

Control Ibom Evacuation Required or Anticipated-Control at LTal Stations:

Evacuation of the Control Iban is required or anticipated and control of shutdcun systems has been established at local control 4

Ltations.

Instnznent Indication l l

Visual / local Alarm fire in (bntrol Ibom Visual Heavy Smoke in Control Iban Toxic Gases Analyzer Other Toxic Gases Observed

(

2/3RISH-7851 High Radiation, Control Boon Annunciators a

60B19 TGIS TR A Hi Toxic gas / trouble 60B20 'IGIS TR B Hi Taxic gas / trouble SITE DERGENCY (SE9)

Evacuation of the Control Iban is required and control of shutdown systems has not been established at local control stations within 15 minutes.

GENERAL DEFGDCY (GE4)

Ioss of (bntrol of Plant i

h i

k --- - - . - - .

)

SAN CNOFRE NJCIEAR GENERATING STATICN DElGEWY PIOCEDURE S023-VIII-13 l /~' ATTACHMDUS 8.2 UNTIG 2 AND 3 REVISION 1 f

PAGE 22 0F 33 j TAB 17 I

)

10KIC/ FIR 9%BLE GASES

}

4 UNUSUAL EVENT (UE16) 4 I Uncontrolled Nearby or Onsite Release Irdication 1 Observation by irritation, noticeable ordor, samples, verbal reports of authenticated accidents resulting 4

in release.

4 ALERT (All)

Gas enters the facility and causes Habitability Problems f

SITE EMEIGENCY (SE10)

Gas Enters Vital Areas and Restricts Access Necessary for Safe Shutdown

' (

t i GENERAL EMERGENCY (GE4) 1

' Ioss of Cbntrol of Plant 1

1 l

J 4

.d a

e e i

i.O A--4-- ym _

4 I

OeacEact raoc11x>as So23-v111-11 O San <=or8E INITS 2 AND 3 xxzaa Ge=Ea^T1 0 Srir1cs REVISION 1 PAGE 23 OF 33 ATTAO N Z 8.2 ;

( TAB 18 i

SECURITY C0f&JOMISE A

I UNUSUAL EVENT (UE28)

Not Applicable. Action per SOGS Security Plan.

i

! 1 I ALERP (Al2) f Not Applicable. Action per SOGS Security Plan.

e 4

SITE EMERGENCY (Sell) i Iminent Ioss of Physical Control of Plant i ,

l _

GENERAL EMERGENCY (GE4)

! Ioss of Physical Control of Plant l O' i

i i

j 4

1 1

)

i i

O i

SAN CNOFRE NUCIEAR GENERATING STATION DEIGENCY PIOCEDURE S023-VIII-11 REVISICN 1 ATTACIMNTS 8.2 UNITS 2 AND 3 PAGE 24 OF 33 i g TAB 19 l

IOSS OF AC POWER UNUSUAL EVENT (UEl7) i 1. Io?s of All On-Site AC Power Capability, Diesel Generators Inoperative.

Annunciators ESF Bus A04 Iow Voltage - 63B39 ESF Bus A06 Iow Voltage - 63A33 480V ESF Bus _B06 Ioss of Voltage 480V ESF Bus _B06 Ioss of Voltage

2. Ioss of Offsite Power Offsite power iroperative ALERP (A13)

Temporary Ioss of Ibth Onsite and Offsite AC Power (Diesels Unavailable)

SITE EMEJGENCY (SE12)

Ioss of Ibth Onsite (Diesels Unavailable) ard Offsite Power for Ionger 'Ihan 15 minutes GENEPAL EMEICENCY (GE4)

Ioss of (bntrol of Plant l

O

4 SAN CNOFRE NUCIEAR GENERATIN3 STATICN DEIGENCY PROCEDURE S023-VIII-11

% UNITS 2 A!D 3 REVISION 1 ATIACHMENTS 8.2 PAGE 25 OF 33 TAB 20

(

IDSS OF DC POWER UNUSUAL EVENT

. Not Applicable 1

4, e

i ALERr (A13)

Ioss of All Onsite DC Power a .

l '

Annunciators 63C31 thit _125VDC_Dl-Bus Trosle 63C52 Unit _125VDC_D2-Charger Tro sle 63C35 Unit _125VDC_D-3-Bus Trouble 63C58 Unit _125VDC_D4-Charger Trosle i

63C48 Unit _125VDC_D5-Charger Trosle

(

63C11 Unit _125VDC_D6-Charger Tro sle SITE EMERGENCY (SE12)

loss of Vital DC Power Sustairm for Iorger than 15 Minutes GENERAL EMERGENCY (GE4)

I Insis of Cbntrol of Plant t

t O

e i

4 I

1 f

i

' O San c Orae noctria GesET&T1W2 Stat 1cn UNITS 2 AND 3 oeicEncY >>ocEauaE So23-v111-11 REVISICN .1 ATTACHMENTS 8.2 PME 26 OF 33 g TAB 21 l 'ICINADO 1

(NJ30AL EVENT (UE19)

! 'Ibrnado Sighted Onsite With a Probable Effect on Station:

' Instrument Description Met. System Wind Spes3 Indicator 10' I Met. System Wind Spee3 Indicator 20' i

> Met. System Wind Speed Indicator 40' Weather Bureau Advisories Personnel Sighting ALERT (A15)

Tornado Strikes Vital Plant Structures J

SITE EME EENCY (SE14)

'Ibrna30 with Winds in Excess of Design Speed (100 mph)

I GENERAL EMEEENCY (GE4) 2 Ioss of Cbntrol of Plant 1

I S OF

!O il 1

\ .

i

' EMEIGENCY PH3CEDURE S023-VIII-11 SAN CNOFRE NOCIEAR GENERATING STATICN REVISION l ATTACHMENTS 8.2 I (JNITS 2 AND 3 PAGE 27 OF 33 f TAB 22 i

HURRICANE i

i UNUSUAL F y_ (UE20) l i

Hurricane With Probable Impact on Station i Description Instrument Met. Systen Wind Spee3 Indicator 10' Met. System Wird Speed Indicator 20' l Wind Speed Indicator 40' Met. System Weather Bureau Advisories

.! ALERT (A16)

J Hurricane with Winds up to Design Speed (100 mph) j I

i \ SITE EMEIGENCY (SE14)

Hurricane Winds in Excess of Design Speed (100 mph) a GENERAL EMEIGENCY (GE4) 1 i

Ioss of Cbntrol of Plant i,

l I

i eeW

.O 1

l SAN CNOFRE NILEAR ENERATIN3 SMTION DEFGDCI PROCEDURE S023-VIII-11 T

REVISICN 1 ATTACHMENIS 8.2 w UNITS 2 AND 3 PAT 28 OF 33 TAB 23

/

EARINQUAKE UNUSUAL EVENT (UE21)

Earthquake Detected by Site Seismic Instrtrnentation

'Ihe accelerograph alarm initiates upon detection of a seisnic event resulting in 0.01 g acceleration. Seismic Accelerograph Operation annunciator indicates start of system.

I ALERP (M7) q 1. Earthquake Greater than 0.25 g, Operating Base Earthquke, (OBE) Occurs.

2. Earthquake Causes Known Damaje to facility Affecting Operation SITE EMEFGENCY (SE15)

- 1. Earthquake Greater than 0.5 g, Safe Shutdown Earthquake, (SSE)

( Nmrs

2. Earthquake Causes Severe Damage to Safe Shutdown Equipnent GENERAL EMERGENCY (GE4)

Ioss of Cbntrol of Plant O

l

O San <= orae Noc=^a Gesta^r1 G erir1o=

UNITS 2 AND 3 ixrm ener rioccouas So23-v111-11 IE/ISICN 1 ATTACHMDTJS -8.2 PAGE 29 OF 33 g TAB 24 FIRE UNUSUAL EVENT (UE26)

Fire within plant whidt is not brought trder control within 10 minutes from start of firefighting efforts.

ALERP (A18)

Fire Nhich Potentially Affects Safety Systems SITE EMERGENCY (SE16)

Fire within the Plant Which Effects the Safe Shutdown of the Plant.

GENERAL EMERGENCY (GE4)

Loss of Cbntrol of Plant C.t 1

e O

I SAN CNOFRE NOCIEAR GENERATITE STATICN DERGENCY PROCEDURE S023-VIII-ll O' UNITS 2 AND 3 RE:VISICN 1 PAGE 30 OF 33 ATIAOiMENIS 8.2

'.1 TAB 25

/

EXPIDSICN UNUSUAL EVENT (UE22)

' Within Security Protected Area with No Significant Effect:

6 Observation of the Event ALERr (A19) l Explosion with Known Damage to Facility, Affection Operation SITE EMERGE 2CY (SE]7) i Explosion Causes Severe Damage to Effect Safe Shutdown Equipnent GENERAL EMEIGENCY (GE4)

. Ioss of Plant Control Occurs .

O e *@

O I

i

J 4

SAN CNOFRE NUCIEAR GENERATING STATION EMEIGENCY PRJCEIIJRE S023-VIII-11

' O' UNITS 2 AND 3 REVISION 1 PAGE 31 OP 33 ATIACWINTS 8.2 TAB 26

(

AIRCRAFT i

UNUSUAL EVENT (UE25) i Aicraft Crashes Onsite-But Outside Protected Area ALERT (A20)

Aircraf t or Missile Strikes a Station Structure Inside Prot.ected Area f SITE EMERGENCY (SE18)

Aircraft or Missile Crash Affects Vital Structure by Impact or Fire GENERAL EMEIGENCY (GE4)

Ioss of Plant Control Occurs

~

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\ .

I e se O

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DEIGENCY PROCEDURE S023-VIII-11 SAN CNOFRE NUCTEAR GENERATING STATION REVISION I ATTACI9h% 8.2 UNITS 2 AND 3 PAGE 32 OF 33 TAB 27

f i

FICOD/ TSUNAMI UNUSUAL EVENT (UE24)

Flood /Tsunani Warnirg-Probable Affect on Operations By Observatiory'aeport by Weather Bureau.

ALERP (A21a)

Flood /fsunani Causes Known Damaje Affectirg Operation SITE EMERGENCY (SE19a)

Flood /fsunnni Causes Severe Damage to Safe Shutdown Equipment GENERAL EMEICENCY (GE4)

Ot Ioss of <mnero1 of 21aet e nf O

SAN CNOFRE NUCIEAR GENERATING STATICN EMERENCY PIOCEIIJRE S023-VIII-ll ATTACHMENIS 8.2 UNITS 2 AND 3 REVISICN 1 PAGE 33 OF 33 TAB 28

( '

CarrAMINATED IRTURY e

UNUSUAL EVENT (UE27)

Personnel injury occurs which results in the transportation of contaminated and injured personnel to an offsite hospital.

ALERP 1

Not Applicable SITE EMERGENCY Not Applicable GENERAL EMEIGENCY l Not Applicable J

O v(-

1 a

6 00 0

_ . - _ - - - - - - -_ _ - - _ ~ --- v - - w

As DEIGENCY PIOCEEIJRE S023-VIII-ll O SAN CNOFRE NUCIEAR GENERATING SIATICN REVISICN 1 ATTAQMNT 8.3 C' UNITS 2 AND 3 PAGE 1 OF 4

(

DEIGENCY CXDRDINAIOR'S DGGGENCY CIASSIFICATICH GUIEMCE AND CHECKLISP J

Initiatirs Condition (Initial Indication) ,

1.

2 Date Time TAB #

Classification of Emergency ,

~

Frm the above information, check off the procedures that are activatal directly by this procedure or by other Emergency Procedures aM fill in the appropriate blanks.

Activated (check)

1. SO23-VIII-12 Unusual Event: Time Activated Date: Assigned to:

Ccanents:

2. SO23-VIII-13 Alert: Time Activa *ad Date: Assigned to:

O-(

Coments:

3. SO23-VIII-14 Site Emergency: Time Activa *M Date: Assigned to:

Coments:

4. SO23-VIII-15 General Emeroency: Time Activated Date: Assigned to:

Chmients: _ _ , ,

P

5. SO23-VIII-16 Notificativ.: Time Activated Date: Assigned *4:

Coments:

6. SO23-VIII-17 Activation and Operation of Emergency Centers aM Orcanizations: Time Activated

' Date: Assigned to:

Ccmnents: .

7. SO23-VIII-18 Notification of Additional Emergency Support Personnel:

Time Activated:

Assigned to:

O Date:

Cmments:

1 l

iMEIGDCf PROCEDURE SO23-VIII-ll

/"3 SAN CNOFRE MJCIEAR GENERATING STATICH ATIAWMDTP 8.3 BEVISION 1 V UNITS 2 AND 3 PAGE 2 OF 4

(

8. 9023-VIII-22 source Term Determination: Time Activated _

Late: Assigned to:

(brrmen*J:

9. m23-VIII-23 Dose Assessment: Tine Activated Date: Assigned to:

Chrments:

10. SO23-VIII-24 Direction of Onsite Emergency Monitoring:

i Time Activated: '

I Date: Assigned to:

(beiments:

1 11 9023-VIII-25 Direction of Offsite Emergency Monitoring:

4 Time Activated ._

' Date: Assigned to:

Chrments:

3 O-(

12. SO23-VIII-26 Recommendation for Offsite Protective Measures:

Time Activated

- Date: Assigned to:

Cmments:

13. SO23-VIII-27 Emergency Environment Monitoring:

Time Activated ,

Date: Assigned to:

Cmments:

14. M23-VIII-31 Emergency Ex1x>sure Control: Time Activated Date: Assigned to:

Cauments:

15. SO23-VIII-32 Local Evacuation and Accountability:

Time Activated:

Date: Assigned to:

Conments:

16. S023-VIII-33 Plant Evacuation ard Accountability:

Time Activated Date: Assigned to: _

Corrments: 1 1

I

EMEKIDCY PROCEDURE S023-VIII-11 Q SAN CNOPRE NJCIEAR GENERATING SIATION REVISICN 1 ATIAOMNT 8.3

, D UNITS 2 AND 3 PAGE 3OF4

(~

17. 9023-VIII-34 Site Evacuation art 3 Accountability:

Time Activated Date: Assigned to:

Coments: l

18. 2 23-VIII-35 Traffic and Access Control: Time Activated Date: Assigned to:

O mnen*a:

19. SO23-VIII-36 Thyroid Prophyloxis: Time Activated Date: Assigned to:

Comnents:

l

20. SO23-VIII-37 Firefighting: Time Activated:

Date: Assigned to:

Ocnnents:

21. S023-VIII-38 Contaminated Injury: Time Activated

( Assigned to:

Date:

Q:mrents:

22. SC23-VIII-39 Rescue: Tune Activated Date: Assigned to: ,

Otanen*J:

_ 23. SO23-VIII-41 Onsite Monitoring: Time Activated Date: Assigned to:

Ocnnents:

24. 8023-VIII-42 Offsite Monitoring ard Sampling:

Time Activated:

Date: Assigned to:

Ocnnents:

~~

25. S023-VIII-43 Samle Coordination During an Emeinency:

Time Activated Date: Assigned to:

Coments:

h DiER3ENCY PROCEDURE S023-VIII-ll (3 SAN CNOFRE NJCIEAR GENERATItG STATICN REVISICN 1 ATTAOiMENT 8.3

, () LNITS 2 AND 3 PAGE 4OF4 r

26. SO23-VIII-44 Dregency Contamination Control:

Time Activated Date: Assig:ed to:

Connents:

27. 9023-VIII-45 Personnel and Vehicle Monitori_ng:

Time Activated Date: Assigned to:

i Ctsments:

i 28. fD23-VIII-46 Onsite Sampling: Time Activated i Date: Assigned to:

4 Conments:

$ 29. SO23-VIII-51 Record Keepino: Time Activated:

Date: Assigned to:

Ctmments:

g ,

t'

30. SO23-VIII-61 Re-ently: Time Activated Date: Assigned to:

Coments:

31. 9023-VIII-62 Activation of the Recovery Orcanizations:

i Time Activated Date: Assigned to:

Ocunents:

NOTE After this checklist is completed and is not required for imediate use, forward it to the Station Services Manager (Administrative Leader i

' if Emergency Organization is activated).

eeO 4

O

O SAN cNOraE NoctriR aexEaAr1ru erxT1aN UNITS 2 ?.ND 3 e eaaEace r m CEouaE So23-v111-11 REVISIN 1 ATTACHMENT 8.4 r

PAGE 1 OF 2 CPlTERIA FOR EMEICENCY CIOSE OUT CHECKLIST

'Ib be used by the Emergency Coordinator to evaluae a decision to terminate an existing ernergency. All the criteria shall be met.

Emergency Ooordinator:

Existing Emergency: No. -

CRITERIA MET.

CRITERIA

1. Initiating Cordition is:

a) Knoan and, b) Under control (stabilized) or c) Correctd or d) No longer at an EAL

.b( 2. Reactor Core is:

a) Operating Normally, or b) Is in Hot-Standby, or c) Is in Cold-Shutdoen, or d) Cold-Shutdcwn Urderway and anticipated within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. All Technical Specifications LCD's Are Met.

i

4. Radiation levels and Airborne CoTentrations in all areas are i

determined to be stable or decreasirg.

! 5. Uncontrolled ra$iological releases from the site are terminated.

i

6. Fires are extinguished, flooding conditions are urder control ard/or any site danage is urder control. .

7. Injured personnel have been transported to the hospital or have received medical treatment. j D

0 l

o 4

SAN WOFRE NUCIEM GENERATIN3 STATION EMEIGENCY PFCCEDURE S023-VIII-11 REnSI m I ATIAOMNT 8.4

.' UNITS 2 AND 3 e

PAGE 2 OF 2 i

4

' Other 8.

(Specify):

j 9. Approval to terminate energency No.

^

Date _

Time Dnergency Cbordinator

10. Notifications male to offsite agencies listed on Table 1 of Bnergency 4

i Procedure S023-VIII-16.

Date Time 4

O( NOTE After this checklist is completed and is not required for immediate use, forward it to the Station Services

! Manager (Administrative Leader if Emergency Organization i

is activated).

4 l

1 OOO

/D V

SAN ONOFRE NUCLEAR GENERATING S'l TOM EMERGENCY PROCEDURE S023-VIII-12 UNIT 2 AND 3 REVISION 1 Page 1 c OCT 9 1981 O UNUSUAL EVENT f 1.0 OBJECTIVE l 1.1 This procedure describes the .tio t n he event that an Unusual Event has be a t' Nuclear Generating Station Unit 2 an ates necessary pre planned response act procedures that prescribe the necessa Ms, Phbje \

'pi'i 1.2 The Emergency Coordinator (Watch Engineer, unti Of [e relieved by a designated alternate) is responsible o g @g W completion of the prescribed actions in this procedure. /,

Emergency Coordinator may delegate responsibility for perform of the prescribed tasks to available qualified SCE personnel,

._ p cept where otherwise specified in this procedure.

'~

("; rn F - E E, W f

2.0 REFERENCES

g { y'g { {$ g } (Qaf g 2.1 San Onofre Nuclear Generating Station Unit 2 and 3 Emer[bkcg pF Qn""

2.2 SONGS-2 and 3 Operating Procedures 4E SONGS-2 and 3 Health Physics Procedures CDM SITE 2.3 2.4 Title 10 Code of Federal Regulations Part 50, Appendix E 2.5 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants".

3.0 PREREQUISITES 3.1 An Unusual Event has been declared based on the occurrence of off normal events which could indicate a potential degradation of the level of safety of the plant. Events characterized as Unusual Events are described in Section 4 of the SONGS-2 and 3 Emergency Plan, and in Emergency Procedure 5023-VIII-11, " RECOGNITION AND CLASSIFICATON OF EMERGENCIES".

3.2 No releases of radioactive material requiring of f-site response or monitoring are are expected unless further degradation of the situation occurs.

4.0 PRECAUTIONS 4.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change, or more definitive ir< formation is obtained.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-12 UNIT 2 AND 3 REVISION 1 Page 2 0 4.0 PRECAUTIONS (continued) i 4.2 Emergency Coordinator responsibilities that may not be delegated include:

4.2.1 Decision to notify offsite emergency management agencies.

4.2.2 Making protective action recommendation as necessary to offsite emergency management agencies.

4.2.3 Classification of emergency event.

4.2.4 Determining the necessity for evacuation of personnel onsite.

4.2.5 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

5.0 CHECKOFF-LISTS 5.1 Attachment 8.1 Unusual Event Checklist

> 6.0 PROCEDURE 6.1 Announce to Control Room personnel that has

( (name) assumed the duties of Emergency Coordinator.

6.2 Announce or have announced the following message over the public address system:

" ATTENTION ALL PERSONNNEL, ATTENTION ALL PERSONNEL: AN UNUSUAL EVENT HAS BEEN DECLARED IN UNIT ____ . MEMBERS OF THE 2/3 ON-SHIFT EMERGENCY ORGANIZATION REPORT TO YOUR EMERGENCY DUTY STATIONS AS REQUIRED. ALL OTHER PERSONNEL'SHOULD CONTINUE WITH THEIR NORMAL DUTIES UNLESS FURTHER INSTRUCTIONS ARE GIVEN."

(Give a brief description of the event, if appropriate, and repeat the announcement)

NOTE: Notify the other Unit (s) watch Engineer of the Emergency.

6.3 Depending on the initiating emergency action level, ensure that the appropriate Emergency Operating Instructions have been implemented 6.4 Contact the Plant Superintendent and discuss plant status and which individuals maybe required to augment the onsite Emergency Ci Organization.

Within 90 minutes compose the Initial Notification Message per 6.5 procedure 5023-VIII-I6, " NOTIFICATIONS," for an Unusual Event.

4 SAN ONOFRE NUCLEAR GENERATING STATION r EMERGENCY PROCEDURE S023-VIII-12 UNIT 2 AND 3 REVISION 1 Page 3

.p 6.0 PROCEDURE (continued)

I 6.6 Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months direct the Shift Communicator to make the initial uffsite agency notifications required for an Unusual Event per procedure 5023-VIII-16 " NOTIFICATIONS".

6.7 If local offsite support (fire, ambulance, police, etc.) is required, direct the Shift Communicator to request such assistance in accordance with S023-VIII-37, "FIREFIGHTING";

S023-VIII-38, " CONTAMINATED INJURY" or the SONGS Security Plan as appropriate for the event.

6.8 Consider if augmentation of on-shift personnel is necessary or desireable. If so, direct the AWS switchboard operator (PAX 56291) to contact the specific individuals by implementing 5023-VIII-18 " NOTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONEL" NOTE: Emergency Centers Staffing Lists are available in Attachment 8.1 of 5023-VIII-18.

6.9 Assess plant conditions and respond appropriately.

6.10 As soon as sufficient information becomes available, compo:e a Follow-up Notification Message per procedure S023-VIII-16,

" NOTIFICATIONS." for an Unusual Event.

( 6.11 . Direct the Shift Communicator to transmit the Follow-up Notification Message to the same agencies who received initial notification.

f.12 Periodically, as additional information becomes available, and/or as conditions change, compose updated Follow-up Notification Messages and have them transmitted.

6.13 If the Interagency Network System or dedicated phone is not used, after 30 minutes, confirm that offsite agency verification has been made. If no verification, direct the Shift Communicator to repeat notification.

i 6.14 Based upon continuous assessment of plant conditions, either:

I 6.14.1 Escalate to higher class of emergency, or 6.14.2 When appropriate, close out the Unusual Event per i

procedure 5023-VIII-11, " RECOGNITION AND CLASSIFICATION OF EMERGENCIES".

6.15 Should reclassification of the emergency become neccessary, initiate the appropriate emergency procedure (5023-VIII-13, 14, or 15) 6.16 In the event of close out, compose a brief summary of the event and direct the Shift Communicator to transmit notification of close out to offsite agencies previously notified.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDbRE S023-VIII-12 UNIT 2 AND 3 REVISION 1 Page 4 4

'O 6.0 PROCEDURE (continued)

' Summary briefing of offsite authorities NOTE: ,

to follow within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of termination '

! or reduction.

7.0 RECORDS 7.1 Attachment 8.1 4

8.0 ATTACHMENTS 8.1 Unusual Event Checklist.

A

(/'_k.

K. P. BARR

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l HEALTH PHYSICS MANAGER 4 ~

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l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-12 UNIT 2 AND 3 REVISION 1 Page 1 of 1

. ATTACHMENT 8.1 UNUSUAL EVENT CHECKLIST (for use with Procedure S023-VIII-12)

1. Assumed Emergency Coordinator duties, announced Unusual Event over public address system, and implemented " NOTIFICATION" procedure.

NOTE: Offsite notification must commence within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of Accident Classification.

E. C. Signature Time Date

2. Type of offsite support requested (if applicable.):

E. C. Initial Time Date

3. Ple it Superintendent Notified.

E. C. Initial Time D4te 4 Offsite agency verification completed.

l O E. C. Initial Time Date

5. Closed out/ Escalated to i (alert, site, general emergency) based upon prcedure_SO23-VIII-11 " RECOGNITION AND CLASSIFICATION OF EMERGENCIES".

E. C. Initial Time Date NOTE After this checklist is completed and is not required for immediate use, forward it to the Station Services Manager (Adiminstrative Leader if Emergency Organization is activated.)

O

t GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-13 SAN ON F ' Page 1 UNIT 2 ..i REVISION 1 OCT 9 1981 g

/ ALERT 5 , as;. (

()-

1.0 OBJECTIVE S W[i

'(, $ \ g 1.1 This procedure describes the h N that an Alert has been declared at Generating Station Unit 2 and 3. This procs o% s necessary pre planned response actions and re fa procedures that prescribe the necessary supplementa 1.2 The Emergency Coordinator (Watch Engineer, until properly relieved by a designated alternate) is responsible for the

' completion of the prescribed actions in this procedure. The Emergency Coordinator may delegate responsibility for performance of the prescribed tasks to available qualified SCE personnel, except where otherwise specified in this procedure.

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station Unit 2 and 3 Emergency Plan RECEIVun 2.2 SONGS-2 and 3 Operating Procedures OCT 141981 n

M 2.3 SONGS-2 and 3 Health Physics Procedures CDM SITE

, 2.4 Title 10 Code of Federal Regulations Part 50, Appendix E 2.5 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergeacy Response Plans and Preparedness in Support of Nuclear Power Plants".

3.0 PREREQUISITES 3.1 An Alert has been declared based on the occurence of events which indicate an actual or potential degradation of the level of safety of the plant. Events classified as Alerts are described in Section 4 of the SONGS-2 and 3 Emergency Plan, and in Emergency Procedure S023-V111-11, "RECOMITION AND CLASSIFICATION OF EMERGENCIES".

-or-3.2 An Unusual Event had been declared and emergency measures are being performed; and on the basis of subsequent informat. ion or upon a deterioration in plant conditions, the condition has been remiassified as an Alert.

O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-13 REVISION I Page 2 UNIT'2 AND 3 4.0 , PRECAUTIONS 4.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classificatin is appropriately revised as conditions change, or more definitive information is obtained.

4.2 Emergency Coordinate- responsibilities that may not be delegated include:

4.2.1 Decision to notify offsite emergency management agencies.

4.2.2 Making protective action recommendations as necessary to offsite emergency management agencies.

4.2.3 Classification of emergency event.

4.2.4 Determining the necessity for evacuation of personnel onsite.

4.2.5 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

]J 5.0 CHECK-OFF LISTS

/ 5.1 Attachment 8.I Alert Checklist.

6.0 PROCEDURE Announce to Control Room personnel that has 6.1 (name) assumed the duties of Emergency Coordinator.

6.2 Announce or have announced the following message over the public address system:

"dTTENTIONALLPERSONNEL,ATTENTIONALLPERSONNEL: AN ALERT HAS BEEN DECLARED IN UNIT . ALL MEMBERS OF THE ON-SHIFT AND 2/3 ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL STANDBY FOR FURTHER INSTRUCTIONS."

(Give a brief description of the event, if appropriate, and repeat the announcement.)

NOTE: Notify the other Unit (s) Watch Engineer of the Emergency Depending on the initiating emergency action level, ensure that j 6.3 the appropriate Emergency Operating Instructions have been implemented.

O 6.4 Compose the Initial Notification Message per Procedure 5023-VIII-16, " NOTIFICATIONS", for an Alert:

6.5 Direct the Shift Communicator to make the initial offsite agency notifications required for an Alert per Procedure 5023-VIII-16

" NOTIFICATIONS".

SAN ONOFRE NUCLEAR' GENERATING STATION EM S GENCY PROCEOURE S023-VIII-13 UNIT 2 AND 3 REVISION 1 Page 3 i

'(G3 ' 1 6.0 PROCEDURE (continued)

(

6.6 If local off site support (fire, ambulance, police, etc.) is required, direct the Shift Communicator to request assistance in l accordance with 5023-VIII-37, "FIREFIGHTING"; SO23-VIII-38,

" CONTAMINATED thJURY" or the SONGS Security Plan as appropriate for the event.

6.7 Instruct the AWS switchboard operator (PAX 56291) to augment the en-shift staff aid activate the emergency response centers by implemer.'ing procedure 5023-VIII-18, " NOTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONEL". -The personnel notified will implement procedure 5023-VIII-17, " ACTIVATION AND OPERATION OF EMERGENCY CENTERS AND ORGANIZATIONS.".

NOTE: Emergency. Centers S;affing Lists are available in

- - - . Attachment 8.1 of S023-VIII-18, 6.8 If additional personnel havin'g specific skills are required, direct the AWS switchboard operator to contact the individuals.

J 6.9 Assess plant conditions and respond appropriately.

O(-

6.10 As soon as sufficient Information becomes available, compose a Follow-Up Notification Message per Procedure 5023-VIII-16,

" NOTIFICATION", for an Alert.

6.11 Direct the Shift Communicator to provide offsite agencies with the following:

6.11.1 Periodic plant status updates (at least every hour) while conditions are changing.

6.11.2 Periodic meteorological assessments (if any releases are occurring, include dose estimates).

NOTE: Use the follow-up Notification Form.

6.12 Verify that communications and documentation are maintained per Procedures 5023-VIII-16, " NOTIFICATION" S023-VIII-18

" NOTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONNEL"and 5023-VIII-51, " RECORD KEEPING".

6.13 If applicable, direct the Emergency Group Leader to dispatch emergency team (s) to investigate identified problem areas.

6.14 If the Interagency Network system or dedicated phone is not used, l after 30 minutes, confirm that offsite agency verification has i

p) u been made. If no verification, direct the Shift Communicator to repeat notification.

6.15 Based upon continuing assessment of plant conditions, either:

6.15.1 Escalate to a higher class of emergency, or

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCYPROCEDURhS023-VIII-13 REVISION 1 Page 4 UNIT 2 AND 3

{ 6.0 PROCEDURE (continued) 6.15 (continued) 6.15.2 Reduce classification to an unusual Event, or 6.15.3 When appropriate, close out the Alert, per procedure l 5023-VIII-11 " RECOGNITION AND CLASSIFICATION OF i EMERGENCIES.

6.16 Should reclassification of the emergency become necessary, initiate the appropriate procedure (5023-VIII-12, 14 or 15).

6.17 In the event of close out or reduction in classification, compose a brief summary of the event and direct the Shift Communicator to transmit notification of close out or reduction to offsite agencies previously notified.

NOTE: Summary briefing of offsite authorities to follow within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of close out or reduction.

7.0 RECORDS 7.1 Attachment 8.1 O 8o ^TT^c"se"Ts 8.1 Alert Checklist K. P. BARR HEALTH PHYSICS MANAGER DB:0088F/sss O

EMERGENCY PROCEDURE S023-VIII-13 SAN ONOFRE NUCLEAR GENERATING STATIONREVISION 1 Page 1 of 1

-UNITS 2 AND 3 ATTACHMENT 8.1 ALERT CHECKLIST (FOR USE WITH PROCEDURE 5023-VIII-13)

1. Assumed Emergency Coordinator duties, announced Alert over public address system, and implemented S023-VIII-16, " NOTIFICATIONS" procedure.

NOTE: Offsite notification must commence within 15 minutes of accident classification Time Date EC Signature

2. Type of offsite support requested (if applicable):

Time Date E.C. Initial

3. Offsite agency verification completed.

Time Date E.C. Initial

/

4. Closed out/ escalated to (site, general emergency) reduced to Unusual Event) based upon procedure 5023-VIII-11, O .

"ascoontrio" ^"o c'^sstitc^ Tion or esencesctes -

Time Date E.C. Initial NOTE:

After this checklist is completed and is not required for immediate use, forward it to the Administrative Leader.

O I

i

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-14 UNIT 2 AND 3 REVISION 1 Page 1 OCT 9 1981 p'" RECElym SITE EMERGENCY

' 4 00I 1.0 OBJECTIVE Jg 1.1 This procedure describes the acti that a Site Emergency has been dec 1 Generating Station Unit 2 and 3. This /O,j,

\

necessary pre planned response actions and I procedures that prescribe the necessary suppleme 1.2 The Emergency Coordinator (Watch Engineer, until properly relieved by a designated alternate) is responsible for the [/gg ccmpletion of the prescribed actions in this procedure. The Emergency Coordinator may delegate responsibility for performance of the prescribed tasks to available qualsfied SCE personnel, except where otherwise specifie ir,}higpro edure, g my s e ; a > : M }y

2.0 REFERENCES

g a

i [6L e%L

( g 2.1 San Onofre Nuclear Generating Station Units 2 and 3 Emergency Plan 2.2 SONGS-2 and 3 Operating Procedures 2.3 SONGS-2 and Health Physics Procedures 2.4 Title 10 Code of Federal Regulations Part 50, Appendix E 2.5 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants".

3.0 PREREQUISITES 3.1 A Site Emergency has been declared based on the occurrence of events which involve actual or likely failures of plant functions needed for the protection of the public. Events classified as Site Emergencies are described in Section 4 of the SONGS-2 and 3 Emergency Plan, and in Emergency Procedure S023-VIII-11,

" RECOGNITION AND CLASSIFICATION OF EMERGENCIES".

-or-3.2 An Unusual Event or Alert had been declared, emergency measures are being performed, and on the basis of subsequent information or upon a deterioration in plant conditions, the condition has been reclassified as a Site Emergency.

i

SAN ONOFRE NUCLEAR GENERATING STATIGN EMERGENCY PROCEDURE S023-VIII-14 Page 2

^

UNIT 2 AND 3 REVISION 1 O 4.0 PRECAUTIONS f

4.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change, or more definitive information is obtained.

4.2 The Site Emergency is the lowest emergency classification in which offsite protective actions for airborne release may be .

warranted. In consideration of the lead time necessary to implement offsite protective actions, notificattors to offsite authorities must be made as soon as possible following the initiating event and immediately after declaration of a Site Emergency.

t 4.3 EMERGENCY COORDINATOR RESPONSIBILITIES THAT MAY NOT BE DELEGATED INCLUDE:

4.3.1 Decision to notify offsite emergency man;gement agencies.

4.3.2 Making protective action recommendations as necessary to offsite emergency management agencies.

4.3.3 Classification of emergency event.

O'~f 4.3.4 Determining the necessity for evacuation of personnel onsite.

4.3.5 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

5.0 CHECK 0FF-LIS TS 5.1 Attachment 8.2 Site Emergency Checklist.

6.0 PROCEDURE 6.1 Announce to Control Room personnel that (name) has assumed the duties of Emergency Coordinator.

6.2 Announce or have announced the following message over the public address system, slowly:

" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: A SITE EMERGENCY HAS BEEN DECLARED IN UNIT . ALL MEMBERS OF 2/3 THE ON-SHIFT AND ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL REPORT TO YOUR DESIGNATED ASSEMBLY POINT. THERE WILL BE NO EATING, DRINKING OR SMOKING UNTIL FURTHER NOTICE." (Repeat)

[]) Notify the other Unit (s) Watch Engineer of the NOTE:

Emergency

~

n SAN ONOFRE NUCLEAR GENERATING STATION ' EMERGENCY PROCEDURE S023-VIII-14 REVISION 1 Page 3 UNIT 2 AND 3 4

6.0 _P_ROCEDURE (continued)

?

6.3 Depending on the initiating emergency action level, ensure that the appropriate Emergency Operating Instructions have been implemented.

6.4 Compose the Initial Notification Message per procedure 5023-VIII-16, " NOTIFICATIONS" for a Site Emergency.

6.5 Direct the Shift Communicator to make the initial offsite agency notifications required, for Site Emergency per procedure 5023-VIII-16, " NOTIFICATIONS".

6.6 If local offsite support (fire, ambulance, police, etc.) is required, direct the Shift Communicator to request such assistance in accordance with S023-VIII-37, "FIREFIGHTING";

5023-VIII-38, " CONTAMINATED INJURY" or the SONGS Security Plan as appropriate for the event.

6.7 Instruct the AWS swithboard operator (PAX 56291) to augment the on-shift staff and activate the Emergency Response Center by implementing procedure 5023-VIII-18 " NOTIFICATION OF ADDITIONAL EMERGERCY SUPPORT PERSONNEL". The personnel notified will implement procedure S023-VIII-17, " ACTIVATION AND OPERATION OF O e EMERGENCY CENTERS AND ORGANIZATIONS".

NOTE: Emergency Centers Staffing Lists are available in Attachment 8.1 of 5023-VIII-18.

NOTE: Parallel activation of the Emergency Operations Facility (EOF) will be underway by the corporate emergency organization.

6,8 If additional personnel having specific skills are required, direct the AWS switchboard operator to contact the individuals.

6.9 Implement procedure S023-VIII-33, " PLANT EVACUATION AND ACCOUNTABILITY" 6.10 Direct that the Radiolr

al Emergency Siren (Thunderbolt) be

sounded.

6.11 Direct the Administ ative leader to implement evacution of the beach per Attachment 8.1 6.12 If changes in onsite or offsite radiation levels are expected, direct the Health Physics Leader to:

6.12.1 Dispatch onsite and/or offsite monitoring teams per procedures SO23-VIII-24, " DIRECTION OF ONSITE

' EMERGENCY MONITORING" and S023-VIII-25, " DIRECTION OF

' 0FFSITE EMERGENCY MONITORING".

. i r

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-14 UNIT 2 AND 3 REVISION 1 Page 4 6.0 PROCEDURE (continued)

/ 6.12.2 Dispatch a Health Physics Technician to the' Assembly Point (s).

6.12.3 Initiate offsite dose projections per procedures S023-VIII 22, " SOURCE TERM DETERMINATION," and S023-VIII-23, " DOSE ASSESSMENTS."

6.13 If the emergency involves inplant radiation protection problems, direct the Health Physics Leader to:

6.13.1 Ir.olement procedures S023-VIII-31, " EMERGENCY EXPO $URE CONTROL", and 5023-VIII-44, " EMERGENCY CONTAMINATION CONTROL".

6.13.2 If appropriate, implement procedures S023-VIII-27,

" EMERGENCY ENVIRONMENTAL MONITORING", 5023-VIII-45,

" PERSONNEL AND VEHICLE MONITORING", and/or 5023-VIII-36, " THYROID PROPHYLAXIS".

6.14 As soon as sufficient information becomes available, compose a Follow-up Notification Message per procedure 5023-VIII-16,

" NOTIFICATIONS" for a Site Emergency.

6.15 Direct the Shift Communicator to provide offsite agencies with

{}; the following:

6.15.1 Periodic plant status updates (at least every hour) while conditions are changing.

6.15.2 Periodic meteorological assessments and dose estimates.

6.15.3 Release ano dose projections based on available plant condition information acd forsreable contingincies NOTE: Use the Follow-up Notification Form.

NOTE: Senior technical and management personnel should be made available for consultation with NRC and State representatives on a periodic basis.

6.16 Verify that communications and documentantion are maintained per procedures 5023-VIII-16, " NOTIFICATION," S023-VIII-18,

" NOTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONNEL" and S023-VIII-51, " RECORD KEEPING".

6.17 If applicable, direct the Emergency Group Leader to dispatch emergency team (s) to invesitgate identified problem areas.

6. *,8 If the Interagency Network System or dedicated line is not used, l

after 30 minutes confirm that offsite agency verification has been made. If no verification, direct the Shift Communicator to repeat notification. ,

SAN ONOFRE NUCLEAR GENERATING STATI0t! EMERGENCY PROCEDURE S023-VIII-14 UNIT 2 AND 3 REVISION 1 Page 5 V

6.0 PROCEDURE (continued)

' 6.19 Ensure that ongoing dose estimates are provided to offsite agencies if an actual release is in progress.

! 6.20 If a report of personnel accountability has not been received within 30 minutes of the time it was ordered, direct the Security Leader to obtain a status report.

6.21 If personnel are unaccounted for, initiate search and rescue operation per procedures 5023-VIII-39, " RESCUE" and S023-VIII-61, "RE-ENTRY", as applicable.

6.22 If site evacuation of non-essential personnel is deemed neccessary, implement procedure 5023-VIII-34, " SITE EVACUATION l

i AND ACCOUNTABILITY".

j 6.23 Evaluate dose projections and estimates. If neccessary, recommend protective actions for the offsite public in accordance with procedure S023-VIII-26, " RECOMMENDATIONS FOR OFFSITE PROTECTIVE MEASURES".

s 6.24 Based upon continuing assessment of plant conditions, either:

6.24.1 Escalate to a General Emergency, or 6.24.2 Reduce classification to a lower class, or 6.24.3 When appropriate close out the Site Emergency per procedure S023-VIII-11, "FCCOGNITION AND CLASSIFICATION OF EMERGENCIES".

t 6.25 Should reclassification of the emergency become neccessary, initiate the appropriate procedure (S023-VIII-12,13, or 15)

I 6.26 In the event of close out or reduction of classification, compose i

a brief summary of the event and direct the Shift Communicator to i transmit notification of close out or reduction to offsite agencies previously notified.

NOTE: Summary briefing of offsite authorities to follow within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of close out or reduction.

6.27 If applicable, impler.t.nt procedure 5023-VIII-62, "ACTIVATICN OF TriE RECOVERY ORGANIZATION".

7.0 RECORDS 7.1 Attachment 8.2 O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-14 i UNIT 2 AND 3 REVISION 1 Page 6

.O

! l 8.0 ATTACHMENTS

! 8.1 Evacuation of Public Beach 8.2- Site Emergency Checklist.

h 5

4 t

e i

4 K. P. BARR I HEALTH PHYSICS MANAGER 1,

i i

i

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DM: 0084F:sss t

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I 1

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4

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-14 UNIT 2 AND 3 REVISION 1 Page 1 of 1 ATTACHMENT 8.1

'(s) i EVACUATION OF PUBLIC BEACH (For use with procedure 5023-VIII-14) l

1. Ensure that the Radiological Emergency Siren (Thunderbolt) has completed it signal cycle.

l 2. Activate the public address system for the public beach areas adjacent to SONGS.

]l l 3. Make the following announcement:

j J

l " ATTENTION PLEASE; ATTENTION PLEASE; A STATE OF EMERGENCY EXISTS AT

SAN ONOFRE NUCLEAR GENERATING STATION. A PRECAUTIONARY EVACUATION OF 1 THIS BEACH HAS BEEN ORDERED. PLEASE LEAVE THE BEACH IN AN ORDERLY MANNER, AND PROCEE0 TO YOUR VEHICLE. UPON ARRIVAL AT YOUR VEHICLE, l

PLEASE DRIVE SAFELY OUT OF THE AREA"

4. Repeat the message two additional times.

5. Activate beach sirens, SP1 thru 5 per procedure (later).

I Signature Time Date 1

O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-14 UNIT 2 AND 3 REVISION 1 Page 1 of 2 O Att^ case"T 8 2 SITE EMERGENCY CHECKLIST (For use with procedure 5023-VIII-14) l

1. Assumed Emergency Coordinator duties, announced Site Emergency over public address system, and implemented S023-VIII-16, " NOTIFICATION" procedure. Sounded siren (YES / ND)

NOTE: Offsite notificatten must commance within 15 minutes of accident classification E. C. Signature Time Date

2. 5023-VIII-33, " PLANT EVACUATION AND ACCOUNTABILITY" Procedure implemented.

E. C. Initials Time Date

3. Beach Evacuation implemented.

E. C. Initials Time Date

4. Type of offsite support requested (if applicable.):

t E. C. Initials Time Date

5. Emergency centers and assembly areas activated.

E. C. Initials Time Date

6. Initiated onsite monitoring (YES / NO) Initiated offsite monitoring (YES / NO). Initiated dose projections (YES /

NO)

E. C. Initials Time Date

7. Directed Health Physics Leader to implement appropriate radiological controls.

E. C. Initials Time Date O

SANONOFRENUCLEERINEENSTINGSTATION EMERGENCY PROCEDURE S023-VIII-14 UNIT 2 AND 3

' "' # REVISION 1 Page 2 of 2 ATTACHMENT 8.2

*/' )

f SITE EMERGENCY CHECKLIST (Continued)

(For use with procedure 5023-VIII-14) i

8. Offsite agency verification completed. .

E. C. Initials Time Date

9. Accountability completed.

E. C. Initials Time Date 4

Evacuated non-essential personnel from site (if applicable) (YES 1

10.

/ NO).

I E. C. Initials Time Date

11. Reconmended t,he following offsite protective actions: (if applicable):

es .

J Vr i

4 E. C. Initials Time Date J

12. Closed out/ Escalated to General Emergency / reduced to (UNUSUAL EVENT / ALERT)

! based upon procedure 5023-VIII-11.

i 4

E. C. Initials Time Date i

NOTE: After this checklist is completed and is not required for immediate use, forward it to the Administrative Leader.

3 i O l

s SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15 UNIT 2 AND 3 REVISION 1 Page 1

' DCT 9 1981

.(a) GENERAL EMERGENCY 1.0 OBJECTIVE N 1.1 This procedure describes the actions o be ta 'heevhnk that a General Emergency has been de Iar rt 14 jggj Nuclear Generating Station Units 2 u6' designates necessary pre planned re

[s Q /t '

applicable procedures that prescribe the .

actions. 1 8 [ @* \

P 1.2 The Emergency Coordinator (Watch Engineer, until prope M relieved by a designated alternate) is responsible for the completion of the prescribed actions in this procedure. The Emergency Coordinator may delegate responsibility for performance of the prescribed tasks to available qualified SCE personnel, except where otherwise specified in this procedure, m r ? 1 -t Mf

2.0 REFERENCES

=

w m

=> R{

d n

w

3 r.

2.1 San Onofre Nuclear Generating Station Unit 2 and 3 Emergency Plan 2.2 SONGS-2 and 3 Operating Procedures 2.3 SONGS-2 and 3 Health Physics Procedures 2.4 Title 10 Code of Federal Regulations Part 50, Appendix E

]

2.5 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants".

3.0 PREREQUISITES 3.1 A General Emergency has been declared based on the occurrence of events which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Events classified as General Emergencies are described in Section 4 of the SONGS-2 and 3 Emergency Plan, and in Emergency Procedure 5023-VIII-11. " RECOGNITION AND CLASSIFICATION OF EMERGENCIES".

-or-3.2 A lesser emergency had been declared, emergency measures are being performed, and on the basis of subsequent information or upon a deterioration in plant conditions, the condition has been reclassified as a General Emergency.

I (vD l

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15 REVISION 1 Page 2 UNIT 2 AND 3 0 4.0 PRECAUTIONS 4.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change, or more definitive information is obtained.

4.2 The General Emergency classification includes actual or imminent events for which offsite protective actions will be needed. In consideration of the lead time necessary to implenent offsite protective actions, notifications, to offsite aut'norities must be made as soon as possible following the initiating event and immediately after declaration of a General Emergency.

t 4.3 EMERGENCY COORDINATOR responsibilities that may not be delegated include:

4.3.1 Decision to notify offsite emergency management agencies.

4.3.2 Making protective action recommendations as necessary to offsite emergency management agencies.

i l 4.3.3 Classification of emergency event.

O 4.3.4 Determine the necess4tv fer evacuat4en of personnei onsite. ,

4.3.5 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

1 5.0 CHECK 0FF-LIS TS 5.1 Attachment 8.2 General Emergency Checklist 6.0 PROCEDURE i

6.1 Announce to Control Room personnel that (name) has assumed the duties of Emergency Coordinator. (if not done in earlier emergency condition)

! 6.2 Depending on the initiating emergency action level, ensure that the appropriate Emergency Operating Instructions have been implemented.

6.3 Announce or have announced the following message over the public address system, slowly:

" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: A GENERAL EMERGENCY HAS BEEN DECLARED IN UNIT . ALL MEMBERS OF THE 2/3 ON-SHIFT AND ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL REPORT TO YOUR DESIGNATED ASSEMBLY POINT. THERE WILL BE NO EATING, DRINKING, OR SMOKING UNTIL FURTHER NOTICE."

j l

l SAN ONOFRE NUCLEAR GENERATIh3 STATION EMERGENCY PROCEDURE S023-VIII-15 l UNIT 2 AND 3 REVISION 1 Page 3 <

l) 6.0 PROCEDURE (c~ontinued) e NOTE: Notify the other Unit (s) Watch Engineer of the Emergency 6.4 Compose the Initial Notificatica Message per procedure 5023-VIII-16, " NOTIFICATIONS" for a General Emergency.

6.5 Direct the Shift Communicator to make the initial offsite agency notifications required, for General Emergency per procedure 5023-VIII-16, " NOTIFICATION".

6.6 If local offsite support (fire, ambulance, police, etc.) is required, direct the Shift Communicator to request such assistance in accordance with S023-VIII-37, "FIREFIGHTING";

S023-VIII-38, " CONTAMINATED INJURY" or the SONGS Security Plan as appropriate for the event.

3 6.7 Direct the AWS switchboard operator (PAX 56291) to augment the on-shift staff and activate the Emergency Response Centers by implementing procedure 5023-VIII-18 " NOTIFICATION OF ADDITIONAL EMERGERCY SUPPORT PERSONNEL". The personnel notified will

! implement procedure S023-VIII-17, " ACTIVATION AND OPERATION OF EMERGENCY CENTERS AND ORGANIZATIONS."

( ,

NOTE: Emergency Centers Staffing Lists are available in Attachment 8.1 of S023-VIII-18.

4 NOTE: Parallel activation of the Emergency Operations Facility (EOF) will be underway by the corporate emergency organization.

6.8 If additional personnel having specific skills are required, direct the AWS switchboard operator to contact the individuals.

6.9 Determine if site evacuees are to be sent home or to one of the 4 Offsite Assembly Areas, if so, use current meteorological data, to determine which Evacuation Route and Offsite Assembly Area (North or South) is furthrest from the plume.

6.10 Implement procedure S023-VIII-34, " SITE EVACUATION AND ACCOUNTABILITY" 6.11 Direct that the Radiological Emergency Siren (Thunderbolt) be sounded.

6.12 Direct the Administrative Leader to implement evacuation of the beach per Attachment 8.1 0

l l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15 UNIT 2 AND 3 REVISION 1 Page 4 6.0 PROCEDURE (continued) 6.13 If changes in onsite or offsite radiation levels are expected, direct the Health Physics Leader to:

I 6.13.1 Dispatch onsite and/or offsite monitoring teams per procedures S023-VIII-24, " DIRECTION OF ONSITE .

EMERGENCY MONITORING" and S023-VIII-25, " DIRECTION OF 0FFSITE EMERGENCY MONITORING".

6.13.2 Dispatch a Health Physics Techinician to the Offsite Assembly Point (s).

6.13.3 Initiate offsite dose projections per procedures 5023-VIII-22, " SOURCE TERM DETERMINATION," and 5023-VIII-23, " DOSE ASSESSMENT."

6.14 If the emergency involves inplant radiation protection problems, direct the Health Physics Leader to:

6.14.1 Implement procedures 5023-VIII-31, " EMERGENCY EXPOSURE CONTROL", and 5023-VIII-44, " EMERGENCY CONTAMINATION CONTROL".

p 6.14.2 If appropriate, implement procedures S023-VIII-27,

\ " EMERGENCY ENVIRONMENTAL MONITORING", 5023-VIII-45,

" PERSONNEL AND VEHICLE MONITORING",and/or 5023-VIII-36, " THYROID PROPHYLAXIS".

6.15 As soon as sufficient information becomes available, compose a

' follow-up Notification Message per procedure S023-VIII-16,

" NOTIFICATIONS" for a Site Emergency.

6.16 Direct the Shift Communicator to provide offsite agencies with the following:

6.16.1 Periodic plant status updates (at least every hour) while conditions are changing.

6.16.2 Periodic meteorological assessments and dose estimates.

I 6.16.3 Release and dose projections based on available plant condition information and forseeable contingincies NOTE: Use the Follow-up Notification Form.

NOTE: Senior technical and management personnel should be made available for consultation with NRC and State representatives on a periodic i basis.

O l 1

i 1

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15 REVISION 1 Page 5 UNIT 2 AND 3 6.0 PROCEDURE (continued) 6.17 Verify that communicaticr.s and documentation are maintained per ,

procedures SO23-VIII-16, NOTIFICATIONS S023-VIII-18;

" NOTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONNEL" and S023-VIII-51, " RECORD KEEPING" .

6.18 If applicable, direct the Emergency Group Leader to dispatch emergency team (s) to investigate identified problem areas.

6.19 If the Interagency Network System or dedicated line is not used, after 30 minutes confirm that offsite agency verification has been made. If no verification, direct the Shift Communicator to repeat notification.

6.20 Ensure that ongoing dose estimates are provided to offsite agencies if an actual release is in progress.

6.21 If a report of personnel accountability has not been received within 30 minutes of the time it was ordered, direct the Security Leader to obtain a status report.

6.22 If personnel are unaccounted for, initiate search and rescue operations per procedures S023-VIII-39, " RESCUE" and S023-VIII-61, "RE-EN1RY", as applicable.

Q 6.23 Evaluate dose projections and estimates. If neccessary, recommend protective actions for the offsite public in accordance with procedure 5023-VIII-26, " RECOMMENDATIONS FOR OFFSITE PROTECTIVE MEASURES".

< 6.24 Based upon continuing assessment of plant conditions, either:

l 6.24.1 Reduce classification to a lower class, or 6.24.2 When appropriate close out the General Emergency per procedure 5023-VIII-11, " RECOGNITION AND CLASSIFICATION OF EMERGENCIES".

6.25 Should reclassification of the emergency become neccessary, initiate the appropriate procedure (5023-VIII-12,13 or 14) 6.26 In the event of close out or reduction of classification, compose a brief summary of the event and direct the Shift Communicator to transmit notification of close out or reduction to offsite agencies previously notified.

NOTE: Summary briefing of offsite authorities to follow within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of close out or reduction.

6.27 If applicable, implement procedure 5023-VIII-62, " ACTIVATION OF p\ THE RECOVERY ORGANIZATION".

1

SAN ONOFRE NUCLEAR GENERATING 3TATION EMERGENCY PROCEDURE S023-VIII-15 UNIT 2 AND 3 REVISION 1 Page 6 7.0 RECORDS !

7.1 Attachment 8.2 8.0 ATTACHMENTS l

8.1 Evacuation of Public Beach 8.2 General Emergency Checklist.

K. P. BARR HEALTH PHYSICS MANAGER DM:0086F:sss i

O O

a SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15 UNIT 2 AND 3 REVISION 1 Page 1 of 1 q\g ATTACHMENT 8.1

, EVACUATION OF PUBLIC BEACH (For use with procedure S023-VIII-15)

1. Ensure that the Radiological Emergency Siren (Thunderbolt) has ;

completed its signal cycle.

2. Activate the public address system for the public beach areas adjacent to SONGS.

3. Make the following announcement:

" ATTENTION PLEASE; ATTENTION PLEASE; A STATE OF EMERGENCY EXISTS AT

. SAN ONOFRE NUCLEAR GENERATING STATION. A PRECAUTIONARY EVACUATION OF THIS BEACH HAS BEEN ORDERED. PLEASE LEAVE THE BEACH IN AN ORDERLY 4 MANNER, AND PROCEED TO YOUR VEHICLE. UPON ARRIVAL AT YOUR VEHICLE, PLEASE DRIVE SAFELY OUT OF THE AREA" i 4. Repeat the message two additional times.

5. Activate beach sirens, SP1 thru 5 per procedure (later).

O Signature Time Date l

I

l l

l

1 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15

N UNIT 2 AND 3 REVISION 1 Page 1 of 2 l '(N,,) ATTACHMENT 8.2 GENER.4L EMERGENCY CHECKLIST (For use with procedure 5023-VIII-15)

1. Assumed Emergency Coordinator duties, announced General Emergency over _

public address system, and implemented S023-VIII-16, " NOTIFICATION" procedure. Sounded siren (YES / NO)

NOTE: Offsite notification must commence within 15 minutes of accident classification.

E. C. Signature Time 'Date

! 2. S023-VIII-34, " SITE EVACUATION AND ACCOUNTABILITY" Procedure impicmented.

4 E. C. Initials Time Date'

3. Beach Evacuation implemented.

E. C. Initials Time Date i 4. Type of offsite support requested (if applicable.):

E. C. Initials Time Date

5. Emergency centers and assembly areas activated.

E. C. Initials Time Date

6. Initiated onsite monitoring (YES / NO) Initiated offsite 3 monitoring (YES / NO). Initiated dose projections (YES /

NO) i E. C. Initials Time Date

7. Directed Health Physics Leader to implement appropriate radiological controls.

E. C. Initials Time Date i

O

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I SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-15 l UNIT 2 AND 3 REVISION 1 Page 2 of 2 l

, .( ATTACHMENT 8.2

'~

GENERAL EMERGENCY CHECKLIST (Continued)

(For use with procedure 5023-VIII-15)

7. Offsite agency verification completed.

E. C. Initials Time Date

8. Accountability completed.

E. C. Initials Time Date

9. Recommended the following offsite protective actions: (if applicable):

E. C. Initials Time Date

10. Closed out/ reduced to unusual event / alert / site emergency O based upon procedure SO23-VIII-11. " RECOGNITION AND CLASSIFICATION OF EMERGENCIES".

E. C. Initials Time Date NOTE: After this checklist is completed and is not required for immediate use, forward it to the Administrative Leaders.

I O

_ _ - - . ._ .. _ a

f

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l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 REVISION 1 Page 1 n}

( UNITS 2 AND 3 V '0CT 9 1981

' NOTIFICATION ,

E Cu g d~ j 1.0 OBJECTIVE 9D7

m'hpj 1.1 This procedure provides instructi f8ffp 'ifk M EED authorities and emergency respon i 'i s .

situations. Notification of SCE per 9( M' W N Emergency Procedure 5023-VIII-18, "NOTIFI IS81

/

EMERGENCY SUPPORT PERSONNEL". Notification o organizations is required for any of the four emergenc classifications. 77 1.2 The Emergency Coordinator is responsible for implementation of the actions described in this procedure. The Shift Comunicator is designated to provide notification to Offsite agencies.

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station Unit 2 and 3 Emerger.cy Plan.

2.2 NUREG-0654/ FEMA-REP 1: " Criteria for Preparation and Evaluation of Radiological Emergency Response P1ans and Preparedness in Support of Nuclear Power Plants."

2.3 Emergency Procedure 5023-VIII-12 " UNUSUAL EVENT".

2.4 Emergency Procedure S023-VIII-13 " ALERT".

2. 5 Emergency Procedure S023-VIII-14 " SITE EMERGENCY".

2.6 Emergency Procedure 5023-VIII-15 " GENERAL EMERGENCY".

3.0 PREREQUISITES 3.1 An emergency condition has been declared at SONGS-2 or 3 as provided in the SONGS-2 and 3 Emergency Preparedness Plan and Emergency Procedure S023-VIII-11 RECOGNITION AND CLASSIFICATION OF EMERGENCIES" 3.2 An existing emergency condition has been reclassified to a higher emergency category, and/or, a significant deterioration in conditions has occurred.

3.3 The energency situation has been corrected and the emergency tenninated.

O l

1 EMERGENCY PROCEDURE S023-VIII-16 SAN ONOFRE NUCL' EAR GENERATING STATION Page 2 REVISION 1 UNITS 2 AND 3

,. 4. 0 PRECAUTIONS 4.1 No press releases on the incident shall be made prior to completion of all notifications, and will be made only by Southern California Edison public infomation personnel.

i 1

! 5.0 CHECK-OFF LIST .

5.1 Check-off List #1 Emergency Notification Call List I

(Attachment 8.1) 5.2 Check-off List #2 Initial Notification Fom - Unusual Event

! (Attachment 8.2) 4 5.3 Check-off List #3 Initial Notification Fom - Alert

! (Attachment 8.3) l 5.4 Check-off List #4 Initial Notification Fom - Site Emergency (Attachment 8.4)

5.5 Check-off List #5 Initial Notification Fom - General Emergency f (Attachment 8.5)

O' se chec*-eff List fe rollo -uP #etific tien ro - (attec+ rent 8.e>

I. 6.0 PROCEDURE l

l 6.1 Upon receipt of the Initial Notification Fom from the Emergency Coordinator, proceed as follows:

l 6.1.1 Using attachment 8.1 Table 1 " EMERGENCY NOTIFICATION CALL LIST" Contact each organization or individual on the Interagency Network System by dialing the i

individual number listed. If the telephones are i inoperative, utilize the specified alternate.

1 1 NOTE: For example San Clemente can be reached by dialing

then 25 i

6.1. 2 When the party answers note tha name of the ,

individual contacted and the time of the contact on -

i Attachment 8.1

~

s 3 6.1.3 Read the introduction paragraph on the notification , , i l

fom and pause to allow the individual to obtain his -

copy of the fom, or blank paper on which to record' ,

' the notification.

6.1.4 Read the text of the notification, emphasizing the variable infomation .

6.1.5 Have the message read back, and if necessaryi correct .

.any errors. Check for accuracy during the readback.

9

.. - - - - - - - . - - . . , . . - - . ..n -- - -- - - - - - , . , - - , . . , .

EMERGENCY PROCEDURE S023-VIII-16 SAM ONOFRE NUCLEAR GENERATING STATION REVISION 1 Page 3 UNITS 2 AND 3 6.0 PROCEDURE (Continued) r 6.1 (Continued) 6.1.6 Direct the party contacted to notify the appropriate individuals in their organizations in accordance with the organization's emergency plans. Remind the party contacted that a call-back is required from the designated individual if the dedicated emergency Interagency Network System line (yellow phone) is not used.

6.1.7 Proceed to the next party on the call-list.

6.1.8 If a party cannot be contacted in a reasonable period of time, bypass that party and proceed down the list.

After the other notifications are complete, re-a ttempt to contact any bypassed part.es. If a r

party still cannot be reached notify the Emergency Coordinator.

6.1.9 Develop a completed " Follow Up Notification Fom "

Attachment 8.6 by consulting with the Emergency Coordinator and other key emergency leaders. (See NOTE 6.1.10) 6.1.10 When any parties call back for furt'her infomation, note the time and the name of the individuals on the c all-l i st. Provide the infomation available from the current Follow-up Notification Fom. If the party requests infomation not on the fom, make reasonable efforts to obtain and relay the infomation, if consistent with completing notifications. Maintain a log of all lines of comunications.

NOTE: For follow up notification all agencies may be reached at one time by dialing

then 99.

6.1.11 If a party not specified on the call-list requests infomation, refer the party to either the SCE Public Relations staff, or to the local emergency services organization in his/her comunity.

6.1.12 Keep a " Log of Events" per procedure S01-VIII-51 "Recordkeeping". Obtain assistance from other available TSC Personnel during times of heavy comunication.

p 6.1.13 Refer to Attachment 8.7 if additional offsite Q emergency response assistance is needed.

EMERGENCY PROCEDURE S023-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATION REVISION 1 Page 4 UNITS 2 AND 3 J.0 PROCEDURE (Continued) 6.2 Check-List Numbering 6.2.1 De Comunicator shall number all check-lists by filling in two blanks provided as given in the following example:

6.2.2 The first emergency event of the Year 1981 was an earthquake, classified as an Unusual Event.

Therefore, it would be numbered as follows:

UE 81 6.2.3 If on that same day more earthquakes occurred with ground accelerations >0.25 g, the event would be classified as an Alert (in accordance with 5023-VIII-11) and numbered as follows:

ALERT 81 6.2.4 As shown above, each emergency condition, regardless of the level of classification, are numbered sequentially frcm January 1 thmugh December 31 of each year.

y NOTE: Dis number is not to be confused with the event classification number used on line number 2 of each initial notification fom.

This number is used to track the number of emergency events and for a file number in CDM.

7.0 RECORDS 7.1 After completion of checklists ard when they are no longer required for imediate use, forward to the Administrative Le ader (Station Services Manager if Emergency Organization is not activated.)

P.0 ATTACff4ENTS 8.1 Emergency Notification Call-List (Table 1)

- 8.2 Unusual Event - Initial Notification Form 8.3 Alert - Initial Notification Fom O

v

4 EMERGENCY PROCEDURE S023-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATION Page 5 UNITS 2 AND 3 REVISION 1 l

1

,8.0 ATTACWENTS (continued) 8.4 Site Emergency - Initial Notification Fom 8.5 Ger,eral Emergency - Initial Notification Form 8.6 Follow-up Notification Fom 8.7 Offsite Assistance Telephone Numbers.

J5&-

r.BmR HEALTH PHYSICS MANAGER JLR:0106F:jhm O

EMERGENCY PROCEDUR -VIII-16 SAN Oh NUCLEAR GENERATING STATION REVISION 1 Page 1 of 2 UNIT 2 AND 3 Attachment 8.1 EMERGENCY EVENT:

(NOTE 1) ,

TABLE 1 DATE:

EMERGENCY NOTIFICATION CALL-LIST TIME: __

NAME OF CONTACT TIME /INIT._ CALL-BACK TIME PRIMARY ALTERNATE (Only 1r not r.9 titled ORGANIZATION / INDIVIDUAL by Dedicated Emergency Phone)

(NOTE 2) ~ . _

Pendleton Coast Area Office *24

- California Dept. of Parks and Recreation

25 City of San Clemente Camp Pendleton - U.S. *23 Marine Corps Base ;

Orange County Control One *27 (28).

San Diego County Office of *29 Disaster Preparedness - Station ,

City of San Juan Capistrano *26 California Highway *32 Patrol - San Diego __

Callfornia Highway *30 -

Patrol - Santa Ana SCE Dispatcher for Edison Direct Line Personnel Hotification (Request offsite agency notification, if necessary)

(Note 4)

\ u ,

C -

SAN UNIT E NUCLEAR GENERATING STA110tl ND 3

$ EHERGENCY PROCED REVISI0il 1 23-V111-nu 93 2 of 2 Attachment 8.1 TA3LE 1 EMERGENCY NOTIFICATION CALL-LIST (continued)

PAGE #2 ORGANIZATION / INDIVIDUAL PRIMI?Y ALTERNATE NAME OF CONTACT TIME /INIT. LALL-BACK TIME (Only it not not1tTed by Dedicated Einergency Phone)

~

(NOTE 2)

U.S. Nuclear Reguletory Direct Line Commission Incident Response ;

Center - Bethesda j (NOTE 3) l Anerican Nuclear Insurers Direct Line (NOTE 5)

California Office of Emergency Services (See Note 4) ,

NOTE 1: See 6.2.3 for instructions, Example: ALERT 81 NOTE 2: All dedicated Emergency Phones can be sTm'uTtaneousTy contacted by dialing *99 call 86181 for Yellow Phone Phone problems (circuit 5929) ,

NOTE 3: Request that the Bethesda NRC Center patch your call into the Region V Office.

NOTE 4: Have the SCE Dispatcher contact the California Office of Emergency Services (C0ES). This should be verfified.

NOTE 5: Required at Site and General Emergency only.

r \ . n

EMERGENCY PROCEDURE S023-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATION PAGE 1 of 3 UNIT 2 AND 3 PEVISION 1 Attachment 8.2 e NOTE: Notification required within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of declaration of an Unusual Ev ent.

AM Time: PM l

Date:

UNUSUAL EVENT - INITIAL NOTIFICATION FORM

- UE NO. -

calling.

"This is the San Onofre Nuclear. Generating Station Unit 2/3 ~

(Name)

The following is a notification of an Unusual Event. Record the infomation to follow on your fom."

1. There has been an Unusual Event at the San Onofre Nuclear Generating

, Station, Unit 1 declared at _ Uime)

2. Event no: listed on the back of the page describes the nature of the occurrence.

3. There been a release of radioactivity to the .

HAS/HAS NOT/NA ' a potential The release __been stopped. There HAS/HAS NOT/NA 15/I5 NOT/NA for an additional release.

4. There is no need for protective action beyond the site boundary. Stand by until further notification is received.

5. Implement your Standard Operating Procedures for an Unusual Event (UE).

6. Call to verify this message. (NA if Intragency Network System is used. )

7. San Clemente, please read back this message. All other jurisdictions, check for accuracy.

EMERGENCY PROCEDURE Sun-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATION REVISION 1 Page 2 of 3 UNIT 2 AND 3 Attachment 8.2' SIMPLIFIED DESCRIPTION - UNUSUAL EVENT EVENT N O.

1. Minor release of radioactive liquid exceeding Instantaneous Technical Specification Limit

2. Minor release to gaseous radioactivity exceeding Instantaneous Technical Specification Limit

3. Hinor loss of control over radioactive material - confined to a single room or facility

4. Reactor coolant system temperature low - shutdown of p1pnt required by procedures

5. Reactor coolant system pressure high - shutdown of plant required by procedures 6a. Reactor coolant system leak exceeding operating limit - plant shutdown required by procedures 6b. Steam Generator tube leak exceeding operating limit - plant shutdown required by procedure

7. Radioactivity in reactor coolant system above limit - plant shutdown required by procedure

8. Reactor coolant system safety or relief valve failure to close

9. Temperature of reactor coolant system high - plant shutdcwn required by procedures

10. Reactor coolant system pressure low - procedures require plant shutdown

11. Safety Injection System started to provide auxiliary core cooling

12. Minor loss of containment integrity requiring plant shutdown

13. Loss of engineered safety feature requiring plant shutdown

~ 14. Loss of fire protection feature requiring plant shutdown

15. Loss of control room indicators, annunciators, or alams

16. Toxic or flamable gaso released onsite or nearby environs ,

17. Loss of onsite backup AC power generation capacity

18. L ss o' 'll offsite AC power

19. Ysite Tornado. Probable impact on station

EMERGENCY PROCEDURE S0?3-VIII-16 REVISION l Page 3 of 3 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 AND 3 Attachment 8.2 -

SIMPLIFIED DESCRIPTION - UNUSUAL EVENT (Continued)

EVENT NO. l

20. HJrricane with probable affect on station 21 . Earthquake detected on plant seismic instruments

22. Explosion within security protected area - no significant damage to station

23. Not assigned

24. Floor or Tsunami warning - probable affect on operations

25. Aircraft crash onsite - outside of protected area

26. Fire requiring activation of plant fire brigade - not under control within 10 minutes 27.

Contaminated / injured person transported by ambulance to local hospital for treatment

28. Security compromise

29. Other

1 SAN ONOFRE NUCLEAR GENERATING STATIDW EMERGENCY PROCEDURE S023-VIII-16 REVISION 1 Page 1 of 3 l UNIT 2 AND 3

" Attachment 8.3 10TE:

Notification to begin as soon as possible but no later than 15 minutes

after Accident Classification.

i AM f Time: PM i

l Date:

ALERT - INITIAL NOTIFICATION FORM ALERT NO.

"This is the San Onofre Nuclear Generating Station Unit 2/3 (Name) calling. The following is a notification of an Alert. Record the

)

infonnation to follow on your form."

1. There has been an incident classified as an Alert at the. San Onofre Nuclear Generating Station, Unit 2/3 declared at t11me)

2. Event no: listed on the back of the page describes the nature of r

l \ the occurrence.

( 3. There been a release of radioactivity to the .

HAS/HA5 NOT The release been stopped. There a potential HAS/HAS NOT/NA I5/I5 NOT/NA for an additional release.

4. There is no need for protective action beyond the site boundary. Maintain Alert status until further notification.

< 5. Implement your Standard Operating Procedures for an Alert Event.

6. Call to verify this message. (NA if Interagency Network System is used.)

' 7. San Clemente, please read back this message. All other jurisdictions, check for accuracy.

O .

El'.EllCluCY ha)Cii,06.t. S023-Vl! .

REVISION 1 Page 2 of 3 SAN ONOFRE HUCLEAR GENERATING STATION ATTACH 4ENT 8.3 UNIT 2 AND 3 SIMPLIFIED DESCRIPTION - ALERT EVENT NO.

1.

Release of radioactive liquid exceeds 10 times the Instantaneous Technical Specification Limit 2.

Release of gaseous radioactivity exceeds 10 times the Instantaneous Technical Specific 3.

Accident resulting in unexpected inplant radiation levels greater than 1000 times nonnal 4a.

Reactor coolant system leak greater than 50 gallons per minutes but less than 250 gallons p 4b.

Steam generator tube leak greater than 50 gallons per minute bus less than 250 gallons pe 5.

Main steam line break - concurrent with steam generator tube leak greater than 10 gallons p

6. High radioactivity in reactor coolant system - possible fuel failure 7.

Reactor not shutdown after valid shutdown signal (s)

8. Capability to place reactor in cold shutdown condition lost

9. Loss of all centrol room alanns (annunciators) - for more than 5 minutes 10.

Control room evacuation anticipated or required - shutdown system control established at remote locations 11.

Toxic or flannable gases present inside facillty - access to certain locations impaired

12. Security compromise

13. Temporary loss of offsite power and onsite backup AC power generation capability

14. Loss of onsite vital DC power

15. Tornado impact on vital plant structures

16. Hurricane winds onsite up to near design speed (100 mph)

17. Earthquake greater than operational basis with known damage to facility affecting operation .

EMERGENCY PROCEDURE S023-VIII-16 SAN ON0FRE NUCLEAR GENERATING STATION REVISION 1 Page 3 of 3 UNIT 2 AND 3 ATTACHMENT 8.3 SIMPLIFIED DESCRIPTION - ALERT EVENT __

NO.

18. Fire onsite with significant potential for affecting safety systems

19. Explosion onsite damaging facility and affecting operation

20. Aircraft or missile strikes a plant structure inside protected area 21 a. Flood or Tsunami cau:es known damage to facility affecting operation 21 b. Other - Specify:

w.,

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 REVISION 1 Page 1 of 3 UNIT 2 AND 3

.Q' Attachment 0.4

' 40TE: Notification G. 5egin as soon as possible but no later than 15 minutes after Accident u assification.

AM Time: PM Date:

SITE EMERGENCY - INITIAL NOTIFICATION FORM SITE EMER NO.

"This is the San Onofre Nuclear Canerating Station Unit 2/3

( Name) calling. The following is a notification of a 54te Emergency. Record the infomation to follow on your fonn."

1. There has been an incident classified as a Site Emergency at the San 'Onofre Nuclear Generating Station, Unit 2 / 3 declared at .

(TimeJ

2. Event no: listed on the back of the page describes the nature of the occurrence.

3. There been a release of radioactivity to the _ .

HAS/HAS NOT The release been stopped. There a potential HA5/HA5 NDl/ 15/15 NUI/

for an additional release.

4. There a need for protective actions beyond the site boundary.

15/I5 NDI Af fected areas include sectors , , ,

, , . The reconsnended protective action is I

Maintain Site Emergency status until further notification.

5. Implement your Standard Operating Procedures for a Site Emergency. )

Call to verify this message. (NA if Interagency Network system 6.

phone is used.

7. San Clemente, please read back this message. All other jurisdictions, check for accuracy.

~

EMERGENCY PR9CEDURE S023-VIII-16 SAN GNOFRE NUCLEAR GENERATING STATION Page 2 of 3 REVISION 1 UNIT 2 AND 3 Attachment 8.4 SIMPLIFIED DESCRIPTION - SITE EHERGENCY EVENT _

NO.

1. dirborne release corresponds to > 50nr/hr wholebody (or 250 mr/hr thyroid) for 1/2 hour or 500 mr/hr t hole body (or 2500nr/hr thyroid) for 2 minutes at the site boundary for adverse meteorology.

2. Major damage to spent fuel due to fuel handling accident.

3. Uncontrolled decrease in fuel pool water level exposes fuel.

4a. Leak in reactor coolant system greater than capacity of makeup pump.

4b. Steam generator tube leak greater than 250 ga11cns.per minute with loss of offsite power.

5. Main steam line break - concurrent with 50 gallons per minute steam generator tube leak and indication of fuel failure.

6. Degraded reactor core. Possible loss of coolable core geometry.

7. Loss of capability to achieve hot standby status.

8. Loss of all Control Room alanns and uncontrolled plan transient occurs.

9. Evacuation of Control Room required - control of plant using local stations not established within 15 minutes.

10. Toxic or flammable gases in vital plant areas restricting necessary access.

11. Security compromised - inninent loss of physical control of plant to outside persons.

12. Loss of all offsite power and all onsite AC power for more than 15 minutes.

13. Loss of vital DC power for more than 15 minutes.

14. Winds in excess of design level site instrumentation g\ g- '

SAN ON0FRC NUCLEAR GENERATING STATION EMFRGENCY PROCEDURE S023-VIII-16 UNIT 2 AND 3 REVISION 1 Page 3 of 3 Attachment 8.4 SIMPLIFIED DESCRIPTION - SITE EMERGENCY .

EVENT N O. _

15. Earthquake greater than safe shutdown level - severe damage to safe shut:fown equipment.

16. Fire affecting safe shutdown of the plant.

17. Explosion causing severe damage to safe shutdown equipment

18. Aircraft crash onsite.affecting vital structures and/or safety systems by impact or fire 19a. Flood or Tsunamic causes severe damage to safe shutdown equipment.

19b. Other (Explain) e G O~

l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 3 REVISION 1 Page 1 of 2

- j UNIT 2 AND 3 Attachnent 8.5 7'OTE: Notification to begin as soon as possible but no later than 15 minutes after Accident Classification.

AM Time: PM Date:

GENERAL EMERGENCY - INITIAL NOTIFICATION FORM GEN EMER NO.

"This is the San Onofre Nuclear Generating Station Unit 2/3 (Name) calling. The following is a notification of a General Emergency. Record the infomation to follow on your fom."

1. There has been an incident classified as a General Emergency at the San Onofre Nuclear Generating Station, Unit 2/3.

2. Event No: listed on the back of the page describes the nature of the occurrence.

O. 3 There HAS/HAS NOT been a release of radioactivity to the .

The release been stopped. There & potential HA5/HAS NOT/ 15/15 NUl/

for an additional release.

4. There a need for protective actions beyond the site boundary.

Af fected areas include sectors , , _,

, , . ine recomencea prosecuve action is Maintain General Emergency status until further notification.

5. Implement your Standard Operating Procedures for a General Emergency. l This notification takes precedence over other pending comunications.

6. Call to verify this message. (NA if Interagency Network Sys*am Phone is used.)

7. San Clemente, please read back this message. All other jurisdictions, check for accuracy.

i l l

EMERGENCY PROCLDunt a3-VIII-It, SAN ON0FRE NUCLEAR GENERATING STATION Page 2 of 2 REVISION 1 UNIT 2 AND 3 Attachment 8.5 .

SIMPLIFIED DESCRIPTION - GENERAL EMERGENCY EVENT N O.

l. Release of airborne radioactive materials corresponds to a projected exposure to people offsite of greater than 500 mrem to the whole body or 25 rem to a child thyroid at the site boundary.

2. Loss of 2 of the 3 barriers between the fuel in the reactor and the environment and high potential for loss of final barrier (clad, reactor cociast system boundary, containment sphere).

3. Control of the plant lost to outside party.

4. Condition of the plant is such tha releases of large amounts of radioactive material within a short time are possible.

O O e- e

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 REVISION 1 Page 1 of 4

-f'] UNITS 2AND3 Attachment 8.6 l

E NO. - SITE EMER NO. - ,

l t

ALERT NO. - GEN EMER NO. -

FOLLOW-UP NOTIFICATION FORM

Prepare to copy a follow up notification message:

UNU5UAL EVENT / ALERT /5ITE/ GENERAL EMERGENCY Time: on 198 . By:

Name: . Return phone number (714) .

1. Affected Facility: San Onofre Nuclear Generating Station, Unit 2/3.

2. Emergency Declared at: am/pm on .

(Class) (nme ) (Date)

3. Current Plant Conditions:

O ,

4. Prognosis for Worsening or Termination of Emergency:

5. Energency Response Actions Underway:

6. Request for Support:

O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE $023-VIII-16 REVISION 1 Page 2 of 4 OUNITS 2 AND 3 .

Attachment 8.6

Recomended Protective Actions (Emergency Coordinator Only): 1

8. Others:

9. Dose Projections / Measurements at Site Boundary:

Measured Projected Whole Body Dose Rate mrem /hr mrem /hr mrem 2-bur Whole Bo@ Dose mrem i

Annual Whole Body Dose Thyroid Dose Rate mrem /hr __

mrem /hr 2-Hour Thyroid Dose ' _ mrem mrem Annual Thyroid Dose

10. Dose Projection /M'easurements Offsite 2 miles 5 miles 10 miles Whole Body Dose Rate, mrem /hr 2-Wur Whole Bo@ Dose, mrem Annual Whole Body Dose, mPem Thyroid Dose Rate, mrem /hr 2-Hour Thyroid Dose, mrem Annual Thyroid Dose, mrem Direction from Plant (Sector)

!O l

l

l EMERGENCY PROCEDURE S023-VIII-16 J SAN ONOFRE NUCLEAR GENERATING STATION Page 3 of 4 REVISION 1 l CUNITS2AND3 Attachment 8.6

1. Meteorology Data:

Wind Direction (To and From) l mile / hour j Wind Speed Wind Direction Persistence (Sigma)

Stability Class (Delta T) _

i Precipitation _

12. Airborne Release:

f Actual Projecte_d Time of Release Start hrs. hrs.

Release Duration cc/sec cc/sec Release Rate Ci/sec Ci/sec j Noble Gas Release Rate Ci/sec Ci/sec Radio-iodine Release Rate _

(

Release Height Ground level Ground level

13. Liquid Release:

Time of Release Start hrs. hrs.

Release Duration gal. _ g al .

i Release Volume Ci Total Activity C1 Radionuclide(s) in Release O

l 4

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 ,

arvi52o" ' e 9 4 af 4 :

O""t's2^"a3 .

Attachment 8.6 4

4. Air / Water Sampled:

Time /Date of Sample Location of Sample Measured Activity uti/cc Radionuclide(s) Present i

O 4 <

t O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCE0VRE S023-VIII-16 ,

REVISION 1 Page 1 of 10 ;

T UNITS 2 AND 3 Attachment 8.7 .

0 0FFSITE ASSISTANCE TELEPHONE NUMBERS 1.1 The following telephone numbers provide an up-to-date list for agencies and persons that may be required to give assistance to SONGS in an emergency.

1.2 The Emergency Planning Mministrator shall ensure on a quarterly basis that the telephone numbers listed are reviewed and updated.

Known changes should be brought to the attention of the f NOTE: l Emergency Planning Administrator as soon as practicable and updates made. ;

For problems with the telephones make emergency call:

Special Services Management Bureau (Bell System) s

-~ -

Edison Pax Service Pax -

LIST ATTACHED A. MEDICAL EMERGENCY RESPONSE AGENCIES B. OFFSITE RADIOLOGICAL EMERGENCY RESPONSE AGENCIES

\ C. OFFSITE SECURITY EMERGENCY RESPONSE AGENCIES D. SCE, SDG1E EMERGENCY RESPONSE E. FIRE, FLOOD, PUBLIC HEALTH, RESCUE EMERGECY RESPONSE AGENCIES F. COMBUSTION ENGINEERING NUCLEAR EMERGENCi RESPONSE l

l8 l

l 4

l l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 ,

3 NITS 2 AND 3 REVISION 1 Page 2 of 10 Attachment 8.7 e

.. MEDICAL EMERGENCY RESPONSE AGENCIES

- Names with two asterisks (**) are authorized for CONTAMINATED accidents.

Always advise if the victim is contaminated.

AMBULANCE I

- Scudders M bulance Service 23011 Moulton Pkwy Laguna Hills 92653 Superior Mbulance Service Escondido 92025 ,

Kartne Base - Camp P .:dleton Fire Dept./Mbulance ,

or !

- Bechtel Emergency Vehicle Units 283 Paramedic '

or Nurse EXT-DOCTORS

- Bundy, B. L. , M.D.

Chard, J.P. M.D.

- Ross, J.F. , M.D.

HOSPITALS 1

Mission Community 27802 Puerta Real hty i Mission Viejo, CA Tri-Ci ty West 1100 - 5th Street Oceanside, CA San Clemente General 654 Camino de Los Mares San Clemente

- South Coast Comunity 31872 Coast iky So. Laguna CA CONTAMINATED: EXT.

- Tr1-City 4002 W. Vi sta Way Oceanside, CA 8

EMERGENCY PROCEDURE 5023-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATION REVISION 1 Page 3 of 10

] UNITS 2AND3 Attachment 8.7 ,

r OFFSITE RADIOLOGICAL EMERGENCY RESPONSE AGENCIES DEPARTMENT TELEPHONE AGENCY RADIOLOGICAL RESPONSE:

C1ty of San Clemente He adquarters San Diego Office of DAY: Manager of 00P via ,

Disaster Preparedness Secretary #

NIGHT: Staff Duty Officer via answering service StatA Dept. of Parks & Duty Officer SCE (System I Recreation Operating Supervisor will I contact if no answer)

Orange County Office of Com. Control I, Duty Emergency Services Officer U. S. Marine Base Camp Base Duty Officer RED PHONE Pendleton U. S. Nuclear Regulatory Duty Officer NRC RED PHONE

(

Comission Region V RADIOLOGICAL ASSISTANCE: .

State of California Highway Patrol Vi sta, CA. DAY:

San Diego Dispatcher NIGHT:

Dept. of Health, Bureau of Sacramento Avail: 24 hrs Rad. Health

~

Office of Emergency Services Sacramento Avail: 24 hrs San Diego County Dept. of Public Walth San Diego Orange County Health Dept. Santa hia S

I

. SAN ONOFRE NUCLEAhl GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 UNITS 2 AND 3 REVISION 1 Page 4 of 10 J Attachment 8.7 r

Offsite Radiological Emergency Response Agencies (continued)

Others General Atomic Company Frank Bold, San Diego Alternate I

Radiation Emergency Oak Ridge, Tennessee DAY:

Assistance Center / Training NIGHT: (& spital)

Site (REAC/TS)

U. S. Dept. of Energy IRAP Interagency Radiological Assitance Team DAY: !

Institute for Nuclear INPO '

Power Operations (INPO) NIGHT:

~

9 8

SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 Page S of 10

~

..) UNITS 2AND3 REVISION 1 Attachment 8.7 0 -

4

, OFFSITE SECURITY EMERGENCY RESPONSE AGENCIES DEPARMENT TELEPHONE AGENCY l Orange County Marine Base Camp Pendleton Provost Marshall (indirect)

ALTERNATE: :(direct)

Orange County Base Duty Officer Sheriff 4 San Diego County Sherif f.

Highway Patrol Vi sta l Dept. Parks and Recreation Pendleton Coast Area lith District Rescue United States Coast Guard Control

)

National Response Center Duty Officer U.S. - F. B. I. Vista U. S. - NRC Region V Duty Of.ffcer !

U. S. - Marshall San Diego

~

O

' ??,

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16

./ UNITS 2 AND 3 REVISION l Page 6 of 10

- Attactanent 8.7

'3 SCE, SDG&E AGENCIES _

SOUTHERN CALIFORNIA EDISON _ _.

Energy Control Center Senior System Operations Supervisor (Dispatcher)

' ALTERNATE ALTERNATE ALTERNATE San Onofre Units 2&3 Control Room o

M t San Onofre Units 2&3 Constniction Site Superintendent, R. Hart SAN DIEGO GAS & ELECTRIC Dispatcher 8i Visitor's Center Old Highway 101 San Clemente 101 W. El Portal, San Clemente Commercial Office General Infomation

- Public Relations

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 REVISION 1 Page 7 of 10

. ', UNITS 2 AND 3 Attachment 8.7 ,

F FIRE, FLOOD, PUBLIC HEALTH, AND RESCUE EMERGENCY RESPONSE AGENCIES TITLE TELEPHONE AGENCY-Fire Dept./ Rescue RED PHONE Marine Base Camp ALTERNATE:

Pendleton CHEMTREC Toxic Chemical Info. Service Environmental Protection Sacramento Agency U. S. Coast GJard lith District (011 Spills)

ORANGE COUNTY Health Department Santa Ana SAN DIEGO COUNTY Dept. of Public thalth Div. of Environmental Italth

' ATE OF CALIFORNIA Dept. of Ibalth Sacramento San Diego (Mr. Coe) DAY:

Regional Water Quality NIGHT:

Control Board Highway Patrol Santa Ana l

l l

l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-16 REVISION 1 Page 8 of 10

- OUNITS 2 AND 3 Attachment 8.7 -

- l i

)

( l F. COMBUSTION ENGINEERING !

NUCLEAR EMERGENCY RESPONSE ORGANIZATION ,

i To activate the Combustion Engineering Nuclear Emergency Response Organization, the following instructions should'be followed: .

1. Read all instructions before taking further action in order to assure ,

that all initially required infomation is available. Initial contact-with the C-E Emergency Response Organization can always be made through the C-E Security Force (phone number below). The Security Fcrce '

Supervisor will have no knowledge of nuclear plants, but is required to obtain certain infomation to assure proper and rapid C-E response.

2. The attached EMERGENCY INFORMATION from lists the information that the C-E Security Supervisor is required to obtain. If he fails to ask for this infomation, you should provide it and assure that he records it.

Activate the C-E Nuclear Emergency Response Plan by calling the following dedicated telephone number at any time:

~

The number will be answered by the C-E Security Force and is held in confidence at U-L. It is reservea strictly for utility activation of the Nuclear tmergency Hesponse Plan.

I

A, g =

D / .

EMERGENCY PROCEDURE S023-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATION Page 9 of 10

- REVISION 1

..r} UNITS 2 AND 3 Attachment 8.7 .

'~, F. COMBUSTION ENGINEERING NUCLEAR EMERGENCY RESPONSE ORGANIZATION i ,

f ,

-5' ,

(continued) 4

4. When your initial contict answers, give him all information indicated on

' the attached EMERGENEY INFORMATION fom. He will be recording the infomation on a similar form. Be sure to indicate EMERGENCY or DRILL.

~

5. In the improbable event that the emergency number in Step. 3 is inoperable and you have not been able to reach C. E., you may alternately contact olie of the individuals on the Back-up Call List (below). These peopls are familiar with the Emergency Response

. Organization and its implementation and will effectively activate the

- Pl an. Again, be sure to indicate EMERGENCY or DRILL.

. BACK-UP CALL LIST J NOTE: If busy, have operator break in on call.

EMERGENCY or DRILL? (Circle one) i 1-(203) 688-1911 C-E WORK EXTENSION HOME PHONE NAME i

Ray Mills ;

Jor;as Strimaitis Reid Wolf 4

Tom Goetz l l l

Fred Stern

~~

0

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-16 REVISION 1 Page 10 of 10 l NITS 2 AND 3 Attachment 8.7 r

F. COMBUSTION ENGINEERING NUCLEAR EMERGENCY RESPONSE ORGANIZATION INITIAL NOTIFICATION EMERGENCY INFORMATION I. CALLER TITLE II. PLANT _ LOCATION III. CALL BACK NUMBERS ( )

s (Give two) ( )

J i

. Is this call for an EMERGENCY or a ORILL ? (Circle one)

V. What is the NOTIFICATION LEVEL ? (Check one or more)

PHONE EXERCISE ( ) ALERT ( )

PRACTICE ( ) SITE EMERGENCY ( )

NOTIFICATION ( ) GENERAL EMERGENCY ( )

VI. What is the C-E RESPONSE to be? (Check one)

NONE ( ) CENTER ACTIVATION ( )

ALERT ( ) FULL RESPONSE ( )

VII. Is there additional EVENT DESCRIPTION? (Include dates and times)

You should give no more than one sentence this time.

l O ,1 VII. READ THIS FORM BACK TO RECEIVER FOR YERIFICATION.

DM:0106F/ryh

l l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-17 REVISION 1 Page 1 UNITS 2 AND 3

.$ ACTIVATION AND OPERATION DCT 9 1981 EMERGENCY CENTERS AND ORGAN TIONS

., s 1.0 OBJECTIVE u ?:

1.1 This procedure provides instructions for the actik $g operation, and organization of the Operations Support C (OSC), and Technical Support Center (TSC). N6 1.2 The Corporate Emergency Support Organization shall be activated by notification through the Energy Control Center System Operating Supervisor.

1.3 The Emergency Coordinator is responsible for implementation of the actions prescribed by this procedure.

2.0 REFERENCES

2.1 NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".

2.2 San Onofre Nuclear Generating Station Units 2 and 3 Emergency

(~}

v Plan 2.3 " SONGS" Corporate Emergency Support Organization Procedures Manual.

2.4 Health Physics Procedure S023-VII-5.3.7 " Iodine Air Monitor Operation" 2.5 Emergency Procedure 5023-VIII-18 " NOTIFICATION OF ADDITIONAL EMERGENCY SUPPORT PERSONNEL."

3.0 PREREQUISITES 3.1 DECLARATION OF AN UNUSUAL EVENT: The Emergency Coordinator position is activated. The balance of the Onsite Emergency Organization is activated only upon the decision of the Emergency Coordinator to do so.

3.2 DECLARATION OF AN ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY:

Mandatory activation of the onsite emergency organization.

4.0 PRECAUTIONS 4.1 No individual occupying an Emergency Response position described in this procedure may be relieved by another qualified individual p until total conditions and the state of emergency response are

( known.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-17 REVISION 1 Page 2 UNITS 2 AND 3 4 5.0 CHECK-OFF LISTS r

5.1 TSC Activation Checklist 5.2 OSC Activation Checklist 6.0 PROCEDURE 6.1 Watch Engineer / Emergency Coordinator (EC)

Upon declaration of an emergency condition (Unusual Event, Alert, Site Emergency, or General Emergency), the Watch Engineer shall assume the position of Emergency Coordinator. He shall maintain the position of EC until properly relieved by the Station Manager or other qualified alternate or until close out of any and all exisiting emergency conditions. Upon assuming the position, the EC shall:

6.1.1 Report to the Control Room for briefing by the Watch Engineer. Upon completion of briefing, assume the dut;es of Emergency Coordinator. At the earitast convenient time, transfer to the Technical Support Center (TSC), and contro'. the emergency response effort from there.

p s'

6.1.2 THE FOLLOWING REPONSIBILITIES OF THE EMERGENCY COORDINATOR MAY NOT BE DELEGATED:

.1 Classification of emergency event.

.2 Decision to notify offsite Emergency Management Agencies.

.3 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

.4 Determining the necessity for evacuation of personnel onsite.

.5 Making protective action recommendations as necessary to offsite Emergency Management Agencies.

6.1.3 Other functional responsibilities of the Emergency Coordinator includes:

.1 Coordinating the response of the station emergency organization.

.2 Assumina overall control of TSC personnel and activities.

l NJ

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-17 REVISION 1 Page 3 UNITS 2 AND 3 6.0 PROCEDURE f'

6.1.3 (continued)

.3 Ensuring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage of key positions in the station emergency organizations.

.4 Provide direction and support to the Watch Engineer.

.5 Establish and maintain communications with offsite Emergency Management Agencies, regulatory agencies, and emergency centers; and ensure that appropriate notifications, liason, and information flow is maintained.

.6 Complete the TSC Activation Checklist. (Attachment

8. 1).

6.2 Emergency Organization Upon declaration of an Alert, Site Emergency, or General Emergency; or as otherwise determined by the Emergency Coordinator, designated individuals (as provided in Emergency Procedure 5023-VIII-18 ) shall assume the following positions and responsibilities:

( }) .

/ 6.2.1 Health Physics Leader

.1 Report to the TSC and assume control of the Health Physics emergency- response effort.

.2 Activate the Iodine Air Monitor BAM-3A(I) per H.P.

procedure 5023-VII-5.3.7.

.3 Perform source term determinations and dose projections as necessary.

.4 Assign qualified personnel to onsite/offsite monitoring teams and direct monitoring team activities.

.5 Provide Health Physics support for onsite emergency response activities.

.6 Keep the Emergency Coordinator advised of any possible need to make offsite protective action recommendations.

.7 Implement appropriate radiological controls.

.8 At the Alert level and personnel availability s- permitting, assign a Health Physics Engineer to the EOF to coordinate offsite monitoring activities with State and Local agencies.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-17 REVISION 1 Page 4 UNITS 2 AND 3 O

V 6.0 PROCEDURE 6.2.1 (continued)

.9 If additional assistance is deemed necessary, refer

,' to the West Coast Utilities Radiological Emergency Mutual Assistance Agreement and/or INPO Resources Manual.

6.2.2 Emergency Group Leader

.1 Report to the Operations Support Center (OSC) and assume control of the OSC emergency response effort.

.2 Assign personnel to emergency teams and coordinate emergency team activities such as first aid, rescue, i

fire. fighting, damage control, and repair.

.3 Provide information and support to the TSC staff for plant operational functions, and provide for personnel for various tasks upon the request of the Emergency Coordinator or designee.

.4 Maintain accountability of OSC and emergency team personnel.

2

( .5 Complete the OSC Activation Checklist (Attachment l

8.2).

.6 Maintain the OSC Log.

I NOTE: IN THE EVENT THE OSC BECOMES UNINHASITABLE, TRANSFER ALL ACTIVITIES AND PERSONNEL TO THE UNIT 1 OSC (Unit 1 Control and Administrative Building Conference Room).

6.2.3 Operations Leader Report to the TSC and coordinate all activities l

.1

~

relating to plant operations.

! .2 Determine if the Control Room or the TSC is the most appropriate duty station.

.3 Advise the EC with respect to plant operations activities.

.4 Maintain the Operations Emergency Log.

I O

t_-

l i l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-17 REVISION 1 Page 5 UNITS 2 AND 3 p

V 6.0 PROCEDURE (continued)

,r -

6.2.4 Technical Support Leader

.1 Report to the TSC.

.2 Provide engineering and technical support to the EC as requested.

.3 Activate the AE and NSSS emergency organizations as required.

.4 Maintain the Technical Support Emergency Log.

NOTE: The Institute of Nuclear Power Operations (INPO) maintains a teletype technical information exchange with other nuclear plant operators. INPO also acts as a coordinator for providir.g the affected plant with additional specialized emergency response personnel and equipment.

i 6.2.5 Administrative Leader

.1 Report to the TSC.

.2 Request an engineer from the Technical Support Leader

( to act as a communicator and assist / relieve the Shift Communicator.

.3 Coordinate provisions for food, transportation, and other logistical support for the emergency response effort.

.4 Act as liason with offsite support groups in providing additional resources such as manpower, equipment, supplies, and transportation.

.5 Obtain personnel work schedules from appropriate emergency organization supervisors for relief of emergency personnel. If the emergency condition is projected to last greater that 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , direct the Shift Communicator /AWS Operator to contact designated relief personnel. Provide a copy of the Watch Bill to the Security Leader for transmital to the Security Officer supervising site ingress.

.6 Coordinate communications and maintain records.

Ensure that all checklists, data sheets, forms, etc.

are appropriately filed.

.7 Maintain the Administrative Emergency Log.

4 1

i

. \

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-17 UNITS 2 AND 3 REVISION 1 Page 6 O.

6.0 PROCEDURE (continued) l' 4

6.2.5.8 Brief the Shift Communicator on the status of Emergency Staff Augmentation.

.9 Forward completed checklists, logs, calculations, and other emergency records to CDM for storage.

6.2.6 Chemistry Leader

.1 Report to the TSC.

.2 Advise the EC with respect to chemistry aspects of the RCS and other plant systems.

.3 Coordinate plant sampling in support of the emergency response effort.

.4 Maintain the Chemistry Emergency Log.

6.2.7 Security Leader

.1 Report to the TSC and coordinate station security activities with the emergency response effort.

.2 Maintain the integrity of station security.

k .3 Coordinate with the Health Physics Leader in establishing or changing access control requirements as dictated by conditions.

.4 Coordinate personnel accountability as required.

.5 In the event of evacuation, dispatch an officer (s) to act as Assembly Area Coordinator (s) and coordinate any necessary traffic control measures.

3

.6 In the event of Site Evacuation dispatch security l

personnel to perform an area by area search to assure that all personnel have evacuated.

j .7 Maintain the Security Emergency Log.

6.2.8 Emergency Advisor

.1 Report to the TSC.

.2 If required, fill in for any missing key TSC personnel.

l

.3 Advise the EC with respect to corrective actions.

O' .4 Maintain the Emergency Advisors Log.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-17 REVISION 1 Page 7 UNITS 2 AND 3

,(-)

v 6.0 PROCEDURE (continued) f-6.2.9 Emergency Planning Coordinator

. 1 Report to the TSC.

. 2 Provide the EC with any assistance required concerning the emergency organization, emergency plan, implementing procedures, etc.

. 3 Maintain the Emergency Planning Log.

'7.0 RECORDS 7.1 Forward all completed checklists and records to the Administrative Leader for ultimate distribution.

8.0 ATTACHMENTS 8.1 Technical Support Center Activation Checklist.

8.2 Operations Support Center Activation Checklist.

8.3 Current Personnel Assignment List - Technical Support Center.

O ,

8.4 Current Personnel Assignment List - Operations Support Center.

t 8.5 Current Personnel Assignment List - Unit 1 Control Room.

K. P. BARR HEALTH PHYSICS MANAGER OM:0100F/sss O

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENC PROCEDURE 5023-VIII-17

~

REVISION 1 PAGE 1 0F 1

(~ UNIT 2 AND 3 ATTACHMENT 8.1 DATE TECHNICAL SUPPORT CENTER ACTIVATION CHECKLIST

1. Plant Manager / designated alternate assumes EC position:

/

(Time /Init.)

/

(Time /Init.)

~

/

(Time /Init.)

l

2. Notification of Emergency Response personnel by the Abl5 Switchboard operator complete.

(Time /Init.)

(

TSC fully staffed and activated. /

3.

(Time /Date)

4. OSC fully activated. /

f Date)

/

5. EOF (ESC-PECC) notified that TSC and OSC are activated.

(Time / Date Health Physics Engineer assigned to EOF /

6.

(Time / Date)

7. Initiate (and update) the Current Personnel /

Assignment List - Technical Support Center, (Time /Date)

Attachment 8.3.

8. Initiate (and update) the Current Personnel /

Assignment List - Unit 1 Control Room, (Time / Date)

Attachment 8.4.

O

' EMERGENCY PROCEDURE 5023-VIII-17 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 AND 3 REVISION 1 PAGE 1 of 1 ATTACHMENT 8.2 DATE OPERATIONS SUPPORT CENTER CHECKLIST (To be completed by the Emergency Group Leader)

1. Designate an individual to act as a communicator and record keeper for the OSC. He shall perform a-c below.

(name)

a. Test Telephone Extentions /

(Time /Init.)

()

Test Walkie Talkies /

b. '

(Time /Init.)

(

c. Inventory Equipment and Supplies - See 501-VIII-72. " Emergency Equipment Checklist and Maintenance. (Done only if seals on equipment lockers have been broken

/

Time / Init.

2. Perform accountability of personnel present and notify the Emergency Coordinator, via the TSC Security

/

Leader.

(Time /Init.)

NOTE: A log of events will be maintained by the i Communicator.

l 3. Designate personnel for Emergency Teams to be ready for action as requested by the Emergency Coordinator.

/

(Use Attachment 8.4 to maintain a current list). (Time /Init.)

4. Initiate (and update) the Current persor.nel Assignment List - Operations Support Center,

/

(Attachment 8.4).

(Time /Init.)

( ])

fr G ~ ~3 k.

EMERCENCY PROCEDURE S023-Vill-17 SAN ONOFRE NUCLEAR CENERATING STATION REVISION 1 Page 1 or 2 UNIT 2 AND 3 ATTACHMENT 8.3 DATE ATTACHMENT 8.3 CURRENT PERSONNEL ASSIGNMENT LIST - TECHNICAL SUPPORT CENTER (TSC)

NOTE: This Checkilst is to be used for the initial Activation of the TSC. If the TSC is to be manned for a song term period, the Administrative leader shall develop a Watchbill designating who shall Fan Emergency Organization positions during designated times. Forward this Checklist to the Administrative Leader upon completion. Promptly update es appropriate.

PEPLACED BY REPLACED BY REPLACED BY TITLE OR CURRENT INDIVIDUAL RESPONSIBILITY Date/ Time ACKNOWLEDGED Date/ Time Date/ Time TUNCTION As of Dale ilme (check) .

I Emergency Cso rd i na to r Emergency Advisor Technical Support Leader Cp3 rations Leader Adainistrative Leader He28th Physics Leader

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O - o 6 SAN ONOFRE NUCLEAR GENERATING STATION EMERCENCY PROCEDURE SC23-Vill-17

~ REVISION 1 Page 1 of 2 UNIT ? AND 3 ATTACHMENT 8.4

+

DATE ATTACHMENT 8.4 CURRENT PERSONNEL ASSIGNMENT LIST - OPERATIONAL SUPPORT CENTER (OSC)

To be completed by the Emergency Croup Leader / Designee in OSC.

Promptly update as appropriate. Post a copy and updates in OSC.

Use additional sheets as requi red. Forward to Administrative Leader upon completion.

RESPONSIBILITY A3SIGNMENT COMPLETED REPLACED BY TITLE OR INDIVIDUAL ASSIGNED DATE/ TIME DATE/ TIME ACKNOWLEDGED OR REPLACED BY FUNCTION (check) DATE/ TIME Eme rgency Group Leader Communica to r uthers (specify)

CONTINUED: Yes/No (ci rcle)

O m o .

c)s EMERGENCY PROCEDURE 8023-Vill-17 SAN ONOFRE NUCLEAR GENERATINC STATION REVISION 1 Page 2 of 2 UNIT 2 AND 3 ATTACHMENT 8.84

DATE ATTACHMENT 8.18 CUPRENT PERSONNEL ASSICNMENT LIST - OPERATIONS SUPPORT CENTER (OSC1 CONTINUATION #

) ?

RESPONSIBILITY ASSIGNMENT COMPLETED REPLACED BY 111LE OR INDIVIDUAL ASSIGNED DATE/ TIME DATE/ TIME ACKNOWLEGED OR REPLACED BY

! FUNCTION DATE/ TIME (check)

Emergency Teams (specify function er.d

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' SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-18 REVISION 1 Page 1 UNIT 2 AND 3 0C1 9 1981 3

NOTIFICATION OF ADDITIONAL

-,CEiVE-i EMERGENCY SUPPORT PERSONNEL OCT 141981 l 1.0 OBJECTIVE GDM S!TE 1.1 During an emergency condition _at SONGS TWO AND THREE prompt notification of additional energency wqswt personnel to augment the on shift personnel as re tuired b RWf50$$ ht3p p %

made. During the normal wor ting houffgn m w ION f a fy@

personnel are notified via t be sg g A S l [c g # [ny This procedure provides insj operator on whom to contact.

t 08 reg %

also provides direction for screening o 'irtcwan; g1 _ lii4((Q concerning emergency conditions. Implementation of this procedure is the responsibility of the duty AWS Switchboard f Operator. 7 ., []

dk I= b E.= I

2.0 REFERENCES

2.1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plant and Preparedness in Support of Nuclear Power Plants" NUREG 0654, Table B-1, " Minimum Staffing Requirements for NRC Licensees for Nuclear Power Plant Emergencies".

2.2 San Onofre Nuclear Generating Station Unit 2 and 3 Emergency Plan 2.3 EMERGENCY PROCEDURE S023-VIII-17 " ACTIVATION AND OPERATION OF EMERGENCY CENTERS AND ORGANIZATIONS."

3.0 PREREQUISITES 3.1 Unusual Event - Option of Watch Engineer 3.2 Alert - Mandatory Activation 3.3 Site Emergency - Mandatory Activation 3.4 General Emergency - Mandatory Activation 4.0 PRECAUTIONS 4.1 The Shift Communicator (PAX ,

, must receive frequent reports on status of Emergency Staff Augmentation.

5.0 CHECK-OFF LISTS 5.1 None

b . .. :

[-

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-18 UNIT 2 AND 3 REVISION 1 Page 2

( '

)O 6.0

,_ PROCEDURE .

6.1 Upon notification by the Watch Engineer or Shift Communicator of the declaration of an emergency condition proceed as follows:

6.1.1 Contact the Edison Operator (PAX 821212 or 822222) and have them activate the beepers of all primary

Emergency Personnel in Attachment 8-1. Inform the operator of the class of emergency and instruct him to request all emergency team members to respond to the site. Have the operator advise you of any contacts he has made.

j 6.1.2 Contact primary (or alternative as necessary) Emergency Management Personnel (Attachment 8.1) and additional emergency support personnel (Attachment 8.2). For Attachment 8.2 use the " Station Emergency Personnel Recall List". As each person is contacted read the standard message as follows:

"THIS IS THE SWITCH BOARD OPERATOR AT SAN ONOFRE NUCLEAR GENERATING STAIION, IS HOME?"

(name)

, , s When the person desired is on the phone proceed as follows:

"AN HAS BEEN DECLARED AT SAN ONOFRE Type of Emergency NUCLEAR GENERATING STATION. EMERGENCY CONTROL CENTERS ARE BEING ACTIVATED AND YOU ARE NEEDED TO RESPOND TO YOUR DESIGNATED DUTY STATION.

t "AT WHAT TIME CAN WE EXPECT YOU TO BE AT THE STATION?"

TIME 6.1.3 Log on Attachment 8.1 and 8.2 the names of responding i personnel NOTE: NAMES ARE LISTED IN ORDER OF THEIR PROXIMITY TO THE J PLANT, FOR THIS REASON ALWAYS START AT THE TOP OF THE LIST.

I 6.2 When all positions in TABLES A & B of Attachment 8.1 and 8.2 have been completed, inform the Shift Communicator in the Control Room (56201) and the Administrative Leader in the TSC (56140).

1 NOTE Control, room # for f( TSC# for j

/ l I

EMERGENCY PROCEDURE S023-VIII-18

'3AN ONOFRE NUCLEAR GENERATING STATION Page 3 REVISION 1 UNIT 2 AND 3 I i

.. - i s

,) 6.0 PROCEDURE (continued)

'~

6.3 Incoming Calls 6.3.1 Do not allow incoming calls to interfere with personnel call up. If during the process of contacting emergency support personnel an incoming call for a non-emergency reason is received, politely explain to them that the {1 person they wish to contact will be unavailable for an )

unknown period of time and ask them to call !ater.

6.3.2 Refer all incoming calls concerning the,e.mergency to SCE Public Relations i _ . . _ _ _ _ ./ unless a call is received from one of the following offsite agencies: ,

.1 City of San Clemente or San Juan Capistrano

.2 Office of Emergency Services - State office at Sacramento, Orange County.or San Diego County

.3 U.S. Nuclear Regulatory Commission or Department of Energy

.4 U.S. Marine Corps Base - Camp Pendleton

.5 Pendleton Coast Area Office State Parks and Recreation

' .6 California Highway Patrol

.7 Plant Vendors: Westinghouse or Bechtel 6.3.3 If the call is from one of the above agencies, take their message and tell them you will relay it to the proper _ person and they will return the call.

7.0 ilECORDS 7.1 Completed attachments shall be forwarded to the Administrative Leader and CDM.

8.0 ATTACHMENTS 8.1 Technical and Operations Support Center Staffing Resource List l

G.2 30Minuteand60MinuteRespongepersonnelTableA&B.

. P. BARR HEALTH PHYSICS MANAGER O.

ODB:0118F:sss l

l

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SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 AND 3 .

EMERGENCY PROCEDURE S023-VIII-18 REVISION 1 PAGE 1 of 7 1 ATTACHMENT 8.1 DATE

! ATTACHMENT 8.1 TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

CONTACTED TSC/OSC/

POSITION TITLE /NAME/ TELEPHONE NUMBERS YES / N0/ TIME PHONE. NO

EMERGENCY Station Manager COORDINATOR- H .B. Ray _

4 Beeper: x Work:

Home: '..s l ist Alternate Asst. Station Mgr., Operations H. E. Morgan Beeper: ' 'N Work: 'N l Home: _

s l ,/N 2nd Alternate Superintendent, Unit 1

! NJ J. TATE _ ' - ~

\ Beeper- '-

Work: !

Home: ; _ _

j 3rd Alternate Supervisor Plant Coordination V. FISHER ._

Beeper:

Work: .[' ~

Home: /

.j

EMERGENCY ADVISOR Asst. Station Mgr., Operations H. E. Moroan Beeper: "N Work:

Home: ..

If the primary person for a position leaves the Southern !

NOTE:

! California area he shall pass the beeper to the next alternate.

l O.

l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-18 REVISION 1 PAGE 2 of 7 UNIT 2 AND 3 ATTACHMENT 8.1 DATE ATTACHMENT 8.1 TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

CONTACTED TSC/OSC/

POSITION TITLE /NAME/ TELEPHONE NUMBERS YES / N0/ TIME PHONE. NO

TECHNICAL SUPPORT LEADER Asst. Station Mgr., Technical Brian Kati ~

Beeper:

Work:

Home: .

s 1st Alternate Supervising Engineer, NSSS Group P. H. Penseyres f) Beeper:

~

'(- Work:

Home: :>

2nd Alternate Supervising Engineer, NSSS Support Group.

Mike Wharton Beeper: -s '

Work: ,

Home: 4

0PERATIONS Superintendent of Units 2 and 3 LEADER J. TATE Beeper:

Work:

Home:

NOTE: If the primary person for a position leaves the Scuthern California area he shall pass the beeper to the next alternate, a

l

[ SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-18 REVISION 1 PAGE 3 of 7 UNIT 2 AND 3 ATTACHMENT 8.1 OATE __

ATTACMMENT 8.1 TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

(continued)

CONTACTED TSC/05C/

POSITION TITLE /NAME/ TELEPHONE NUMBERS YES / N0/ TIME PHONE. NO OPERATION Alternates (continued) ist Alternate Supervisor of Plant Coordination V. FISHER Beeper:

Work: \?

Home:

Alternates- Off Duty Watch Engineer

'}

[1 Don Lokker Work:

Home: 1 Tom James Work: s Home: ,

Kieth.Eckman Work:

Home: --

~_

Robert Brown Work:

Home: },

Mike Lisitza Work:

Home:

NOTE: If the primary person for a position leaves the Southern California area he shall pass the beeper to the next alternate.

O

EMERGENCY PROCEDURE S023-VIII-18 SAN ONOFRE NUCLEAR GENERATING STATION REVISION 1 PAGE 4 of 7 UNIT 2 AND 3 ATTACHMENT 8.1 DATE ATTACHMENT 8.1 TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

(continued)

CONTACTED TSC/OSC/

POSITION TITLE /NAME/ TELEPHONE NUMBERS YES / N0/ TIME PHONE. NO

HEALTH PHYSICS Health Physics Manager LEADER K. P. Barr Beeper:

Work: \

Home: \

1st Alternate Health Physics Supervisor Unit 1 Scott Medling Beeper: N '

/N Work:

V Home: h

(

2nd Alternate Health Physics Supervisor Units 2 & 3 John Albers ,_

Beeper:

Work: N '

Home: _ ,

SECURITY LEADER Security Supervisor K. N. Hadley Beeper:

Work:

Home:

Alternate Shift Supervising Security Officer Work:

_~

NOTE: If the primary person for a position leaves the Southern California area he shall pass the heeper to the next alternate.

O

4

.'Iilp

' EMERGENCY PROCEDUPE SO23-VIII-18 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 AND 3 REVISION 1 PAGE 5 of 7 ATTACHMENT 8.1 DATE ATTACHMENT 8.1 TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

(continued)

TITLE /NAME/ TELEPHONE NUMBERS CONTACTED TSC/OSC/

POSITION YES / N0/ TIME PHONE. NO

EMERGENCY GROUP Asst. Station Mgr., Maintenance LEADER R. Santosuosso Beeper:

Work:

Home:

1st Alternate Supervisor of Plant Maintenance Unit 1

[s s J. BANK 0VICH i() Beeper:

Work:

Home: ; ,

2nd Alternate Maintenance Foreman Gene Harker Beeper:

Work:

s Home:

Station Services Manager l

ADMINISTRATIVE l LEADER William J. M=++a-1 Beeper:

Work: , l Home: .- ,

NOTE: If the primary person for a position leaves the Southern California area he shall pass the beeper to the next alternate.

s_-).

r SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-18 UNIT 2 AND 3 REVISION 1 PAGE 6 of 7 ATTACHMENT 8.1 DATE ATTACHMENT 8.1 4

TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

(continued) 1 i

ADMINISTRATIVE LEADER (continued)

TITLE /NAME/ TELEPHONE NUMBERS CONTACTED TSC/OSC/

POSITION t

YES / N0/ TIME PHONE. NO 1st Alternate Accounting & Clerical Supervisor i Patricia J. Rankin ~

Beeper:

Work:

Home: .

2nd Alternate Warehouse Supervisor Ernest Rintrd ^ .

i O[ Beeper:

Work:

s i Home: ,.-

I

CHEMISTRY LEADER Chemistry Supervisor Marvin Sullivan^

Beeper:

Work: ' 's '

Home: .

ist Alternate Supervisor of Unit 2 3 Chemistry

. Al Prosser Beeper: ,

Work:

Home: ,

i NOTE: If the primary person for a position leaves the Southern California area he shall pass the beeper to the next alternate.

l O

l

l r

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-18 UNIT 2 AND 3 REVISION 1 PAGE 7 of 7 ATTACHMENT 8.I

' DATE ATTACHMENT 8.1 TECHNICAL AND OPERATIONS SUPPORT CENTER STAFFING RESOURCE LIST.

(continued)

~

i CONTACTED TSC/OSC/

POSITION TITLE /NAME/ TELEPHONE NUMBERS YES / N0/ TIME PHONE. N0 f

!

ADMINISTRATIVE LEADER

( (continued) l 2nd Alternate Chemical Engineer Jane Young

'- Beeper:

~

e -

!

EMERGENCY Emergency Planning PLANNING Coordinator COORDINATOR Dennis McCloskey Beeper:

Work:

Home: s, I

1st Alternate Nuclear Engineer Donald Bennette Beeper:

Work:

Home: y NOTE: If the primary person for a position leaves the Southern California area he shall pass the beeper to the next alternate.

o.

1

,- SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-18 UNIT 2 AND 3 REVISION 1 Page 1 of 3 ATTACHMENT 8.2 TABLE A: 30 MINUTE RESPONSE TIME PERSONNEL POSITION EXPECTED RESPONSE OR EXPERTISE NAME TIME CONTACTED TIME HEALTH PHYSICS SUPPORT:

Health Physics Engineer AM/PM AM/PM (1)

(1 required)

Health Physics AM/PM AM/PM (1)

Technican (6 required) AM/PM AM/PM (2)

AM/PM AM/PM (3)

O (4) AM/PM AM/PM

{

AM/PM AM/PM (5)

AM/PM AM/PM (6)

TECHNICAL SUPPORT:

AM/PM AM/PM Core / Thermal (1)

Hydraulics Engineer (1 required)

I & C Techncian AM/PM AM/PM (1)

(1 required)

AM/PM AM/PM Communicator (1)

(1 required)

MAINTENANCE SUPPORT:

AM/PM AM/PM Electrician (1)

(1 required)

O

4

~

J

. r~\

d EMERGENCY PROCEDURE S023-VIII-18

'. SAN ONOFRE NUCLEAR GENERATING STATION Page 2 of 3 )

UNIT 2 AND 3 REVISION 1 ATTACHMENT 8.2 TABLE B: 60 MINUTE RESPONSE TIME PERSONNEL NOTE: CONTINUE TO CONTACT PERSONNEL ON THE 30 MINUTE RESPONSE TIME LIST (FOR THE POSITIONS BELOW) UNTIL IT IS EXHAUSTEO, THEN USE THE 60 MINUTE RESPONSE TIME LISTS.

EXPECTED RESPONSE POSITION NAME TIME CONTACTED TIME OR EXPERTISE HEALTH PHYSICS SUPPORT: i AM/PM AM/PM Health Physics (1) AM/PM AM/PM Engineer (2)

(2 required)

AM/PM AM/PM Health Physics (1)

() Technican (6 required) (2) AM/PM AM/PM i AM/PM AM/PM (3)

AM/PM AM/PM (4)

AM/PM AM/PM (5)

AM/PM AM/PM (6)

TECHNICAL SUPPORT:

AM/PM Electrical (I) AM/PM Engineer (1 required)

AM/PM AM/PM Mechanical (1)

Engineer (1 required)

AM/PM Nuclear Chemistry (I) AM/PM Technician (1 required)

AM/PM AM/PM Communicator (1)

O (2 required)

(2) AM/PM AM/PM

. . ~

^ '

i i

o. ,

[ SAhONOFRENUCLEARGENERAIINGSTATION EMERGENCY PROCEDURE S023-VIII-18 UNIT 2 AND 3 ,. ,

REVISION 1 Page 3 of 3 ATTACHMENT 8.2

- TABLE B: 60 MINUTE P.ESPONSE TIME PERSONNEL

~(CONTINUED)

POSITION EXPECTED RESPONSE NAME TIME CONTACTED TIME

O_R TXPERTISE

)

I' MANTENANCE .

SUPPORT:

Electrician AM/PM

-(1). __

AM/PM (1 required)

MANTENANCE SUPPORT: (Continued)

AM/PM AM/PM I Mechanical (1)

Teca"'c "

' ~O' ,(1-required) i OPERATIONS SUPPORT:

i RAD WASTE (1) AM/PM AM/PM OPERATOR (1 required) cc: CDM EPIPS in Control Room, TSC, OSC, PBX Switchboard Emergency Planning Coordinator Assistant Plant Managers O

k SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 REVISION 1 Page 1

. r~ - UNITS 2 AND 3

.0C1 9 1981 SOURCE TERM DETERMINATION RECElvED OCT 141981 1.0 OBJECTIVE N~O) FOR N This procedure provides the inf ation k%r nhbITE gnt amount of radioactive material alvail se@c(pyg f during an emergency, and the reJg g The Health Physics Leader shall be respons e Mig of- this procedure.

i (ON

, . 7 ,,.* r * '

' F $

2.0 REFERENCES

-jr f [ [ [ ,

, b kr h' \

2.1 NUREG-0654, Rev.1, Criteria For Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2 San Onofre Nuclear Generating Station, Units 2 & 3, Final Safety Analysis Report, Section 15 2.3 San Onofre Nuclear Generating Station, Units 2 & 3, Emergency Plan 2.4 San Onofre Nuclear Generating Station, Units 2 & 3 Bechtel Job No. 10079, Letter to H. L. Richter (SCE) from R. L. Rogers O (eechtei) 3.0 PREREQUISITES 3.1 An emergency has been declared at San Onofre Units 2 & 3.

3.2 The Emergency Coordinator has requested a source term determination from the affected reactor containment.

3.3 If dose rate measurement from portable survey instruments are required, personnel shall be briefed by the Walth Physics Leader prior to being dispatched.

4.0 PRECAUTIONS 4.1 Source tem determination is an estimate of the rate of release of radioactive material from containment.

4.2 Dose rate measurements from portable survey instruments are only necessary if the ERMS and In-Containment Monitors are inoperative.

O I

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 REVISION 1 Page 2 UNITS 2 AND 3 5.0 CHECK-OFF LISTS 5.1 Reactor Containment Activity Using ERMS Monitors Worksheet and Check-Off List ( Attachment 8.1).

5.2 Reactor Containment Activity Using In-Containment Monitors Worksheet and Check-Off List (Attachment 8.2).

5.3 Reactor Containment Activity Using Portable Instrumentation Worksheet and Check-Off List (?.ttachment 8.3).

5.4 Reactor Containment Activity Using Effluent Sampling or the Post Accident Sampling System (PASS) Checklist (Attachment 8.4).

5.5 Source Tem Calculation Using Containment Leakage Checklist (Attachment 8.5).

5.6 Source Tem Calculation Using Effluent Monitors Checklist (Attachment 8.6).

5.7 Source Tem Calculation Using Effluent Sampling or Post-Accident Sampling System (FASS) Checklist (Attachment 8.7).

6.0 PROCEDURE ta a accideat =$tuatiaa coat ia eat shou'd be 'so' ted- 'h e O(

radioactivity inside containment can be estimated with four possible sets of instrumentation; the In-Containment monitors, the ERMS monitors, portable instrumentation, or via a gas sampling and analysis method. The Ci content of containment should be calculated with all of the available methods and the highest result used. Portable instrumentation should be used as a back-up method only.

6.1 Reactor Containment Activity Using ERMS Monitors (use Attachment 8.1 ) .

6.1.1 Log the ERMS readings from RE 7858-1, RE 7859-2 and RE 7860-3 taken from panel ZL 154/165 (outside Control Room)'on Attachment 8.1, Step 1.0. Pe rfom multiplication to get total curies available for release.

6.1.2 Log tG fate and time the readings were taken and ini tiiC. _

6.1.3 Enter the highest Ci total into Steps 2.1 and 2.2.

Calculate the I-131 and Xe-133 activity available for release from containment.

O l_ _ -- - --

l l

l*

l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22

. UNITS 2 AND 3 REVISION 1 Page 3 i

- 6.0 PROCEDURE (Cont'd) e 6.1 (continued) 6.1.4 Notify the Emergency Coordinator of the results.

6.2 Reactor Containment Activity Using the High Range In-Containment Monitors (use Attachment 8.2) .

6.2.1 Enter the mR/hr readings from RI-7820-1 and RI-7820-2 into Attachment 8.2 Ste)s 1.1 and 1.2, respectively.

Perfom the multiplicatton to determine the total curies available for release, as detemined by each of the detectors.

6.2.2 Select the higher value and enter this value in Step 2.1 and 2.2. Perfom the multiplication to detemine the I-131 and Xe-133 available for release.

6.2.3 Notify the Emergency Coordinator of the results.

6.3 Reactor Containment Activity Using Portable Instrumentation (use Attachment 8.3).

NOTE: These locations may be inaccessible due to high radiaiton levels.

O 6.3.1 Brief survey team on the location (s) to be surveyed.

( Complete Step 1.0 of Attachment 8.3. The locations selected should be as close as is practical to the ERMS detector.

6.3.2 Dispatch survey team in accordance with Emergency Procedure S023-VIII-24. " Direction of Onsite Emergency Monitoring".

6.3.3 Log the survey team results for locations surveyed on Attachment 8.3, Steps 2.1, 2.2, and/or 2.3.

6.3.4 If more than one of the ERMS detector locations were surveyed, determine the highest reading (mR/hr) and perfom the multiplication survey reading in Steps 2.1_o_niy 2.2 or 2.3 for the highest to detemine the total curies available for release.

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t SAN ONOFRE NUCLEAR GENERATING STATION DIERGENCY PROCEDURE S023-VIII-22 i Page 4 i, UNITS 2 AND 3 REVIS!0N1 6.0 PROCEDURE (Cont'd) 6.3.5 Enter the highest value obtained in 2.1, 2.2 or 2.3 1

e in Steps 3.1 and 3.2. Perfom the multiplication to detemine the I-131 and Xe-133 activity available for release from containment.

6.3.6 Notify the Emergency Coordinator of the results.

6.4 Reactor Containment Activity Using Effluent Sampling or Post I kcident Sampling System (PASS) ( Attachment 8.4).

6.4.1 From effluent sampling analyses, record the concentrations of I-131 and Xe-133 in Step 1.0 of

Attachment 8.4.

1 l 6.4.2 In Step 2.0, multiply by the conversion factors to

' obtain the total C1 of I-131 erd Xe-133 available for

! release from containment.

I 6.4.3 From the PASS analyses, record the concentrations of 1-131 and Xe-133 in Step 3.0 of Attachment 8.4.

i s

6.4.4 In Step 4.0, enter the I-131 and Xe-133 l concentrations and multiply by the conversion factor l

4 to obtain the total Ci of I-131 and Xe-133 available

<ar r ' <ra coat $a at-O .

I 6.5 Source Tem Calculation At this point, we have estimated the amount of radioactivity in

! containment. The source tem, i.e., radioactivity release rates, !

are calculated from releases occurring either from containment !

! leakage or from the plant stack. j I Source Tem From Containment Leakage ( Attachment 8.5). !

6.5.1 j

i

.1 Detemine the amount of I-131 (Ci) and Xe-133 (Ci) :

available for release from containment. This was done in procedures 6.1 through 6.4 above. Select the highest values, and enter in Steps 1.1 and 1.2 of 3 Attachment 8.5.

.2 The release rate from containment when it is isolated I is assumed to be 1.6 CFM. This indicates a 0.1%

i leakage rate per day. If better infomation is available, modify this assumption. Othemise, enter i

3 the assumed containment release rate in Step 2 of Attachment 8.5.

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4 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 REVISION 1 Page 5 UNITS 2 AND 3 6.0 PROCEDURE (Cont'd)

-Q

' .3 Enter the I-131 and Xe-133 Curie totals into Steps 3.1 and 3.2 respectively. Perfom the multiplication to obtain the release rates (Ci/sec) of I-131 and Xe-133.

6.5.2 Source Tem From Effluent Monitors ( Attachment 8.6).

.1 Log the reading from the Plant Stack Effluent Monitor (2RI-7865-1) in Step 1.0 of Attachment 8.6.

.2 Enter this value in Steps 1.1 and 1.2. Perfom the multiplication in Steps 1.1 and 1.2 to detemine the concentration (uci/cc) for 1-131 and Xe-133 in the plant stack.

. .3 1he stack release rate is assumed to be 166,000 CFM.

This indicates that two fans are running. If better infomation is available, modify this assumption.

Otherwise, enter the assumed release rate in Step 2.0.

.4 Enter the concentrations of I-131 and Xe-133 into Steps 3.1 and 3.2 respectively. Enter the stack <

release rate from Step 2.0 into Steps 3.1 and 3.2.

Perfom the multiplication to detemine the I-131 i

O (Cf/sec) and Xe-133 (Ci/sec) release rates.

6.5.3 Souce Tem from Effluent Sampling or Post Accident Sampling System (PASS) ( Attachment 8.7).

NOTE: This methodology can only be used if stack effluent sampling or the PASS methods and analyses have been perfomed.

.1 Obtain the I-131 and Xe-133 concentrations from Attachment 8.4. Select either effluent sampling or PASS results, depending on which is available. Lo g the I-131 (uct/cc) and Xe-133 ( uCi/cc )

concentrations in Attachment 8.7, Steps 1.1 and 1.2 respectively (as determined in Attachment 8.4).

.2 The stack release rate is assumed to be 166,000 CFM.

This indicates two (2) fans are running. If better infomation is available, modify the assumption.

Otherwise, enter the assumed release rate in Step 2.0.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 REVISIONI Page 6

. UNITS 2 AND 3

.3 Enter the concentrations of I-131 and Xe-133 into Steps 3.1 and 3.2, respectively. Enter the stack e

release rate into Steps 3.1 and 3.2. Perfom the multiplication to detemine the I-131 (Ci/sec) and Xe-133 (Ct/sec) release rates.

7.0 RECORDS Forward all records to the Administrative leader upon completion.

8.0 ATTACMENTS 8.1 Reactor Containment Source Tem Using ERMs Channels Worksheet and Check-Off List.

8.2 Reactor Containment Source Tem Using In-Contamination Monitors Worksheet and Check-Off List.

8.3 Reactor Containment Source Tem Using Portable Instrumentation Worksheet and Check-Off List.

r=

K. P. B ARR HEALTH PHYSICS MANAGER JSD:0128F/sss O

l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 atvistod i attac*t"T 81

'O uwtTs 2

a PAGE 1 0F 1 REACTOR CONTAINMENT ACTIVITY USING ERMS MONITORS WUKK5Htti AND CHtGK-Utt L151 mR/hr X 3.6E5 = Ci Total STEP 1.0 ERMS - RE 7858-1 =

ERMS - RE 7859-2 = mR/hr X 3.6E5 = Ci Total ERMS - RE 7860-3 = mR/hr X 3.6E5 = Ci Total Date Time HPL Initial s STEP 2.0 Select highest Ci total (above). Enter value below and multiply to get Ci I-131 and Xe-133 available for release.

STEP 2.1 ( Ci Total) x (.031) = C1 (I-131)

O/ STEP 2.2 ( Ci Total) x ( 136) = Ci (Xe-133)

Date Time HPL Initials 3.0 Emergency Coordinator notified of results.

Date Time HPL Initials O

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l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 O UNITS 2 > 3 REVISION i ATTACNMENT 8.2 PAGE 1 0F 1 REACTOR CONTAINMENT ACTIVITY USING IN-CONTAINMENT MONITORS WORK 5HEET AND CHECK-OFF LIST STEP 1.0 In-Containment Montors: .

mR/hr x (.644) = Ci Step 1.1 Detector RI-7820-1 tiotal Ci Availabl e for Release) mR/hr x (.644) = Ci Step 1.2 Detector RI-7820-2 (Total Ci Availabl e for Release)

STEP 2.0 Using the higher value from Step 1.0, enter value in Step 2.1 and 2.2.

O STEP 2.1 ( Ci To tal ) X ( .031 ) = Ci (1-131)

STEP 2.2 ( Ci Total) X (.136) = Ci (Xe-133)

STEP 3.0 Emergency Coordinator notified of rnults.

Date Time HPL Initiali i

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i-SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22

~

REVISION 1 ATTACMENT 8.3 UNITS 2 & 3 PAGE 1 0F 1 l REACTOR CONTAINMENT ACTIVITY USIhG PORTABLE IN51RUMLNIAT10N WORK 5MLtl ANU CHtCK-Utt LI5I STEP 1.0 Survey Team Briefed - Emergency Procedure 5023-VIII-24, initiated.

Date Time HPL Initials

STEP 2.0 Survey Team Results: (Using Portable Instrumentation)

Total Ci Available Dose Rate (mR/hr) Factor For Release Location STEP 2.1 RE 7858-1 ( ) x (3.6E5) =

l

! STEP 2.2 RE 7859-2 ( ) x (3.6E5)=

STEP 2.3 RE 7860-3 ( ) x (3.6E5) =

!O Date Time HPL Initials

! (

i STEP 3.0 Enter highest value below.

n STEP 3.1 ( Cf To tal ) X ( .031) = C1 (I-131)

( Ci Total) X (.136) = Ci (Xe-133)

STEP 3.2 Date Time HPL Initial 5 STEP 4.0 Emergency Coordinater notified of results.

l Date Time HPL Initial s l

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J SAN ONOFRE NUCLEAR GENERATING STATION EMEi"NCY PROCEDURE S023-VIII-22

(-} UNITS 2 AND 3 REVISION 1 ATTACMENT 8.4 PAGE 1 of 1 REACTOR CONTAINMENT ACTIVITY USING EFFLUENT SAMPLING OR PASS CHECKLIST STEP 1.0 1-1 31 Effluent Sampling Concentration uCi/cc Xe-133 Effluent Sampling Concentration u Ci/cc STEP 2.0 uti x 6.51 E4 = Ci (I-131) i I-131 cc uti x 6.51 E4 = C1 (Xe-133)

Xe-13 3 E STEP 3.0 I -1 31 PASS Concentration pCi/cc ye-133 PASS Concentration uCf /cc STEP 4.0 uti x 6.51E4 = Ci(I-131 )

O I-131 E ,

(

p Ci x 6.51 E4 = Ci ( Xe-133)

Xe-133 E O

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-22 REVISION 1 ATTACHMENT 8.5 UNITS 2 AND 3 PAGE 1 of 1

< SOURCE TERM CALCULATION USING CONTAINMENT LEAKAGE CHECKLIST Step 1.0 NOTE: Use highest values obtained for Containment Activity from Attachments 8.1, 8.2, 8.3, or 8.4.

Ci 1.1 1-131 Total Curies Available For Release

]

Xe-133 Total Curies Available For Release Ci 1.2 Containment Relcese Rate CFM Step 2.0 Step 3.0 Radioactivity Release Rate Calculation 3.1 Ci (I-131) x (7.25 E-9) x CFM = C1/sec

( 3.2 C1 (Xe-133) x (7.25 E-9 x CFM = _Ci/sec 1

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M SAN ONOFRE NUCLEAR GENERAT.NG STATION EMERGENCY PROCEDURE S023-VIII-22 REVISION 1 ATTACINENT 8.6 l UNITS 2 AND 3 '

PAGE 1 of 1 r

SOURCE TERM CALCULATION USING EFFLUENT MONITORS CHECKLIST STEP 1.0 Stack Effluent Monitor: uCi/cc 1.1 uti/cc x . 0 31 = uti/cc Stack Effluent I-131 Con-Monitor Reading centration 1.2 uti/cc x .136 = uti/cc Stack Effluent Xe-133 Co n-Monitor Reading centration STEP 2.0 Stack Release Rate: CFM STEP 3.0 Radioactivity Release Rate Calculation 3.1 uCi/cc x CFM x 4.72x10-4 = Ci/sec s 1-131 stack stack Release 1-131 Release Concentration Rate Rate

(

3.2 uti/cc x CFM x 4.72x10-4 = Ci/sec Xe-133 Stack Stack Release Xe-131 Release Concentration Rate Rate O

>> 1

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' l SAN Oh0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-YIII-22

'() UNITS 2 'AND 3 REVISION 1 ATTACHMENT 8.7 PAGE 1 of 1 7' l l

SOURCE TERM CALCULATION USING EFFLUENT SAMPLING OR PASS ANALYSE 5 CHECKLISI l

l STEP 1.0 Effluent Sampling Concentrations or PASS Concentrations I 1.1 1-131 Concentration u Ci/c c 1.2 Xe-133 Concentration uCi/cc

! STEP 2.0 Stack Release Rate: CFM i

) STEP 3.0 Radioactivity Release Rate Calculation s

3.1 uCi/cc x CFM x 4.72x10-4 = Ci/sec

1-Ist Stack stack Release I-131 Release 1

({]) - Concentration Rate Rate

(

I i 3.2 uCi/cc x CFM x 4.72x10-4 = Ci/sec

Xe-133 stack Stack Release Xe-133 Release Concentration Rate Rate 4

0

1 1

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-23 REVISION 1 Page 1 UNITS 2 AND 3 DOSE ASSESSMENTS OCT 3 1981 l

1.0 OBJECTIVE This procedure provides the dose calculation methodology for gaseous releases, during an emergency.

The Health Physics Leader shall e respo t}1[QSp%ementation of this procedure, or, in his a sen %$7gy'toordih clVQ

2.0 REFERENCES

/Kp l. g $1 4 1981 2.1 U.S. Nuclear Regulatory Commission, Reg NTdg d@TF.

"Onsite Meteorological Programs" ff 2.2 U.S. Nuclear Regulatory Commission, Regulatory Guide 1.145,

" Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants" 2.3 NUREG-0654, Rev.1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.4 U.S. Environmental Protection Agency, EPA-520/1-75-001, " Manual of Protective Action Guides and Protective Actions for Nuclear p)

U Incidents" 25 San Onofre Nuclear Generating Station, Unit 2 and 3 Final Safety Analysis Report, Section 15 2.6 San Onofre Nuclear Generating Station, Units 2 & 3, Emergency Plan 2.7 Emergency Procedure S023-VIII-22, " SOURCE TERM DETERMINATION" 2.8 Emergency Procedure 5023-VIII-41, "0NSITE MONITORING" 2.9 Emergency Procedure 5023-VIII-42, "0FFSITE MONITORING AND SAMPLING" 2.10 Emergency Procedure S023-VIII-27, " EMERGENCY ENVIRONMENTAL MONITORING" 3.0 PREREQUISITES 3.1 An emergency has been declared at San Onofre Nuclear Generating Station, Unit 2 and 3.

3.2 A gaseous release of radioactive material is in progress, or is projected to occur, or radioactive material has been released into containment.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-23

, UNITS 2 AND 3 REVISION 1 Page 2

'. Q ~

4.0 PRECAUTIONS Calculated doses are only estimates of the actual doses in the 4.1 i

plant environs.

4.2 Dose calculation estimates should be verified by actual field measurements. This is done by implementation of Emergency Procedures S023- VIII-41, "0NSITE MONITORING"; SO23-VIII-42, "0FFSITE MONITORING AND SAMPLING; and S023-VIII-27, " EMERGENCY ENVIRONMENTAL MONITORING".

5.0 CHECK-OFF LISTS 5.1 Attachment 8.1 - Determination of Atmospheric Dispersion Factors Checklists 5.2 Attachment 8.2 - Dose Calculations Checklist 6.0 PROCEDURE 6.1 Determination of Atmospheric Dispersion Factors (Use Attachment 8.1).

NOTE: In the determination of Atmospheric Dispersion Factors, meteorologic data from the SONGS Met Tower is< desirable.

o 1

If this data is unavailable in the Control Room, an individual may be dispatched to the Met Tower to read the local instrumentation indicators and report back to the Control Room.

If SONGS Met Tower data is unavailable, obtain met data, (wind direction and windspeed) from San Diego Lindberg Field,'. _ >(Identify yourself as SCE staff). Assume stability class F when using San Diego meterology.

6.1.1 Utilizing the best meterological information available, determine the windspeed ar.d log it in Step 1.0 of Attachment 8.1. Windspeed is indicated in MPH. Perform the multiplication to convert MPH to m/sec (or knots to m/sec if using San Diego data).

.1 Record the wind direction in degrees in Step 1.0.

Using Table I, determine the affected sector designation. Log this in Step 1.0 of Attachment 8.1.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-23 REVISION 1 Page 3 UNITS 2 AND 3 O 6.0 PROCEDURE (Cont'd) 6.1.2 Obtain the vertical temperature gradient ( AT) from Met Tower data and log it in Step 2.0.

6.1.3 Compare the AT observed above with the AT column of Table II in Attachment 8.1 to determine the Stability Class (A through G). If Met data is unavailable, assume Class F. Log the Stability Class in Step 3.0.

6.1.4 Using the stability class from above, look up the ADF X U values from Table III of Attachment 8.1.

These values are the Atmospheric Dispersion Factors (ADF) times the windspeed, U. Log these values in Step 4.0. Then divide them by the current windspeed to get the ADF's.

6.2 Dose Rate Calculation 6.2.1 Dose rate calculations are performed at five distances eauivalent to locations at the beach (83m),

Exclusion Area Boundary (600m), 2 miles, 5 miles,10 miles, 20 miles, and 50 miles. The data needed for these calculations is the source term (EPIP SO23-VIII-22)and the ADF's, (Step 4, Attachment 8.1 O',..

of this procedure).

6.2.2 Perform the calculations requested in Attachment 8.2, Step 2.0.

7.0 RECORDS 7.1 Foward all records and calculation worksheets to the Administrative Leader 8.0 ATTACHMENTS 8.1 Determination of Atmospheric Dispersion Factors Checklist 8.2 Dose Calculation Checklist

.Ictsr -

K. P. BARR HEALTH PHYSICS MANAGER RLS:0129/sss i (

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t _ m

l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-23 UNITS 2 & 3 REVISION 1 Page 1 of 3 O ATT^casEnT 8.I DETERMINATION OF ATMOSPHERIC DISPERSION FACTORS CHECKLIST Step 1.0 (Use the 10 meter chart recorder)

Wind Speed: ( MPH) X (.447) =U= m/sec Knots) X (.514) = m/sec

(

Wind Direction: Degrees (Obtain the affected sector from attached Table I)

Affected Sector Designation (By Letter)

Step 2.0 Determine from Met Tower instrumentation, the vertical temperature gradient.

AT = degrees C Step 3.0 Determine the Stability Class (From Table II, attached).

Stability Class

(

HPL Initials Time Date Step 4.0 Atmospheric Dispersion Factor (ADF)

Using the stability class from above, look-up the ADF X U values for each of the locations from Table III. Log these values below.

Then divide them by the windspeed, U, in m/sec from Step 1.0 above and log into the table below:

BEACH EAB 2 MILES 5 MILES 10 MILES 20 MILES 50 MILES ADF X U ADF NOTE: Divide [ADF X U] by the windspeed (Step 1.0 in m/sec) to get the ADF values.

O

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-23 UNITS 2 & 3 REVISION 1 Page 2 of 3 O) t v TABLE I ATTACHMENT 8.1 WIND DIRECTION TABLE DEGREES SEC10R DESIGNATION 348.75'-11.25' J 11.25'-33.75' K 33.25'-56.25' L 56.25*-78.75' M 78.75*-101.25' N 101.25*-123.75* P 123.75'-146.25* Q 146.25'-168.75' R 168.75*-191.25' A 191.25*-213.75' B O 213.75 -238.25- . C 236.25*-258.75* D 258.75*-281.25* E 281.25*-303.75" F 303.75'-326.25' G 326.25'-348.75* H l

0

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY' PROCEDURE S023-VIII-23 UNITS 2 & 3 REVISION 1 Page 3 of 3 ATTACHMENT 8.1

-())) -

TABLE II DETERMINATION OF ATMOSPHERIC DISPERSION FACTORS Classification of Atmospheric Stability by AT-

! Stability Class AT ( *C)

A < ( .57)

R ( .56) to ( .51)

C ( .50) to ( .45)

D ( .44) to ( .15)

E ( .14) to (+.45)

F ( .46) to (1.2)

G > 1.2 O

J

> O

i t<; .

,a

'f 'l t

L./

m N

e

=O @

>eb w e N N e e

.J e e e e a MW - O O W W W W W 3 N Z in. en. O. e.

Q3 en C m N e N en n e WO E+1 DA @

O w N N e e en w J e e a e e U = -

O O w w w w w 3 en O E e.

E e en. e.

A O - e N *e. -

- e= m

)-

UZw r

ZOK w-Z W O en u w

-4 J N e e en en

> s- -

O O e o e e a wm I w w w w w E4 a. m. &. in. e.

=O 3 = 2 - m

(

E

-O M N w e e e en en en 4 = D J e O O w w w w w e a e EO -WDC I en. m. N. N. N.

O J 6 e - en .- m N E to O

- 4 4 W W 4

E w

IE W w w W e en en en a e O J e e e e e

- O w w w w w w E Z

( e. in. N. in. O. O.

W N e in N m m N

.J O

D Um en en en 3 3 3e 3 e e wO e a e o t: r m w w w w w we w w4 < N. m. a. en. m.

O w N. .

ZN - # m N m in 5 O

N 2-47t MD Z 3 3 3 3 3 3 2 O e e e e o e e

< w w w w w w w w

e o. N. m. a. e. . m.

a en 5 e e m o r% @

D f \

\

o J 4 m O O W 6 0 eO

SAN DNOFRE NUCLEAR GENERATI"' ?T'JION EMERGENCY PROCEDURE SO23-VIII-23 UNITS 2 & 3 REVISION 1 Page 1 of 4

,() ATTACHMENT 8.2 DOSE CALCULATION CHECKLIST Step 1.0 (Obtain highest source term data from EPIP-S023-VIII-22)

(Obtain met dat'a from attachment 8.1, this procedure)

/ /

TIME DAY DATE 4

Source Term: Ci/sec(Xe-133) Ci/Sec(I-131)

Windspeed MPH m/s Stability Class Wind Direction From: (Degrees)

Affected Sector Designation (By Letter) l BEACH EAB 2 MILE 5 MILE 10 MILE 20 MILE 50 MILE ADF's O Sten 2.o

( Dose Rate (DR) at Beach l

i 4 WHOLE BODY DR = ADF (at beach) X Source Term (Xe-133) X 3.36E4 DR = X X 3.36E4 = mrem /hr ADF Xe-133 a

t 1

i I

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_m -__a _-_ __

- m m-----

SAN ONOFRE NUCLEfR GENERATING STATION i EMERGENCY PROCEDURE 5023-VIII-23 UNITS 2 & 3 REVISION 1 Page 2 of 4 ATTACHMENT 8.2

,( )

THYROID DR = ADF (at beach) X Source Term (I-131) X 1.85E9 X 1.85E9 = mrem /hr DR = X ADF 1-131 Step 3.0 Dose Rates at EAB WHOLE BODY DR = ADF (at EAB) X Source Term (Xe-133) X 3.36E4 4

X X 3.36E4 = mrem /hr 4 DR =

ADF Xe-133 THYROID j OR = ADF (at EAB) X Source Term (I-131) X 1.85E9 DR = X X 1.85E9 = mrem /hr ADF 1-131

( Step 4.0 Dose Rates at 2 Miles i

WHOLE BODY DR = ADF (at 2 Miles) X Source Term (Xe-133) X 3.36E4 DR = X X 3.36E4 = mrem /hr ADF Xe-133

, THYROID DR = ADF (at 2 Miles) X Source Term (I-131) X 1.85E9 DR = X X 1.85E9 = mrem /hr ADF I-131 l

0

SAN ONOFRE NUCLEAR GENERATING STATION' ~ - EMERGENCY PROCEDURE S023-VIII-23 UNITS 2 & 3 REVISION 1 Page 3 of 4 ATTACHMENT 8.2

'(-])

Step 5.0 Dose Rates at 5 Miles WHOLE BODY DR = ADF (at 5 Miles) X Source Term (Xe-133) X 3.36E4 X 3.36E4 = mrem /hr DR = X ADF Xe-133 THYROID DR = ADF (at 5 Miles) X Source Term (I-131) X 1.85E9 X 1.85E9 = mrem /hr DR = X ADF I-131 Step 6.0 Dose Rates at 10 Miles WHOLE BODY

() DR = ADF (at 10 Miles) X Source Term (Xe-133) X 3.36E4 DR = X X 3.36E4 = mrem /hr

( ADF Xe-133

. THYROID DR = ADF (at 10 Miles) X Source Term (I-131) X 1.85E9 X 1.85E9 = mrem /hr DR = -

X ADF I-131 Step 7.0 l

Dose Rates at 20 Miles WHOLE BODY DR = ADF (at 20 Miles) X Source Term (Xe-133) X 3.36E4 X 3.36E4 = mrem /hr DR = X ADF Xe-133 THYROID DR = ADF (at 20 Miles) X Source Term (I-131) X 1.85E9

() DR =

ADF X

1-131 X 1.85E9 = mrem /hr

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-23 UNITS 2 & 3 REVISION 1 Page 4 of 4

. ,,s ATTACHMENT 8.2

<() _

Step 8.0 Dose Rates at 50 Miles WHOLE BODY DR = ADF (at 50 Miles) X Source Term (Xe-133) X 3.36E4 DR = X X 3.36E4 = mrem /hr ADF Xe-133 THYROID DR = ADF (at 50 Miles) X Source Term (I-131) X 1.85E9 DR = X X 1.85E9 = mrem /hr ADF I-131 Step 9.0 Dose Rate Summary s / /

w TIME DAY , DATE

( Source Term: Ci/sec Xe-133 Ci/sec I-131 Wind Speed: MPH m/s Stability Class:

Wind Direction From: degrees Wind Direction Toward: sector designation mrem / hour BEACH EAB 2 MILE 5 MILE 10 MILE 20 MILE 50 MILE WHOLE BODY THYROID O

EfC'J3EMCY FROCEDURE S023-VIII-24 SH ONOFRE NUCLEAR GENERATING STATION Page 1 REVISION O UNITS 2 AND 3 pd SEP j J981 DIRECTION OF ONSITE EMERGENCY MONITORIM l

1.0 OBJECTIVE &E*b

\L i 1.1 This procedure provides the gliidance h6r coo direction of onsite radiological monitoring efforts y I/8 g ,

emergency. The Health Physics Leader (or in his absence g Fgy Emergency Coordinator) is responsible for the implementatio 8

this procedure. RECE pp OCT 141981

2.0 REFERENCES

2.1 NUREG-0654, Rev.1 Criteria for Preparation and Evaluatio:CotA SiTF.

Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants l I

2.2 San Onofre Nuclear Generating Station, Unit C and 3 Emergency Plan 3.0 PREREQUISITES 3.1 y condition has been declared at San Onofre Nuclear An emergenc$tation, Unit 2 and 3.

Generating i The Emergency Coordinator has requested onsite monitoring and/or O

V 3.2 emergency center - assembly area monitoring.

(

4.0 PRECAUTIONS 4.1 Monitoring teams should be reminded to inonitor their own exposures, and request relici if their cumulative exposure approaches an administrative mit. The Emergency Coordinator may authorize emergency exposure extensions in accordance with procedure 5023-VIII-31, " EMERGENCY EXPOSURE CONTROL."

4.2 Ensure that all comunications related to reporting monitoring data are brief and factual.

4.3 Ensure that instructions and data transmissions are carefully worded and understood:

4.3.1 Avoid abbreviations, use the complete word or unit.

4.3.2 Clearly identify survey locations, using predetemined survey locations, map coordinates, equipment and building names, as available.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-24 REVISION O Page 2 UNITS 2 AND 3 5.0 CHECK-0FF LISTS 5.1 Onsite Monitoring Checklist 6.0 PROCEDURE 6.1 Discussion 6.1.1 The extent and degree of onsite radiological monitoring following a release of radioactive material will depend on the nature, the severity, the physical / chemical fom, and the radioisotopic composition of the release. The Emergency Coordinator, with the assistance and advice of the Health Physics Leader, will detemine the extent and nature of post-accident radiological monitoring.

6.1.2 Sufficient Health Physics personnel will be available to support several monitoring teams for releases which occur during nomal working hours. During other times, it may only be possible to deploy one monitoring team immediately. In these circumstances, the Health Physics Leader will assign priorities for radiological monitoring based on the known or O Prosected redioiosicci coadisiaas. aiie ceiiias ia additional personnel. -

6.1.3 In the event of a radioactive release detemintd or estimated to be equivalent to or greater than 10 times the applicable technical specification, a monitoring team should be dispatched to perfom a beta-gama dose rate survey offsite. The purpose of this survey is to confim that a release is (has) taken place, and to assess the need for protective actions. The starting point of this survey should be consistent with the expected source and magnitude of the release and extend out to the site perimeter in the sector with the highest projected dose rate.

This survey should be limited to specific survey points rather than a " scan" survey in order to obtain initial data rapidly. Following this, time and personnel pemitting, more extensive scan surveys may be perfomed if warranted. Based on the survey results at this point, the monitoring team should proceed along the site perimeter for a sufficient distance in either direction to ensure that the maximum levels have been identified. This survey should be perfomed periodically if the release continues and if personnel are available.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-24 UNITS 2 AND 3 REVISION O Page 3

, 6.0 PROCEDURE (Continued) 6.1 Discussion (Continued)

6.1.4 Silver zeolite cartridges will be used for all air sampling. Upon completion of field analysis of the cartridges, return cartridges to the plant for analysis using laboratory instrumentation. All samples obtained by the monitoring teams will be returned to the plant for additional analysis.

6.1.5 If a Local Area Evacuation has been initiated, based on area radiation monitors or continuous air monitors, an appropriate survey should be perfomed

, to verify the alam condition and to attempt to determine the reason for the increase from nomal

' levels.

6.1.6 If a Plant Evacuation is declared, a survey should be performed in the primary Assembly Area (AWS Building Supply Center to verify the reading of the Control j Room area radiation monitor, and an air sample for

' particulate and iodine radioactivity should be obtained, if the monitor indicates he need, or if airborne activity is suspected.

Q General Instructions for Onsite Monitoring

( 6.2 6.2.1 Use available infomation (meterologicel infomation, effluent monitors, radiation monitor, etc.) to defir.e sector (s) or area (s) to be monitored.

.1 If in-plant monitoring is indicated, detemine area (s) to be monitored and best route for monitoring team (s) to approach area (s).

.2 If out-of-doors onsite monitoring is indicated, detemine the direction of the pime and i detemine which sector (s) should be monitored.

Identify specific locations to be monitored.

L 6.2.2 Assemble monitoring team (s). Ensure that at l least one member of each team is qualified to perfom radiological surveys.

6.2.3 Brief monitoring team (s) on sector (s) or area (s) to be monitored; radiological j

conditions and other potential hazards that may i

be encountered; precautions to be observed; and O Protective ciotnias or eau 4P eat as aecess rx-NOTE: If necessary, ensure that Radiation Exposure Pemit(s) and/or Emergency Exposure Authorizations are obtained. ,

. _ = . _ _ - ._. . . .-- .. . . -

4 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-24 UNITS 2 AND 3 REVISION O Page 4

_ 6.0 PROCEDURE (Continued) 6.1 Discussion (Continued) l' 6.2.4 Dispatch monitoring team (s). Maintain frequent radio contact and track progress of team (s) on a map or plan view as appropriate.

6.2.5 Record monitoring data as it is received over the radio. Backup readings or samples should be taken if appropriate. Remind team members to monitor their own exposure.

6.2.6 If initial results indicate that more complete J

data is needed, or that adjacent areas should be surveyed, direct monitoring team (s) to l perfom additional monitoring at specified

locations.

6.2.7 Upon completion of monitoring, recall 4

monitoring team (s). Instruct team leader to report to the TSC for debriefing, if necessary.

6.2.8 Evaluate monitoring data and advise the Emergency Coordinator of the results.

j Q I ( 6.2.9 Implement emergency procedure S023-VIII-44,

" EMERGENCY CONTAMINATION CONTROL", if appropriate. Implement Emergency Procedure J S023-VIII-43, " Sample Coordination during an Emergency".

6.2.10 Evaluate laboratory analyzed data and adivse the Emergency Coordinator of the results. Upon receipt of survey foms, review and submit to the Administrative Leader for filing.

6.3 Specific Instructions for Emergency Center / Assembly Area

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Monitoring 6.3.1 Local Evacuation Assembly Area _s_:

.1 If the evacuation is frem a contaminated area or results from an airborne release of radioactivity, direct monitoring team to perfom the following surveys:

.1.1 Contamination smear survey of floor area route to assembly area.

O .1.2 Personnel contamination monitoring with V particular emphasis on the face, hands and feet.

.1.3 Airborne radioactivity survey utilizing a particulate filter and silver zeolite cartridge.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-24 REVISION O Page 5 UNITS 2 AND 3

! ,, 6,0 PROCEDURE (Continued) 4 i 6.3.1 (Continued) i

.2 If the evacuation is from a clean area and is l the result of a radiation alam, perfom the following surveys:

- .2.1 Dose Rate Survey with open and closed shielded

! readings.

.2.2 Personnel and Assembly Area floor contamination survey.

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.2.3 Airborn'e survey; only if contamination greater than 100 p on individuals or 1000 !

I cpm /100cm' on the floors is found.

.3 If the results of the radiation surveys at the assembly area (s) indicate levels in excess of

]

100 arem/hr or gross airborne radioactivity in excess of 4E-8 uCi/cc, or if continued occupancy is expected to result in excess of 40 MPC-hrs. for isotopic mix less noble gasses; re'oc te to aother ^=se 617 are ad aotifs j O --

the EC.

! ( .4 If only contamination is found then control l

egress from the area by ensuring all personnel j exiting area t.re clean or wearing sufficient non-contamine%C patective clothing to prevent i

spread of th tattinination.

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.5 The cT e V .an and airborne surveys will only U Asf %A initially, and as requested by EC. The cose rates in the Assembly Area should be continuously monitored until the i emergency condition is teminated.

6.3.2 Plant Evacuation Assembly Areas:

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.1 No surveys other than nomal exM monitoring 4 '

(frisking) are necessary if the evacuation is precautionary and no release of radioactive

material locally or to the environs has occurred.

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.2 If the evacuation is the result of a release of

' radioactive material, known or supsected, the following site assembly areas should have dose rate coat ==4a tioa. ae irborae survers

' O conducted at the locations below in the following preferential order:

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EMERGENCY PROCEDURE S023-YIII-24 SAN ONOFRE NUCLEAR GENERATING STATION PAGE 6 REVISION O i

, UNITS 2 AND 3

- 6.0 PROCEDURE (Continued) 6.3.2 (Continued)

.2.1 The AWS Warehouse NOTE: No survey is necessary at the CDM Center as the AWS Warehouse surveys should be sufficient to ascertain the conditions in that area.

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.2 If conditions pemit, tuch as the release has ceased or is not affecting the Assembly, area contamination control efforts should be conducted to ensure minimal contamination is spread further.

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.3 If the results of the surveys at the Assembly l

Area indicate levels in excess of 100 mrem /hr or gross airborne radioactivity in excess of i 4E-8 uCi/cc, or if continued occupancy is i expected to result in excess of 40 MPC-:1ours for isotopic mix less noble gasses, notify EC 4

and request pemission to relocate to an Offsite Assembly Area.

t I f .4 The frequency of monitoring should be as follows:

.4.1 Contamination - initally and as directed by the i

EC or HPL if conditions deteriorate.

.4.2 Radiation Dose Rate - continuously

.4.3 Airborne - initially and once every 1/2 hnur unless directed otherwise by the EC or HPL, 6.3.3 Site Evacuation Assembly Areas:

NOTE: Monitoring of Offsite Assembly Areas is covered in this procedure as well as " Direction of Offsite Monitoring" as a matter of convenience.

.1 No surveys other than nomal existing monitoring cre necessary if the evacuation is precautionary and no release of radioactive material locally or to the environs has l

occurred.

l EMERGENCY PROCEDURE SO23-VIII-24 SAN ONOFRE NUCLEAR GENERATING STATION Page 7 REVISION O i UNITS 2 AND 3

!O 6 0 PROCEDURE (Continued) 6.3.3 (Continued)

.2 If the evacuation is the result of release of radioactive material, known or suspected, the designated Offsite Assembly Area should have dose rate, contamination, and airborr.e surveys conducted.

.3 If conditions pemit, such as the release has ceased or is not affecting the Offsite Assembly Areas, contamination control efforts should be conducted to ensure minimal contamination is spread further or leaves the site.

.4 If the results of the surveys at the Offsite Assembly aree(s) indicate levels in excess of 100 arem/hr or gross :tirborne radioactivity in excess of 4E-8 pCi/cc, or if centinued occupancy is expected to result ir, excess of 40 MPC-hours for isotopic mix less noble gasses, notify EC and request pemission to relocate to the Alternate Offsite Assembly Area.

.5 The frequency of monitoring should be as

( follows:

.5.1 Contamination - initially and as directed by the EC or HPL if conditions deteriorate.

.5.2 Radiation Dose Rate - continuously.

.5.3 Airborne - initially and once every 1/2 hour unless directed otherwise by the EC or HPL.

6.3.4 Control Room and TSC

.1 Radiation Dose Rates shall be monitored continuously

.4.2 Airborne surveys should be obtained every 30 minutes or more frequently if the radiation dose rate surveys indicate a rise in noble gas airborne activity.

NOTE: If no release of radioactive material is occurring the airborne surveys are not necessary.

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EMERGENCY PROCEDURE S023-VIII-24 SAN ONOFRE NUCLEAR GENERATING. STATION Page 8 REVISION O

, UNITS 2 AND 3 6.0 PROCEDURE (Continued) 6.3.4 (Continued)

.4.3 Personnel Contamination Surveys should be i

perfomed prior to entering the TSC or Control

' Room.

Surface contamination surveys should be 4

perfonned every 30 minutes.

4.4 Evacuatior, of the Control Room and TSC should i

i only be implemented for radiological conditions

' which exceed Attachment i radiation dose rates, l

radiciodine concentrations and/or associated i pemissable occupancy times.

t 6.3.5 OSC and ESC

.1 Radiation dose rates should be monitored continuously.

.2 Airborne surveys should be obtained every 30 minutes.

^

NOTE: If no release of radioactive material is occuring then airborne surveys are not necessary.

.3 Personnel Contamination Surveys should be t

perfomed prior to entering the OSC and ESC.

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.4 Surface contaminai. ion surveys should be perfomed every 30 minutes.

.5 If the results of the radiation surveys at the OSC or ESC indicate levels in excess of 100 mrem /hr or gross airborne radioactivity in excess of 4E-8 uCi/cc, or if continued occupancy is expected to result in excess of 40 MPC-brs for isotopic mix less noble gasses; relocated to an unaffected area designated by the EC.

NOTE: In case of OSC evacuation, relocation should be to the Units 2 and 3 OSC if radiological conditions pemit.

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- SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-24 REVISION O PAGE 9 UNITS 2 AND 3 7.0 RECORDS 7.1 Forward the results of all radiation monitoring and assessment actions to the Administrative Leader.

8.0 ATTACMENTS 8.1 Criteria for Mandatory Evacuation.

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K. P. BARR HEALTH PHYSICS MANAGER O

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-24 REVISION O Page 1 of 2 ATTACit4ENT 8.1

{ UNIT 2 AND 3

^

- CRITERIA FOR MANDATORY ONSITE EVACUATIONS WHOLE BODY IMPLEMENT RADIOI0 DINE EVACUATION CONCENTRATION DOSE RATE WITHIN (p CI/cc) l (arem/ hour)

Up to 600 8 Hours Up to 1E-5 )

600 to 1000 4 Hours lE-5 to 2E-5 1000 to 2500 2 Hours 2E-5 to 4E-5 2500 to 5000 1 tur 4E-5 to 7E-5 5000 to 10,000 30 min. 7E-5 to 1E-4 10,000 to 20,000 15 min. 1E-4 to 3E-4

> 20,000 IMEDIATELY > 3E-4 O(

,. It is 4mportant to reaiize that there is no direct corre,ation between the whole body dose rates and the radioiodine concentrations; and the measurements or projections of each must be performed independently.

In the event that only a direct radiation detennination is available, with no corresponding knowledge of the concentration or fraction of the total which is attributable to radiciodine, the most conservative assumptions specified in the USEPA Manual for Protective Action Guides would be required. Such assumptions, based only on direct radiation detenninations, would likely result in gross over-estimation of thyroid dose comitment.

2. Whole body dose to non-emergency personnel should not exceed 5000 mrem -

from the event. The whole body dose rates specified above are based on 5000 mrem. This value is based on the UPESA PAG Manual specified upper limit for members of the general public. Although this table specifies mandatory evacuation times, in the absence of significant constraints evacuations should be implemented to maintain personnel exposure as low as reasonably achievable and within specified quarterly exposure limits.

3. Maximum concentrations for specified time correspords to approximately 25,000 mrem adult thyroid dose comitment. Radioiodine concentration vs. adult thyroid dose comitment based on Appendix 0, (January 1979) to U5EFK' Manual of Protective Action Guides. Radiciodine nuclide distribtution corresponds to four (4) hours following reactor shutdown.

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EMERGENCY PROCEDURE S023-VIII-24 SAN ONOFRE NUCLEAR GENERATING STATION Page 2 of 2 REVISION O UNIT 2 AND 3 ATTAC *ENT 8.1

- ONSITE MONITORING CHECKLIST

1. Onsite monitoring to be perfonned at the following locations:

HPL Initials lime Date 1 l

2. Monitoring team (s) briefed and dispatched.

HPL IninaTs Time Date

3. Monitoring team (s) recalled.

HPL Initials Time Date

4. Sumary of radiological conditions:

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( l Reported to Emergency Coordinator:

HPL Initials Time Date

5. Procedures Implemented:

HPL Initials Time Date

6. Sumary of Laboratory Data:

Reported to Emergency Coordinator:

O HPL Initials Time Date DM:0094F/sf

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-25

'{l REVISIO ' PAGE 1 UNITS 2 & 3 gg DIRECTION OF 0FFSITE EMERGENCY MONITORI p 1.0 OBJECTIVE

/04/ N r '0

/

This procedure provides the guidance for coordination and 5 //

offsite radiological monitoring efforts during an emergency. Q ,

Physics Leader is responsible for the implementation of this proced

2.0 REFERENCES

2.1 NUREG-0654, Rev.1 Criteria for Preparation and Evaluation of Radio-f logical Emergency Response Plans and Preparedness in Suppqrt-3 gtygr Power Plants 2.2 San Onofre Nuclear Generation Station, Units 2 & 3 Emergenh1 n CDM S!TE 3.0 MEREQUISITES 3.1 An emergency condition has been declared at San Onofre Nuclear Gener-ating Station, Units 2 & 3.

3.2 The Emergency Coordinator has requested offsite monitoring.

f')

v f 4.0 PRECAUTIONS 4.1 Monitoring teams should be reminded to monitor their own exposures, and request relief if their cumulative exposure approaches an administrative limi t. The Emergency Coordinator may authorize emergency exposure ex-tensions in accordance with Emergency Procedure 5023-VIII-31, " Emergency Exposure Control".

4.2 Ensure that all comunications related to reporting monitoring data are brief and factual.

4.3 Ensure that instructions and data transmissions are carefully worded and understood: l 4.3.1 Avoid abbreviations, use the complete word or unit.

4.3.2 Clearly identify survey locations, using predetemined survey locations, map coordinates, equipment and building names, as available.

5.0 CHECK-0FF LISTS 5.1 Offsite Monitoring Checklist O

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O sin onorat #UcLena acutan11ao station UNITS 2 & 3 Estaatucv eaoctount so23-v111-2s REVISION NEW PAGE 2 i

6.0 PROCEDURE 6.1 Discussion 6.1.1 The extent and degree of offsite radiological monitoring following a release of radioactive material will depend on the nature, the severity, the physical / chemical fom and the radioisotopic composition of the release. The Health Physics Leader, (or in his absence the Emergency Coordinator), will detemine the extent and nature of post-accident radiological monitoring.

6.1.2 Sufficient health physics personnel will be available to support several monitoring teams for releases which occur during normal working hours. During other times, it may only be possible to deploy imediately one monitoring team.

In these circumstances, the Health Physics L>ader will assign priorities for radiological monitoring based on the known or projected radiological conditions, while calling in additional O( Persoaaei-silver zeolite cartridges will be used for all air sampling.

6.1.3 Upon completion of field analysis of the cartridges, return cartridges to the plant for analysis using laboratory instru-mentation. All samples obtained by the monitoring teams will be returned to the plant for additional analysis.

6.2 General Instructions For Offsite Monitoring 6.2.1 Use available information (meteorological infomation, effluent monitors, radiation monitors, etc.) to define sector (s) or area (s) to be monitored.

6.2.2 Assemble monitoring team (s). Ensure that at least one member of each team is qualified to perform radiological surveys.

6.2.3 Brief monitoring team (s) on sector (s) or area (s) to be monitored; radiological conditions; precautions to be ob-served; and protective clothing or equipment as necessary.

6.2.4 Dispatch monitoring team (s). Maintain frequent radio contact and track progress of team (s) on a map or plan view as appro-priate.

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n O San On0raE uUC'E^a cEnEa^11ao STATI0" UNITS 2 & 3 eMEacEuCv eROCE00RE 5023-vlII-2s REVISICN NEW PAGE 3 6.0 PROCEDURE (Cont'd) 6.2.5 Advise teams to scan (move back and forth) with instruments to locate highest reading in a plume.

6.2.6 Record monitoring data as it is received over the radio.

Direct backup readings or samples be takan if appropriate.

Remind team members to monitor their own exposure.

6.2.7 If initial results indicate that more complete data is needed, or that adjacent areas should be surveyed, direct monitoring team (s) to perform additional monitoring at specified locations.

6.2.8 Upon completion of monitoring, recall monitoring team (s).

Instruct team leader to report to the TSC for debriefing, if necessary.

6.2.9 Evaluate monitoring data and advise the Emergency Coordinator

! of the results.

) Implement Emergency Procedure S0'23-VIII-26, " Recommendations

' 6.2.10

~

l for Offsite Protective Measures", if appropriate.

6.2.11 Evaluate laboratory analyzed data and advise the Emergency Coordinator of the results. Upon receipt of survey foms, review and submit to the Administrative Leader for filing.

6.3 Specific Instructions For Offsite Assembly Area Monitoring 6.3.1 In the event of Site Evacuation, the designated offsite assembly area shall be surveyed for dose rate, airborne and contamination conditions.

6.3.2 If the results of the radiation surveys at the remote assembly area (s) indicate levels 'n excess of 100 mrem /hr or gross airborne radioactivity ir excess of 4E-8 pCi/cc, or if occu-pancy is expected to.restit in excess of 40 MPC-hours for isotopic mix less noble c ases; relocate the personnel and vehicles to the alternate offsite assigned reception centers designated by County Emergency Response Personnel.

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.n-v SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-25 REVISION NEW PAGE 4 UNITS 2 & 3 6.0 PROCEDURE (Cont'd) 6.3.3 The frequency of monitoring should be as follows:

i

.1 Contamination initially and as directed by the Emergency Coordinator or Health Physics Leader if conditions deteri-i orate.

, .2 Radiation Dose Rate - continuously.

.3 Airborne initially and once every 1/2 hour unless directed

] otherwise by the Emergency Coordinator or Health Physics Leader.

7.0 RECORDS Forward the results of,all radiation monitoring and assessment actions to the Administrative Leader.

8.0 ATTACHMENTS 8.1 Offsite Monitoring Checklist K. P . MRR HEALTH PHYSICS MANAGER i

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' EMERGENCY PROCEDURi It?3-VIII-25

. SAN DN0FRE NUCLEAR GENERATING STATION REVISION NEW AT:4CHMENT 8.1 1

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, UNITS 2 & 3 PAGE 1 0F 1 '

/~')s

\.

0FFSITE MONITORING CHECKLIST

1. Offsite monitoring to be performed at the following locations:

Time Date HPL Initials

2. Monitoring team (s) briefed and dispatched.

Time Date HPL Initials 4

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3. Monitoring team (s) recalled.

Time Date HPL Initials

4. Summary of radiological conditior.s:

Reported to Emergency Coordinator HPL Initials Time Date

5. Procedures Implemented:

Time Date -

HPL Initials

6. Summary of Laboratory Data:

4 Reported to Emergency Coordinatcr: HPL Initials Time Date

l SAN Oi10FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-26

.O REVISION NEW PAGE 1 ;

V UNITS 2 & 3 RES RECOMMENDATION FOR OFFSITE P T '

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Fyj 1.0 OBJECTIVE gg 7 This procedure provides the guidance for t y in making recommendations for offsite protective .

Coordinator. The Health Physics Leader is responsible tion of this procedure. The Emergency Coordinator is rescon making the recomendations to state and local emergency authoritie 47/

protective actions.

RECEIVEP NOTE: The responsibility to make protective action recomendations can not be delegated. OCT 141981 CDM S'TE

2.0 REFERENCES

2.1 NUREG-0654, Rev.1, Criteria for Preparation and Evaulation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2 EPA 520/1-75-001, Manual of Protective Action Guides and Protective

~] Actions for Nuclear Incidents 2.3 San Onofre Nuclear Generating Station, Units 2 & 3 Emergency Plan 3.0 PREREQUISITES 3.1 An emer-gency condition has been declared at San Onofre Nuclear Generating i

Station, Units 2 & 3.

3.2 Initial assessments and dose projections have been made which indicate the need for offsite protective actions.

4.0 PRECAUTIONS 4.1 Initiation of protective actions for cffsite areas is the responsibility of the State of California.

4.2 The Emergency Coordinator will make recomendations for protective actions as advised by the Health Physics Leader only after review of Attachment 8.1 " Basis For Protective Action Recommendations".

4.3 If immediate protective actions are required, and the state authorities are unable to respond in a timely manner, recommendations will be made directly to the local authorities.

O 5.0 CaECx-0 a lSTS 5.1 Offsite Protective Action Recommendation Checklist

O \_/ SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-26 UNITS 2 & 3 REVISION NEW PAGE 2 6.0 PROCEDURE (Cont'd) 6.1 Obtain projected dose data generated by procedure 5023-VIII-23 " Dose Assessments".

s.2 Using meteorological data, determine the plume direction and wind speed. Evaluate the potential for wind direction. shifting.

6.3 Evaluate plant condition parameters to approximate the duration of the release; or if the release has not started, how long until the release does start and what will be the duration of the release.

6.4 Using the data obtained in Steps 6.1 through 6.3, determine the appro-priate protective action recommendations utilizing Attachments 8.3, 8.4 and 8.5.

6.5 Attachments P.6 and 8.7 may be used to determine the effectiveness of r.hel teri ng.

6.6 Determine the affected area.

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(_ NOTE: Do not delay recommending protective actions while waiting for offsite monitoring team results.

(

6.7 Advise the Emergency Coordinator to make the recommendations for appropriate offsite protective action to County authorities as fol-lows:

6.7.1 Identify the affected area (s) by radius. (Forexample:

" Evacuate within a 5 mile radius, seek shelter beyond 5 miles" . )

6.7.2 If the wind variability permits, use sector numbers. (For example: " Evacuate within a 5 mile radius and in sectors C and D to 10 miles. Seek shelter in all other sectors to 10 miles" . )

6.8 If, as a result of continuing assessment, dose projection results or meteorological conditions change significantly, re-evaluate the recom-mended protection action and, if necessary, update the initial recom-mendation.

7.0 RECORDS After review, data sheets will be transmitted to the Administrative Leader.

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O V SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-26 UNITS 2 & 3 REVISION NEW PAGE 3 8.0 ATTACHMENTS 8.1 Basis for Protective Action Recomendations 8.2 Offsite Protective Action Recomendation Checklist 8.3 Recomended Protective Action to Avoid Whole Body and Thyroid Dose f.om Exposure to a Gaseous Plume 8.4 Guidelines for Protection Against Ingestion of Contamination 8.5 Recomended Protective Actions 8.6 Representative Shielding Factors From Gama Cloud Source 8.7 Representative Shielding Factors for Surface Deposited Radionuclides o(

A K. P. BARR 4

HEALTH PHYSICS MANAGER l -

JSD:emb -

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EMERGENCY PROCEDURE S023-VIII-26

.OV SAN ONOFRE NUCLEAR GENERATING STATION UN:TS 2 & 3 REVISION NEW ATTACHMENT 8.I PAGE 1 0F 2 BASIS FOR PROTECTION ACTION RECOMMENDATIONS A. PROTECTIVE ACTION GUIDES Protective actions are measures taken to avoid or reduce the projected dose when the benefits derived form such action are sufficient to offset any undesirable features of the protective actions.

The protective actions in this procedure emphasize protective actions for minimizing the exposure of the public to external and internal radiation exposure. Detailed guidance for minimizing public exposure via the in-gestion pathway is also given.

1. No protective action should be recommended for incidents involving actual or potential radioactivity releases which are projected to result in projected whole body or thyroid doses less than about 170 mrem to members of the general public.

2. Sheltering of members of the general public within affected areas should be recommended for incidents involving actual or potential i

radioactivity releases which are projected to result in whole body or p thyroid doses greater than 170 mrem, but less than 1 rem whole body /5 rem thyroid (child).

B. PROTECTIVE ACTION OPTIONS

1. Sheltering Sheltering is a protective action which involves members of the general public taking cover in a building that can be made relatively air tight. Although sheltering, particularly in masonry buildings, will also reduce the exposure of personnel to external radiation as the 1

plume passes, this effect is less significant than the corresponding reduction in internal exposure. Sheltering is an appropriate protec-tive action for:

a. Severe incidents in which an evacuation cannot be implemented because of inadequate lead time ti the rapid passage of the plume

! (" puff" release).

b. When an evacuation is indicated, but local constraints, such as traffic conditions, dictate that directing the public to seek shelter is a more feasible and effective protective measure than evacuation.

c. As a precautionary measure, while a detemination of the need to evacuate is made.

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1 SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-26 ATTACHMENT 8.1

-( ) UNITS 2 & 3 REVISION NEW PAGE 2 0F 2 BASIS FOR PROTECTION ACTION RECOMMENDATIONS

2. Evacuation Evacuation of the population is the most effective protective action.

Traffic conditions may make evacuation an inappropriate measure for:

a. An incident involving a release, or potential release, which is projected to result in an offsite dose greater than 1 rem whole body, and/or 5 rem to the child thyroid, in situations where the lead time between declaration of the emergency and population relocation is compatible with plume involvement.

b. Situations which do not provide for advance warning, but for which substantial reductions in population dose can ba made by avoiding exposure to residual radioactivity (plume fallout) in wake of sudden severe incidents.

C. DESIGNATION OF AFFECTED AREAS

1. The designation of the area requiring protective actions will depend x on several variables, each of which will have to be evaluated at the

( tine of the incident. F.ajor variables, include the nature and extent of the incident, local geography, and existing meteorological conditions.

Generally, the affected area will resemble a keyhole consisting of a circle with a 90* (or larger) wedge shaped sector attached in the downwind direction,

2. Affected areas will be defined by SCE personnel on the bacis of circles or various diameters, and if wind patterns permit, particular sectors beyond the initial circle.

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SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-26 1( ) UNITS 2 & 3 REVISION NEW ATTACHMENT 8.2 PAGE 1 0F 2 0FFSITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST FOR LIQUID RELEASE:

Release activity: ;

1. Release volume:

Offsite Dose Assessment:

HPL Initials Time Date

2. Communicated release information to Emergency Coordinator HPL Initials Time Date FOR GASE0US/ AIRBORNE RELEASES

1. Results of Offsite Dose Projection:

O<.

HPL Initials Time Date Windspeed mph.

2. Plume direction: .

Prognosis for wind direction shifting:

HPL Initials Time Date

3. Duration (estimate if necessary of release):

HPL Initials Time Date O .

J SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-26 O UNITS 2 & 3 REVISION NEW ATTACHMENT 8.2 PAGE 2 0F 2 0FFSITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST

4. Protection action (s) recomended:

s HPL Initials Time Date Completed:

Health Physics Leader Time Date

, 5. Affected area (s):

HPL Initials Time Date 1

6. Protective action recommendations reviewed and comunicated to County Authorities.

(

HPl. Initials Tinie Date

7. Re-evaluation of data:

Protective Actions recomended:

HPL Initials Time Date O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-26 h

UNITS 2 & 3 REVISION NEW ATTACHMENT 8.3 PAGE 1 0F 1 RECOMMENDED PROTECTIVE ACTIONS TO AVOID WHOLE BODY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME Projected Dose (Rem) to Recommendations The Population Actions Coments Whole Body < 1 No planned protection actions. Previously recommended Issue an advi.sory to seek protective actions may Thyroid < 5 shelter and await' further in- be reconsidered or structions. teminated.

Monitor environmental radiation levels.

Whole Body 1 to < 5 Seek shelter as minimum. If constraints exists, Consider evacuation. Evacuate special consideration unless constraints make it should be given for impractical . evacuation of children Thyroid 5 to < 25 _

Monitor environmental radiation and pregnant women.

i; levels.

4 Control access.

Whole Body 5 and above Conduct mandatory evacuation. ' Seeking shelter would

( Monitor environmental radiation be an alternative if levels and adjust area for man- evacuation were not datory evacuation based on immediately possible.

Thyroid 25 and above these levels.

Control access.

Projected Dose (Rem) To Emergency Workers Whole Body 25 Control exposure of emergency Although respirators team members to these levels and thyroid prophy-Thyroid 125 except for lifesaving missions. laxis should be used (Appropriate controls include where effective to time limitations, respirators control dose to emer-and thyroid prophylaxis.) gency workers, Thyroid Whole Body 75 Control exposure of emergency dose should not be the team members perfoming a limiting factor for lifesaving mission to this lifesaving missions.

level. (Control of time exposure will be most effec-tive.)

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SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-26 UNITS 2 & 3 REVISION NEW ATTACHMENT 8.4 PAGE 1 0F 2 GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION +

I. Ground Contamination A. Action Levels

1. Projected whole body dose above the ground 1 Rem.

2. Ground Contamination Levels 200 pCi/m 2 at t = 1 hr. post-accident.

3. Exposure rate 12 mrem /hr at 1 meter above ground at t = 1 hr post-accident.

B. Reconinended Protective Actions

1. Evacuation of affected areas.

2. Restriction of entry to contaminated offsite areas until radiation level has decreased to State appitved levels.

II. Food and Water Contamination A. Action Levels contamination in Total Intake Milk or Water via al' Pasture (0.5 Rem WB or Bone: (5 Rem WB or Bone: Food & Water Grass 1.5 Rem Thyroid) 15 Rem Thyroid) Pathways (Fresh Weight)

Preventive Level Emergency Level Preventive Emergency Preventive Emergency (pCi/1) (pC1/1) (pC1) (pCi) (pCi/kg) (pCi/kg)

Nuclide*

I-131 (Thyroid) 0.012 0.12 0.09 0.9 0.27 2.7 Cs-137 (Whole 0.34 3.4 7 70 3.5 35 Body)

Sr-90 (Bone) 0.007 0.008 0.02 0.2 , 0.7 7 Sr-89 '

(Bone) 0.13 1.3 2.6 26 13 130

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EMERGENCY PROCEDURE S023-VIII-26 SAN ON0FRE NUCLEAR GENERATING STATION ATTACHMENT 8.4 REVISION NEW UNITS 2 & 3 PAGE 2 0F 2 GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION

II. Food and Water Contamination (Cont'd) -

B. Reconnended Protective Actions Emergency Preventive

1. Removal of lactating dairy cows from contaminated Isolate food and water from its introduction into pasture and substitution of uncontaminated stored commerce after considering:

feed. availability of other possible actions; a.

2. Substitute source of uncontaminated water,

b. importance of particular food in nutrition;

3. Withhold contaminated milk from market to allow radioactive decay. c. time and effort to take action;

4. Divert fluid milk to production of dry whole milk, d. availability of other foods.

butter, etc.

If other nuclides are present, Regulatory Guide 1.109 should be used to calculate the dose to the critical organ (s).

Infants are critical segment of the population.

References:

U.S. Food and Drug Administration, Federal Register, Volume 43, No. 242, December 15, 1978.

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! '( ) SAN ON0FRE NUCLEAR GENERATING STATION UNITS 2 & 3 EMERGENCY PROCEDURE S023-VIII-26 REVISION NEW ATTACHMENT 8.5 PAGE 1 0F 2 RECOMMENDED PROTECTIVE ACTIONS ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE RECOMMENDED EMERGENCY Inhalation of Evacuation, shelter, access control, PHASE 1 gases, radio- respiratory protection, prophylaxis (0.5 to 24 hrs)* iodine, or (thyroid protection).

particulate I

Direct whole Evacuation, shelter, access control body exposure

! Ingestion of Take cows off pasture, prevent cows from milk drinking surface water, discard contaminated milk, or divert to stored products, such as cheese.

( INTERMEDIATE Ingestion of Wash all produce, or impound produce, delay harvest until approve substitute uncontamin-PHASE 2 fruits and ated produce.

Ingestion of Cut off contaminated supplies, substitute water from other sources, filter, demineralize.

(24 Hrs to Whole body Relocation, decontamination, access control.

30 days)* exposure and inhalation i

1 Emergency Phase - Time period of major release and subsequent plume exposure.

2 Intermediate Phase - Time period of moderate continuous release with plume exposure and contamination of enviroment.

" Typical" Post-Accident time periods l'

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EMERGENCY PROCEDURE S023-VIII-26 O SAN ON0FRE NUCLEAR GENERATING STATION ATTACHMENT 8.5

\J UNITS 2 & 3 REVISION NEW PAGE 2 0F 2 RECOMMENDED PROTECTIVE ACTIONS ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE REC 0 MENDED i

Ingestion of Ncontamination, condemnation, or destruc-food and water tion of food; deep plowing, condemnation contaminated or alterate use of land.

4 LONG TERM from the soil PHASE 3 either by resus-pension or uptake through roots.

Whole body expo- Relocation, access control, decontamination, sure from deposi- fixing of contamination, deep plowing.

(Over 30 days)* tion material or inhalation of resuspended material

(

3 Long Term Phase - Recovery period

" Typical" Post-Accident time periods J

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,e SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-26

( UNITS 2 & 3 REVISION NEW ATTACHMENT 8.6 PAGE 1 0F 1

~

REPRESENTATIVE SHIELDING FACTORS FROM GAMMA CLOUD SOURCE Shielding Structure or Location Factor (a) Representative Range Outside 1.0 --

Vehicles 1.0 --

Wood-Frame House (b) 0. 9 --

(No Basement)

Basement of Wood House 0.6 0.1 to 0.7 (c)

Masonry Housa (No Basement) 0.6 0.4 to 0.7 (c) ;

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Basement of Masonry House 0.4 0.1 to 0.5 (c) l Large Office or Industrial Building 0.2 0.1 to 0.3 (cad)

(a) The ratio of the dose received inside the structure to the dose that would be received outside the structure.

I O (b) A wood frame house with brick or stone veneer is approximately equivalent to a

( masonry house for shielding purposes.

(c) This range is mainly due to different wall materials and different geometries.

(d) The shielding factor depends on where the personnel are located within the building (e.g., the basement or an inside room).

SELECTED SHIELDING FACTORS FOR AIRBORNE RADIONUCLIDES Wood House, no basement 0.9 Wood House, basement 0.6 Brick House, no basement 0.6 Brick House, basement 0.4 Large Office or Industrial Buidling 0.2 Outside 1.0

Taken frpm SAND 77-1725 (Unlimited Release)

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EMERGENCY PROCEDURE S023-VIII-26

-]- SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 REVISION NEW ATTACHMENT 8.7 PAGE 1 0F 1 REPRESENTATIVE SHIELDING FACTORS FOR SURFACE DEPOSITED RADIONUCLIDES REPRESENTATIVE REPRESENTATIVE STRUCTURE OR LOCATION SHIELDING FACTOR (a) RANGE 1 m above an infinite smooth surface 1.00 --

1 m above ordinary ground 0.70 0.47 - 0.85 1 m above center of 50ft roadways, 0.55 0.4 - 0.6 50% decontaminated Cars on 50ft road:

Road fully contaminated 0.5 0.4 - 0.7 Road 50% decontaminated 0.5 0.4 - 0.6 Road fully decontaminated 0.25 0.2 - 0.5 Trains 0.40 0.3 - 0.5 One and two-story wood-frame house 0.4 0.2 - 0.5 (no basement)

One and two-story block & brick house 0.2(b) , 0.04 - 0.40

( (no basement)

House basement, one/two walls fully exposed 0.1(b) 0.03 - 0.15 One story, less than 2ft of basement, walls exposed 0.5(b) 0.03 - 0.07 Two stories, less than 2ft of basement, walls exposed 0.03(b) 0.02 - 0.05 Three/four-story structures, 5000 to 10,000 f t2 per floor:

l First and second floors: 0.05(b) 0.01 - 0.08 Basement 0.01(b) 0.001 - 0.07 Multi-story structures,10,000 sq. f t per floor:

Upper floors 0.01(b) 0.001 - 0.02 Basement 0.005(b) 0.001 - 0.015 (a) The ratio of dose received inside the structure to the dose that would be received outside the structure.

(b) Away from doors and windows.

Taken from SAND 77-1725 (Unlimited Release)

0 EMERGENCY PROCEDURE S023-VIII-27 SAN ONOFRE 14UCLEAR GENERATING STATION 91981 ~ Page 1 NEW SEP UNITS 2 AND 3 o

V EMERGENCY ENVIRONMENTAL MONI RIN 1.0 OBJECTIVE l'

i" F"g

' [ "*" -; ghT*si!

gr { -

[

This procedure provides guidance s97 a of offsite environmental monitoring r8g The Health Physics Leader is responsible N

of this procedure. 's gg l

.j

2.0 REFERENCES

/

OF 2.1 San Onofre Nuclear Generating Stttion, Units 2 and 3 Emergency Plan 2.2 SONGS, Units 2 and 3 Environmental Procedure, S-IX-I.1, -

Environmental Sample Collection.

2.3 SONGS, Units 2 and 3 Environmental Procedure S-IX-1.2, Air Samples 2.4 SONGS, Units 2 and 3 Environmental Procedure S-IX-1.4, Drinking Water 2.5 SONGS, Units 2 and 3 Environmental Procedure S-IX-1.5, Beach Sand 2.6 SONGS, Units 2 and 3 Environmental Procedure S-IX-1.6, Local Crops

~.) SONGS, Units 2 and 3 Environmental Procedure S-IX-1.8, Soil 2.7

( Samples 3.0 PREREQUISITES 3.1 An emergency condition has been declared at San Onofre Generating Station, Units 2 and 3.

3.2 The Emergency Coordinator has requested emergency environmental monitoring.

4.0 PRECAUTIONS 4.I Monitoring terams should be reminded to monitor their own exposures, and request relief if their cumulative exposure approaches an administrative limit. The Emergency Coordinator may authorize emergency exposure extensions in accordance with Emergency Procedure 5023-VIII-31, " EMERGENCY EXPOSURE CONTROL" 4.2 Ensure that all communication related to reporting monitoring data are brief and factual.

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. 1 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-27 UNITS 2 AND 3 NEW Page 1 of 2

^TT^cass"T 8 2

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INSTRUCTIONS FOR EMERGENCY ENVIRONMENTAL MONITORING TEAMS 1.0 Report to Health Physics Leader (HPL) for briefing.

2.0 When instructed as to the type of samples to be obtained review the appropriate environmental procedure. These are listed below with a j

short explanation.

S-IX-1.1 " ENVIRONMENTAL SAMPLE COLLECTION" Gives directions j ,

for all kinds of sampling, includes necessary equipment and directions to TLD locations.

S-IX-1.2 " AIR SAMPLES" Gives directions for taking environmental air samples and the locations of samplers.

S-IX-1.4 " DRINKING WATER" Gives directions for taking drinking water samples and the normal locations.

S-IX-1.5 " BEACH SAND" Gives directions for beach sand sampling.

S-IX-1.6 " LOCAL CROPS" Gives directions for taking local crop

samples and the normal locations. Samples from other location may be necessary.

( S-IX-1.8 "SblLSAMPLES" Gives directions for taking soil samples.

3.0 Obtain the appropriate sampling equipment from normal supply locations.

l 4 4.0 Cbtain a Walkie-Talkie and check operation before leaving the station.

Keep the radio operational at all times while offsite in order to maintain communications with the HPL.

5.0 Obtain and re-zero dosimeters if the HPL deems them necessary. Don Protective clothing and/or respirators only if directed by the HPL.

Such protective measures would be necessary only if a significant airborne release has occurred.

6.0 Obtain an SCE vehicle, if available. Otherwise, use any available privattiy owned vehicle. Note gas tank level. Ensure that there is at least one-half tank of gas. Obtain another vehicle if necessary.

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EMERGENr.y PROCEDURE 5023-VIII-27 SAN ONOFRE NUCLEAR GENERATING STATION NEW Page 2 UNITS 2 AND 3 4.0 PRECAUTIONS (continued) 4.3 Ensure that instructions and data transmissions are carefully worded and understood.

4.3.1 Avoid abbreviations, use the complete word or unit.

4.3.2 Clearly identify survey locations, using predetermined survey locations, map coordinates, equipment and building names, as available.

5.0 CHECK-OFF LISTS 5.1 Environmental Monitoring Checklist 6.0 PROCEDURG 6.1 Discussion 6.1.1 The extent and degree of environmental monitoring following a release of radioactive material will depend on the nature, the severity, the physical / chemical form and the radioisotopic composition of the release. The Hegith Physics Leader, (or in his absence the Emergency Coordinator), will determine the need for and extent O. of post-accident enviromental monitoring.

(

6.1.2 Sufficient health physics personnel will be available to support several monitoring teams for releases which occur during normal working hours. During other times, it may only be possible to deploy immediately one monitoring team. In these circumstances the Health Physics Leader will assign priorities for monitoring based on the known or projected radiological conditions, while calling in additional personnel. Nonna11y, radiological monitoring will have priority over environmental monitoring.

6.1.3 Environmental monitoring can effectively document integrated gamma exposure and/or iodine concentration of specific locations. The capablility is limited by the number and location of established monitoring points. Additionally, environmental monitoring can be used to assess contamination levels in sofi, drinking water and feed or food crops.

6.1.4 Normally environmental monitoring would not be implemented immediately after declaration of an ,

emergency. Rather, it should be implemented after the termination of a radioactive release or O '

periodically during a prolonged low level release.

This being the case, monitoring teams dispatched for l

environmental monitoring should include one individual cognizant of environmental procedures.

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1 EMERGENCY PROCEDURE S023-VIII-27 SAN ONOFRE NUCLEM GENERATING STATION NEW Page 3 UNITS 2 AND 3 7

6.0 PkOCEDURE (continued) 6.2 General Instruction for Offsite Monitoring 6.2.1 Emergency enviror.v. ental monitoring.

.1 For Alert (when a radioactivety release is involved) or Site Emergency Conditions, one set of gamma dosimenters should be exchanged for each location upon termination of the emergency condition.

.2 For a General Emergency condition one set may be exchanged during the emergency conditions but shc,uld not be exchanged during any known release period.

Consideration for exchanging the dostmeters would include:

a) Taking parallel actions with the state and NRC as deemed necessary.

b) Providing interim data as to long term effects of the casulty on the environment.

c) Providing additional data as to the extent of the release plume.

I .3 The second set of dosimeters should not be exchanged, except at the normal annual exchange frequency.

.4 When exchanging dosimeters ensure that an adequate supply of replacement dosimeters is available. These may be requested from the contractor laboratory.

1

.5 Other environmental monitoring samples may be obtained as appropriate. These include; Drinking Water, Local Crops, soil samples and sand samples.

These samples would be useful to assess environmental contamination levels.

6.2.2 Use available information (meterorological information, effluent monitors, radiation monitors, etc.) to define sector (s) or area (s) to be monitored 6.2.3 Asssemble monitoring team (s). Ensure that at least one member of each team is cognizant of normal environmental procedures.

6.2.4 Brief monitoring team on monitoring locations to be sampled; the samples to be taken; radiological conditions; precautions to be observed; and protective clothing or equipment a:, neccessary. ,

6.2.5 Ensure that the environmental monitoring team has Attachment 8.2 of this procedure and any reference environmental procedures which cover the sampling to be performed.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-27 NEW Page 4 UNITS 2 AND 3 r

D) (continued) 6.0 PROCEDURE 6.2 (continued) 6.2.6 Dispatch monitoring teams (s) maintaining radio contact.

6.2.7 Determine the most convienent airitne service to the Oakland Airport. This may be from San Di:go, Orange County or Los Angeles. Make arrangements for air freight of environmental samples.

6.2.8 Contact EAL Corporation and arrange for emergency environmental monitoring analysis services.

NOTE: EAL CORPORATION 2030 Wright Av.

RICHMOND, CA. 94804 (415) 235-2633 Inform EAL of the Airline flights which will be used to transport samples to them.

6.2.D Normally qualitative results of sample analysis will be telephoned from EAL within a few hours of receipt. Quantitative formalized results will be

( s) available within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reciept, with the

('

teception that leafy vegetable analysis results take 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Evaluate analysis results and advise the Emergency Coordinator of the results.

6.2.10 Implement Emergency Procedure 5023-VIII-26,

RECOMMENDATIONS FOR OFFSITE PROTECTIVE MEASURES". if appropriate.

6.2.11 Upon receipt of formalized analysis results - review ;

and submit to the Administrative Leader for filing.

7.0 RECORDS 7.1 Forward the results of all emergency environmental monitoring sample analyses to the Administrative Leader.

OA ATTACHMENTS 8.1 Emergency Environmental Monitoring Checklist 8.2 Instruction for Emergency En ronmental Monitoring Teams.

K. P. BARR

() HEALTH PHYSICS MANAGER DM:0101F/sss i l

s EMERGENCY PROCEDURE 5023-VIII-27 SAN ONOFRE NUCLEAR GENERATING STATION NEW Page 1 of 1 UNITS 2 AND 3 ATTACHMENT 8.1

[)

EMERGENCY ENVIRONMENTAL MONITORING CHECKLIST

1. Environmental monitoring to be performed at the following locations:

Time Date HPL Inittais--

2. Environmental Monitoring Team briefed and dispatched.

HPL Initials Time Date

3. Environmental Monitoring Team recalled.

HPL Initials Time Date

4. Summary of Environmental Monitoring qualitative analysis results:

N

)

Reported to Emergency Coordinator HPL Initials Time Date

5. Procedure Implemented:

Time Date HPL Initials

6. bummary of Formalized data:

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SAN ONOFRE NUCLEAR GENERATING. STATION EMERGENCY PROCEDURE 5023-VIII-27 UNITS 2 AND 3 NEW Page 2 of 2 ATTACHMENT 8.2' 1()

7.0 Proceed to the assigned sampling locations and obtain samples in accordance with existing environmental monitoring procedures.

8.0 If it is necessary to enter private or military property, identify yourself as Southern California Edison Employees with SCE identification card, and briefly and courteously explain the reason for the special sampling.

9.0 Continue collecting samples until all of the samples have been collected or as directed by the HPL, then return to the station for further instructions.

DATE ENVIRONMENTAL MONITORING TEAM LEADER O<

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-31 REV NEW PAGE 1 UNITS 2 & 3

'C 0E EMERGENCY EXPOSURE C JTROL g

1.0 OBJECTIVE ! f This procedure provides guidance and crite f of personnel exposure to radiation in excess of r g '

y \

limits during an emergency. The Emergency Coordinator approve emergency exposure authorizations. Assigned Hea technicians are responsible for implementation of this proce j[8g Health Physics leader is responsible for reviewing all aspects o n gency exposure authorization and post exposure evaluation. gg

2.0 REFERENCES

OCT 109@

2.1 10 CFR 20, Standards for Protection Against Radiation COM bII ~

2.2 ICRP Publication 28, The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers 2.3 EPA-520/1-75-001, Manual of Protective Action Guides and Protective

)

Acticns for Nuclear Incidents 2.4 NUREG-0654, Rev.1 Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 3.0 PREREQUISITES 3.1 An emergency condition at San Onufe Nuclear Generating Station has resulted in radiation levels within the plant, in excess of nonnal levels, and special considerations are required for exposure control.

3.2 The provisions of this procedure are applic-ble only in actual emer-gency situations, and are applicable only to SONGS-2 & 3 emergency '

organization personnel perfonning assigned emergency functions.

3.3 The radiation exposure to emergency personnel shall be maintained as low as reasonably achievable and should be maintained within the SONGS-2 & 3 administrative exposure guides and/or less than the radiation exposure limits in 10 CFR 20, if practical. _

3,4 To maintain personnel exposures within established guides and limits, administrative methods used during normal operatior.s to control and minimize exposures, such as exposure clearances and ALARA measures, should remain in force during an emergency condition to the degree consistent with timely implementation of emergency measures.

3.5 To the degree possible, the probability of success of the proposed action requiring emergency exposure shall be weighed against the projected element of risk.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-31 PAGE 2

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( UNITS 2 & 3 REVISION NEW

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3.0 PREREQUISITES (Cont'd) 3.6 The Emergency Coordinator may approve personnel exposures in excess of nonnal guides and limits but less than the planned radiaticn exposure criteria established in this procedure if the prerequisites for re-ceiving such exposure are satisfied.

3.7 The Emergency Coordinator is the only individual authorized to permit emergency exposures.

4.0 PRECAUTIONS 4.1 Emergency exposures should be limited to one occurrence in a lifetime.

4.2 Personnel shall not be permitted to enter any area where dose rates are unknown.

4.3 Dosimetry equipment capable of measuring the anticipated maximum exposure and type of radiation (s) shall be worn by personnel receiving emergency exposure.

4.4 Extremity dosimeters shel, be worn if the anticipeted extremity exposure O( is greater than about 5 times the whole body exposure.

4.5 Reasonable measures shall be taken to minimize skin contamination and the ingestion of radioactive materials.

4.6 Personnel receiving exposures which may or will exceed 10 CFR 20 limits shall be volunteers.

4.7 Women of child-bearing age and capability shall not be permitted to ret.eive exposures which exceed 10 CFR 20 limits.

4.8 Volunteers should be more than 45 years of age, if possible.

4.9 All volunteers shall be briefed on potential biological consequences prior to receiving such exposure.

5.0 CHECK-0FF LISTS Not Applicable ,

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-31 REVISION NEW PAGE 3 ig UNITS 2 & 3 I 6.0 PROCEDURE 6.1 Emergency Exposure Documentation NOTE: The following actions shall be perfomed to docu-ment emergency radiation exposure. Although it is preferable to perform these steps before the exposure is received, the Emergency Coordinator may, at his discretion, verbally authorize the emergency exposure with documentation to be com-pleted at a later time. Any emergency exposures authorized shall be in accordance with the guid-ance of Attachment 8.1.

6.1.1 Have the individual who will receive the emergency exposure complete Section A of the Emergency Exposure Authorization Fom items I through 5 (See Attachment 8.2).

6.1.2 Complete items 6 and 7 of Section A and submit the form to the Health Physics Leader for review and endorsement.

6.1.3 Prior to entry into the affected area, the individual shall be briefed on the radiological conditions and other condi-(v'() tions known or expected to exist in the area; the task (s) to be performed; ALARA measures applicable to the task (s);

and, any contingency measures.

NOTE: The Heelth Physics Group shall ensure that emergency workers monitor their exposures during the perfomance of their tasks, using their dosimeters.

6.1.4 Have the individual who will receive the emergency exposure complete Section B of the fom. Attachment 8.3 contains the infomation on Effects of Acute Exposures.

6.1.5 Submit the fom to the Emergency Coordinator for approval.

6.1.6 Following the exposure, complete Section C of the fom.

6.1.7 Submit the fom to the Dosimetry Supervisor who shall com-plete Section D of the form.

6.1.8 The Health Physics Leader shall review all doucmentation of emergency exposures before forwarding to the Administrative Leader.

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f EMERGENCY PROCEDURE S023-VIII-31 A SAN ONOFRE NUCLEAR GENERATING STATION PAGE 4

, V REVISIOF NEW UNITS 2 & 3 r

6.0 PROCEDURE __ (Cont'd) 6.2 Post-Exposure Evaluations E 2.1 Individuals receiving emergency exposures shall be restricted from further occupational radiation exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance.

6.2.2 An exposure evaluation shall be perfomed to detemine a dose equivalent for the emergency exposure. This evaluation shall be based on measured area dose rates, airborne radio-activity measurements and dosimetry results.

NOTE: Record exposure devices shall be processed, either by the onsite dosimetry system or by the dosimetry vendor, following any emergency exposure.

6.2.3 If an individual's dose equivalent exceeds 10 rem for the whole body, 60 rem for the skin and/or 150 rem for an ex-tremity (two times the annual dose equivalent limits), the J

O. details of the exposure shall be brought to the attention

( of a physician who shall determine the need for, extent of I

and nature of any clinical, biological or biochemical examin-ations.

6.2.4 If an individual's dose equivalent exceeds 25 rem for the whole body,150 rem for the skin and/or 375 rem for an extremity (5 times the annual dose equivalent limits), the individual shall be examined by a physician. The physician shall determine the need for, extent of and nature of any clinical, biological or biochemical examinations and any necessary medical surveillance.

NOTE: The dose equivalent is equal to the total risk to the organ of interest, be it from internal exposure, external exposure or both.

7.0 RECORDS 7.1 Completed Attachment 8.2 7.2 Dosimetry records. ;

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] SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-31 UNITS 2 & 3 REVISION NEW PAGE 5

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4 8.0 ATTACHMENTS f

8.1 Emergency Exposure Guidelines 8.2 Emergency Exposure Authorization Fom

.i

8.3 Effects of Acute Exposures

! K. P. BARR

! HEALTH PHYSICS MANAGER l

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-31 REVISION NEW ATTACHMENT 8.1 b'~N liNITS 2 & 3 -

PAGE 1 0F 1

(* EMERGENCY EXPOSURE GUIDELINES Lifesaving / Protection Emergency Of Public Health And (Non-Lifesaving)

Safety Activities Activities Whole Body Thyroid Whole Body Thyroid Dose (Rem) Dose (Rem) Dose (Rem) Dose (Rem)

Undertaking Corrective

125 75 25 Actions Perfonning Assessment -- 25 125 Actions

25 125 Providing First Aid 75 Perfonning Personnel ** 15

- 3 Decontamination

( Providing Ambulance ** ** 15 3

Services Providing Medical ** ** 15 3

Treatment Perfonning Search and

125 75 25 Rescue Operations 75

25 125 Removal of Injured Persons

-- 25 125 Recovery of Dead --

No specific upper limit is given for thyroid exposure since in the extreme case complete thyroid lost might be an acceptable penalty for a life saved.

However, this should not be. necessary as respirators and/or thyroid pro-tection for the rescue personnel are available.

q ** It is unlikely that lifsaving guidelines will be necessary if exposures are maintained as low as practicable; however, should they be necessary, guide-

'v lines shall be consistent with other " Lifesaving / Protection of Public Health and. Safety Activities".

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-31 f- REVISION NEW ATTACHMENT 8.2

\ UNITS 2 & 3 PAGE 1 0F 3 EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION A

1. Name of Individual to Receive Exposure:

2. Social Security No.:

3. Film or TLD Badge No.:

4. Employer /SCE Department:

S. Date of Authorization:

6. Authorized Exposure Limit:

7. Conditions:

Individual is a volunteer or professional rescue person.

Individual is broadly familiar with radiological consequences n of exposure.

()

( Woman capable of reproduction has been advised not to take part (Reg. Guide 8.13).

Individual has not received an emergency exposure before.

Dose rates in area known/ measurable.

Undertaking corrective actions.

Performing assessment actions.

Providing first aid.

Performing personnel decontamination.

Providing ambulance services.

Providing medical treatment.

Performing search and rescue operations.

Removal of injured persons.

oete:

O Heeith enysics teeder:

(Signature)

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d SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-31 REVISION NEW ATTACHMENT 8.2 UNITS 2 & 3 PAGE 2 0F 3 EMERGENCY EXPOSURE ' AUTHORIZATION FORM SECTION B I have volunteered to perform the task (s) during which I will receive the emergency exposure and I have been briefed on the potential biological consequences of the proposc-d emergency exposure.

Individual to Receive Exposure: Date:

(Signature)

Date:

Approved By:

Emergency Coordinator lO ( SECTION C (Attach exposure evaluation)

Film or TLD Badge / Direct-Reading Dosimeter Results:

Bioassay Results:

Medical Evaluation / Action:

Dose Equivalent Assigned to Individual:

Date:

Health Physics:

(Signature)

4 EMERGENCY PROCEDURE S023-VIII-31 t[]' SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 REVISION NEW ATTACHMENT 8.2 PAGE 3 0F 3 p.

EMERGENCY EXPOSURE AUTHORIZATION FORM l

j' SECTION D I

Disposition (Allow additional exposure, restrict access, etc.):

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, Dosimetry Supervisor: Date:

(Signature) i i

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4 O SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-31 O UNITS 2 & 3 REVISION NEW ATTACHMENT 8.3 PAGE 1 0F 1

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EFFECTS OF ACUTE EXPOSURES Acute Dose (Rem) Probable Effect 0-50 No obvious effect, except possibly minor blood changes.80-120 Vomiting and nausea for about I day in 5 to 10 percent of exposed personnel.

Fatique but no serious disability.

130-170 Vomiting and nausea for about I day, followed by other symptoms of radiation sickness in about 25 per:ent of personnel.

No deaths anticipated.

180-220 Vomiting and nausea for about I day, fol-lowed by other symptoms of radiation sick-ness in about 50 percent of personnel.

Rarely death may occur.

270-330 Vomiting and nausea in nearly all personnel on first day, followed by other symptoms of

(' ' radiation sickness. About 20 percent deaths

( with 2 to 6 weeks after exposure; survivors convalescent for about 3 months.

400-500 Vomiting and nausea in all personnel on first day, followed by other symptoms of radiation sickness. About 50 percent deaths within 1 month; survivors convalescent for about 6 months.

550-750 Vomiting and nausea in all personnel within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from exposure, followed by other symptoms of radiation sickness. Up to 100 percent deaths; few survivors convalescent for about 6 nonths.

1000 Vomiting and nausea in all personnel within 1 or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Probably no survivors from radiation sickness.

5000 Incapacitation almost immediately. All per-sonnel wil1 be fatalities within 1 week.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-32 REVISION 1 Page 1 UNIT 2 AND 3 O OCT 9 1981 O

LOCAL AREA EVACUATION Ac w nHNTABILITY O

1.0 OBJECTIVE O CONSTW @ p r 1.1 This procedure provides inst uct$$[ $8fn0Nty 18 emergencyevacuationofloca@{g:. 0 within SONGS Unit 2and 3. T!.e _ 1 procedure may also be applied, as appropria'ttt t6 g g" : A OMO74 TION related to other hazards affecting habitability, such as h '

toxic gas, or chemical hazards. The Emergency Coordinator is responsible for implement t o } ,of 1.hi s p,ro,cedur,A. etrREC64vcn m eh f.a. j k 4 cd \ ' i

2.0 REFERENCES

L geu J te LIbbCT14jfm 2.1 San Onofre Nuclear Generating Station Unit 2 and 3. EmergSMM SITE Plan 2.2 Emergency Procedure 5023-VIII-11, " RECOGNITION AND CLASSIFICATION OF EMERGENCIES" 2.3 Emergency Procedure 5023-VIII-33, " PLANT EVACUATION AND ACCOUNTABILITY."

2.4 Emergency Procedure 5023-VIII-34, " SITE EVACUATION AND ACCOUNTABILITY."

( 2.5 Emergency Procedure S023-VIII-61, "RE-ENTRY" '

3.0 PREREQU13ITES 3.1 Hi alarm (s) on any Area Radiation Monitoring System (ARMS) Alarm, or:

3.2 A building or containment ventilation monitor (s) indicates airborne activity in excess fo 10MPC, or:

3.3 Alarm on portable radiation monitors and/or continuous air monitors (CAMS), or:

3.4 Localized spills of sufficient magnitude to result in personnel exposure, or:

3.5 Radiation dose rates, radioiodine concentrations, and associated permissible occupancy times in excess of those in " Criteria for Mandatory Evacuations "(Attachment 8.1) in localized areas (e.g.: containment, localized areas of buildings, etc.) of the plant, or:

3.6 Fire in any occupied area, or:

3.7 Toxic or flammable gases or heavy smoke observed or reported in O "> re or:

3.8 Chemical hazards to personnel in any area.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-32 UNIT 2 AND 3 REVISION 1 Page 2 o

V 4.0 PRECAUTIONS 4.1 Evacuation of the Control Room should only be implemented in the event of:

4.1.1 Uncontrolled fire in the Control Room.

4.1.2 Heavy smoke or toxic or flammable gases in the Control Room.

l 4.1.3 Radiation dose rates, radioiodine concentrations, and associated permissible occupancy times exceed those in " Criteria for Mandatory Evacuations" (Attachment 8.1).

i NOTE: Evacuation of the Control Room should only be implemented after respiratory protective equipment and other protective measures prove inadequate.

4.2 Local Area Evacuations are announced over the public address system, indicated by an area radiation or airborne monitor alarm, or initiated by personnel in the affected area in response to observed conditions. No other alarm system shall be used to initiate this type of evacuation.

( 5.0 CHECK-OFF LIST 5.1 Local Area Evacuation Checklist.

6.0 PROCEDURE NOTE: A Local Area Evacuation may be initiated by personnel in the affected area in response to observed conditions, survey instrument indications, or locally-alarming radiation monitors. The procedure steps below assume that the evacuation is initiated by indications / alarms observed in the Control Room.

4 As a result, some steps may not be applicable to all Local Area Evacuations.

6.0 PROCEDURE 6.1 Have the following announcement made over the public address system:

" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: THERE IS A (HIGH RADIATION LEVEL / FIRE /0THER HAZARD-) INDICATED ,

IN . PERSONNEL IN AFFECTED AREAS l (specify Area)

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ev^CuA1E 10 (specify location)

(PR0v10E ANY Aoo1110NAt INSTRUCTIONS NECESSARY.)

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-32 UNIT 2 AND 3 REVISION 1 Page 3 iO 6.0 PROCEDURE 6.1 (continued)

NOTE: Evacuees would normally assemble at the Health Physics Access Control Point (at the entrance to the Radwaste Building.)

6.2 Repeat the announcement two additional times at approximately one

, minute intervals.

6.3 Evaluate alarm (s) or information received with respect to other control room instrument indications.

6.4 Initiate personnel accountability for a Local Area Evacuation as i follows

i NOTE: The number of personnel involvoc in a Local Area j Evacuation is normally small and involves areas which, when occupied, are normally attended by supervising and/or Health Physics personnel.

l 6.4.1 If access to the area is controlled by a manned l Health Physics control point direct Health Physics i personnel to assist personnel in the removal of

protective clothing and/or respiratory protection

! ( equipment and in monitoring in order to facilitate

clearing the affected area. Also direct the Health i Physics Technician (s) to account for all personnel in j the area using Radiation Work Permit records, and j

notify the Control Room when all personnel have been i accounted for and are clear of the affected area.

l 6.4.2 If step 6.4.1 does not apply or proves ineffective, l

contact the supervisor (s) of the work party (ies) to t verify the presence of individuals in the work party (ies).

6.4.3 If individuals are not accounted for, page them over j the public address system. ,

i 6.4.4 If individuals are still unaccounted for, implement

! procedure 5023-VIII-39, " SEARCH AND RESCUE" 6.5 Direct Health Physics to perform radiological surveys in the affected areas to identify the extent, nature, and if possible, the source of the problem. Direct Health Physics personnel to

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perform radiological surveys in the areas in which evacuees are assembled and provide evacuees with assistance.

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4 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-32 UNIT 2 AND 3 REVISION 1 Page 4

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- 6.0 PROCEDURE (continued) 6.6 If the results of radiation surveys at the assembly area indicates radiation levels in excess of 100 mrem /hr or gross airborne radioactivity (less noble gases) in excess of 4E-8pCi/cc, or if continued occupancy is expected to result in excess of 40 MPC-hours for isotopic mix less noble gases; relocate to another Assembly Area, or if necessary, initiate a Plant or Site Evacuation.

6.7 Evaluate the survey results and any changes in plant parameters.

If the survey (s) show that radiation or contamination levels are abnormally high, consider corrective actions, including decontamination.

6.8 Use Procedure 5023-VIII-11. " RECOGNITION AND CLASSIFICATION OF EMERGENCIES", to determine if an emergency event should be declared.

7.0 RECORDS 7.1 Attachment 8.2

] I 8.0 ATTACHMENTS 8.1 Criteria for Mandatory Evacuations 8.2 Local Area Evacuation Checklist.

. wb K. BARR HEALTH PHYSICS MANAGER KB:0072F:jhm i

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-32 UNIT 2 AND 3 REVISION 1 'Page 1 of 1 ATTACHMENT 8.1 l -

CRITERIA FOR MANDATORY ONSITE EVACUATIONS WHOLE BODY IMPLEMENT RADIOI0 DINE DOSE RATE EVACUATION CONCENTRATI0W.

(mrem / hour) WITHIN (y CI/cc) i Up to 600 8 Hours Up to IE-5 600 to 1000 4 Hours IE-5 to 2E-5 1000 to 2500 2 Hours 2E-5 to 4E-5 2500 to 5000 1 Hour 4E-5 to 7E-5 5000 to 10,000 30 min. 7E-5 to IE-4 10,000 to 20,000 15 min. IE-4 to 3E-4

>20,000 IMMEDIATELY >3E-4 Oi'

1. It is impertant to realize that there is ne direct cerreiation set een the whole body dose rates and the radiciodine concentrations; and the measurements or projections of each must be performed independently.

In the event that only a direct radiation determination is available, with no corresponding knowledge of the concentration or fraction of the total which is attributable to radioiodine, the most conservative assumptions specified in the USEPA Manual for Protective Action Guides would be required. Such assumptions, based only on direct radiation determinations, would likely result in gross over-estimation of thyroid dose commitment.

2. Whole body dose to non-emergency personnel should not exceed 5000 mrem from the event. The whole body dose rates specified above are based on 5000 mrem. This value is based on the USEPA PAG Manual specified upper limit for members of the general public. Although this table specifies mandatory evacuation times, in the absence of significant constraints evacuations should be implemented to maintain personnel exposure as low as reasonably achievable and within specified quarterly exposure limits.

3. Maximum concentrations fon specified time corresponds to approximately 25,000 mrem adult thyroid dose commitment. Radioiodine concentration vs. adult thyroid dose commitment based on Appendix D, (January 1979) to USEPA Manual of Protective Action Guides. Radioiodine nuclide distribution corresponds to four (4) hours follwino reactor shutdown.

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SAN ONSFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-32 U' NIT 2 AND 3 REVISION 1 Page 1 of 2

.<- ATTACHMENT 8.2

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LOCAL AREA EVACUATION CHECKLIST (For use with Procedure 5023-VIII-32)

1. Local Area Evacuation Announced:

Emerg Coord. / Watch Supv. Signature Time Date

2. Area (s)

Evacuated:

Reason for evacuation:

Assembly Area:

E.C. / WS INITIAL TIME DATE

3. Accountability Implemented:

O( a. All involved individuals accounted for: ( YES / NO )

b. The following named individuals are unaccounted for (if applicable)

c. " SEARCH & RESCUE" procedure implemented if applicable.

( YES / NO )

E.C. / WS INITIAL TIME DATE

4. Radiation surveyor (s) dispatched E.C. / WS INITIAL TIME DATE O

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-32 UNIT 2 AND 3 REVISION 1 Page 2 of 2 ATTACHMENT 8.2 Cc

5. Summary of affected area radiological status:

E.C. / WS INITIAL TIME DATE

6. Offsite agencies notified: (if applicable)

E.C. / WS INITIAL TIME DATE NOTE: AFTER THIS CHECKLIST IS COMPLETED AND IS NOT REQUIRED FOR IMMEDIATE USE, FORWARD IT TO THE STATION SERVICES MANAGER.

FORWARD TO THE ADMINISTRATIVE LEADER IF EMERGENCY ORGANIZATION IS ACTIVATED.

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SAN ONOFRE NUCLEAR GESU11NG STATION EMERGENCY PROCEDURE S023-VIII-33 UNIT 2 AND 3 _ REVISION 1 Page 1 G DCI gg} fflg PLANT EVACUATION AND A :COUNTABRA#fgygg7,upN ,Q ,

1.0 OBJECTIVE APPll ABLEg[h 1.1 This procedure provides instructions for7mp.rr Ek MA emergency evacuation of non-essential personnel (personhe+w ,%_ TIDS-without an assigned emergency response function) from the SONGS Unit 2 and 3 Plants. The Emergency Coordinator is responsible for implementation of this procedure.

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station, Unit 2 and 3 Emergency Plan.

2.2 Emergency Procedure 5023-VIII-14, " SITE EMERGENCY" 2.3 Emergency Procedure 5023-VIII-11, " RECOGNITION AND CLASSIFICATION OF EMERGENCIES" 2.4 Emergency Procedure 5023-VIII-32, " LOCAL AREA EVACUATION AND ACCOUNTABILITY" 2.5 Emergency Procedure 5023-VIII-34, " SITE EVACUATION AND ACCOUNTABILITY"

( 2.6 Emergency Procedure 5023-VIII-61, "RE-ENTRY"'

3.0 PREREQUISITES Q E" {[ ,((

I

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" ' ~"

3.1 Declared Site Emergency, or:

3.2 Declared Plant Evacuation at Unit 1; 3.3 Valid Hi alarm (s) on two or more Area Radiation Monitoring System (ARMS) Alarms, or:

3.4 Fire, toxic or flammable gases or heavy smoke affecting more than just one room or local area, or:

3.5 High airborne radioactivity levels, as detected by installed monitors or survey, that impact more than one room or local area, or:

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-33 REVISION 1 Page 2 UNIT 2 AND 3

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3.0 PREREQUISITES (continued) 3.6 Radiation dose rates, radioiodine concentrations, and associated permissible occupancy times in excess of those in " Criteria for Mandatory Onsite Evacuations" (Attachment 8.1) in wide areas of the plant.

4.0 PRECAUTIONS 4.1 Evacuation of the Control Room should only be implemented in the event of:

4.1.1 Uncontrollable fire in the Control Roem, or:

4.1.2 Heavy smoke or toxic or flammable cases in the Control Room, or:

4.1.3 Radiation dose rates, radioiodine concentrations, and associated permissible occupancy times exceed those in " Criteria for Mandatory Onsite Evacuations "

(Attachment 8.1)

NOTE: Evacuation of the Control Room should only be implemented after respiratory

() protective equipment and other protective measures prove inade,quate.

4.2 The actual decision to implement a Plant Evacuation is the responsibility of the Emergency Coordinator. The decision should be based upon the Emergency Coordinators evaluation of the magnitude and severity of the situation.

4.3 Accountability must be completed within 30 minutes after Plant Evacuation.

5.0 CHECK-OFF LISTS 5.1 Plant Evacuation Checklist.

6.0 PROCEDORE 6.1 Evaluate information available on initiating event. If additional time or information is needed prior to making the decision to implement a Plant Evacuation, order a Local Area Evacuation for effected areas in accordance with procedure 5023-VIII-32, " LOCAL AREA EVACUATION AND ACCOUNTABILITY" 5.2 Direct the Security Supervisor / Leader to appoint an officer to act as the Assembly Area C9ordinator and dispatch him to the Assembly Area.

() NOTE: Upon arrival, the Assembly Area Coordinator will maintain Communications with the Emergency Coordinator.

l SAN ONOFRE NUCLEAR GENERATING STAT [0N.. '

EMERGENCY PROCEDURE S023-VIII-33 UNI 1 2 AND 3 REVISION 1 Page 3

.. (1'~)6.0 PROCEDURE _ (continued) 6.3 If a Site Emergency has not been declared have the following announcement made over the public address system:

" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: THERE IS A

(HIGH RADIATION LEVEL / FIRE /0THER HAZARD) INDICATED IN (specify area) ALL PERSONNEL WITH EMERGENCY ASSIGNMENTS REPORT TO 'YOUR DUTY STATION. ALL OTHER PERSONNEL F: PORT TO YOUR DESIGNATED ASSEMBLY AREA. 1HERE WILL BE NO EATING, DRINKING OR S*d OKING UNTIL FURTHER NOTICE;"

(Provide any additional instruction if neccessary) 6.4 Repeat announcement two additional times. Initiate " Plant Evacuation Checklist," Attachment 8.2 6.5 If the emergency is radiological in nature, direct that the Radiological Emergency Siren (Thunderbolt) be sounded.

6.6 Call Unit 1 Control Room (Bell. or PAX ~

/,

inform them of the Plant Evacuation, and indicate that'they p) v should assemble their non-essential personel also implementing S01-VIII-33, " PLANT EVACUATION AND ACCOUNTABILITY". -

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6.7 Ensure personnel evacuate in accordance with Attachment 8.2

'6.8 Initiate personnel accountability for a Plant Evacuation as follows (this should normally be delegated to the Security Leader):

6.8.1 Direct the supervising security officers at each of the protected area exits to determine the names of the individuals, who have not evacuated the Protected Area by using the sign out registor, and have them promptly report these names to the TSC.

6.8.2 Determine the names of the Emergency Team Members and operations personnel in the Control Room, TSC and OSC.

6.8.3 Direct the supervising security officer to provide the TSC with the names of security personnel who are still at their posts.

NOTE: Ensure that all personnel listed as being within the Protected Area are Emergency Team Members, operations, or security personnel. -

6.8.4 If a complete accounting of all persoanel within the Protected Area indicates a missing or trapped individual, report individual name(s) and last known location (s) to the Emergency Coordinator, and recommend that he implement procedure 5023-VIII-39,

" RESCUE."

5AN ONOFRE NUCLEAR GENERATING STATION M GENCY PROCEDURE S023-VIII-33 1 2

UNIT 2 AND 3 REVISION 1 Page 4 O

6.0 PROCEDURE (continued) 6.9 Direct the Health Physics Leader to assess the radiological status of affected areas as follows:

6.9.1 Direct Health Physics personnel to perform radiological surveys in affected areas per procedure 5023-VIII-24, " DIRECTION OF ONSITE EMERGENCY MONITORING". The purpose of these surveys is to determine the extent, natuta, and, if possible, the source of the problem, 6.9.2 Direct tha+. Health Physics personnel perform radiological surveys at the Assembly Areas.

6.10 On the basis of radiation surveys performed in the affected areas and assembly areas, allow personnel to 'eturn to their normal work station, send personnel home, or evacuate them to an Offsite Assembly Area.

6.10.1 If the results of radiation surveys at the Assembly Area indicate radiation levels in excess of 100 mrem /hr or gross airborne radioactivity (less noble gases) in excess of 4 E-8 uCI/cc, or if continued occupancy is O- expected to result in excess of 40 MPC-hours for isotopic mix less noble gases; relocate to

(

another assembly area, or if necessary initiate a Site Evacuation (5023-VIII-34 " SITE EVACUATION AND ACCOUNTABILITY).

6.10.2 If contamination beyond the owner controlled area is observed or suspected, direct Health Physics personnel to establish a personnel monitoring station in an area where ambient radiation levels permit personnel contamiration monitoring. (Personnel within the owner controlled area are monitored upon exit from the owner controlled area.)

6.10.3 Implement procedures S023-VIII-44, " EMERGENCY CONTAMINATION CONTROL " and/or 5023-VIII-45,

" PERSONNEL AND VEHICLE MONITORING" if appropriate.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-33 UNIT 2 AND 3 REVISION 1 Page 5 O l l

- 7.0 RECORDS 7.1 Attachment 8.2 8.0 ATTACHMENTS 8.1 Criteria for Mandatory Onsite Evacuations .

8.2 Plant Evacuation Checklist.

4.

8.3 Plant Scheme Evacuation

.I K. BARR HEALTH PHYSICS MANAGER i

KB:0103F:sss 4

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-33 UNIT 2 AND 3 REVISION O Page 1 of 1 O ATTACHMENT 8.1 CRITERIA FOR MANDATORY ONSITE EVACUATIONS WHOLE BODY IMPLEMENT RADIOIODINE DOSE RATE EVACUATION CONCENTRATION (arem/ hour) WITHIN (7 CI/cc)

Up to 600 8 Hours Up to IE-5 l

600 to 1000 4 Hours IE-5 to 2E-5 1000 to 2500 2 Hours 2E-5 to 4E-5 2500 to 5000 1 Hour 4E-5 tc 7E-5 5000 to 10,000 30 min. 7E-5 to IE-4

. 10,000 to 20,000 15 min. IE-4 to 3E-4

>20,000 IMMEDIATELY > 3E-4 O 1. It is important to realize that there is no direct correlation between the whole body dose rates and the radioiodine concentrations; and the

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measurements or projections of each must be performed independently.

l In the event that only a direct radiation determination is available, with no corresponding knowledge of the concentration or fraction of the total which is attributable to radioiodine, the most conservative dssumptions specified in the USEPA Manual for Protective Action Guides would be required. Such assumptions ~, based only on direct radiation determinations, would likely result in gross over-estimation of thyroid

dose commitment.

2. Whole body dose to non-emergency personnel should not exceed 5000 crem from the event. The whole body dose rates specified above are based on 5000 mrem. This value is based on the USEPA PAG Manual specified upper 4

limit for members of the general public. Although this table specifies mandatory evacuation times, in the absence of significant constraints evacuations should be implemented to maintain personnel exposure as low as reasonably achievable and within specified quarterly exposure limits.

3. Maximum concentrations for specified time corresponds to approximately j 25,000 mrem adult thyroid dose commitment. Radiciodine concentration vs. adult thyroid dose commitment based on Appendix D. (January 1979) to USEPA Manual of Protective Action Guides. Radioiodine nuclide distribution corresponds to four (4) hours following reactor shutdown.

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4 SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-33 UNIT 2 AND 3 REVISION 1 Page 1 of 2 fs

( ATTACHMENT 8.2

'~ PLANT EVACUATION CHECKLIST (For use with Procedure 5023-VIII-33)

1. Local Area Evacuation Announced: ( YES / NO ) Time Plant Evacuation Announced: ( YES / NO..) Time

/

EMERGENCY C0r'01NATOR SIGNATURE DATE

2. Units 2 and 3 Control Room notified. / /

E.C. IN.I.TIAL TIME DATE

3. Accountability Implemented: (Required within 30 minutes)

a. All involved individuals accounted for: ( YES / NO )

b. The following individuals are unaccounted for (if applicable)

c. " RESCUE" procedure implemented if applicable. ( YES / NO )

/ /

E. C. INITIAL TIME DATE

4. Reason for evacuation:

/ /

E. C. INITIAL TIME DATE l

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGEN Y PROCEDURE S023-VIII-33 UNIT 2 AND 3 REVISION 1 Page 2 of 2

-() ATTACHMENT 8.2

5. Radiation surveyor (s) dispatched: ( YES / NO )

/ /

E. C. INITIAL TIME DATE

6. Summary of plant radiological status: ,.

/ /

E. C. INITIAL TIME DATE

7. Offsite agencies notified: ( YES / NO )

Summary of subsequent actions taken:

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/ /

E. C. INITIAL TIME DATE NOTE: AFTER THIS CHECKLIST IS COMPLETED AND IS NOT REQUIRED FOR IMMEDIATE USE, FORWARD IT TO THE ADMINISTRATIVE LEADER.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-33

- UNIT 2 AND 3 REVISION 1 Page 1 of 2 ATTACHMENT 8.3 PLANT EVACUATION SCHEME

1. All personnel within the Protected Area except Operations, Security, and Emergency Team Members shall evacuate through the Protected Area North Gate to the Warehouse Assembly Area at the North End Receiving Bay of the AWS Building.

1.1 Personnel within the protected area, should remove protective clothing and put on clean clothing prior to proceeding to the Warehouse, unless instructed otherwise by Health Physics Pesonnel.

1.2 Personnel should avoid the area immediately South of the Containment Sphere and Turbine Deck on their route out of the Protected Area.

1 1.3 The Guard in the tower station will report to the AWS Warehouse Assembly Area to assist the Assembly Area Coordinator. Security Officers at the Protected Area South Gate entrances shall close their posts and remove the badges and registration logs and set up an alternate post at the North PA Vehicle Gate or report to an assembly area as directed by the Security Leader.

2. All personnel, including visitors and contractors, outside the Protected Area, but within the Owner controlled Gates, shall report to the AWS Warehouse at the north end receiving area.

3. Administration Shop and Warehouse (AWS) Building personnel shall report as follows:

3.1 Personnel in the Administration and Engineering Area (except CDM Center) should proceed to the Assembly Area at the Warehouse North Entrance.

3.2 Personnel in the shop and supply counter area of the Warehouse should proceed through the Warehouse to the North Receiving Area l

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- I EMERGENCY PROCEDURE 5023-VIII-33 5 SAN ONOFRE NUCLEAR GENERATING STATION REVISION 1 Page 2 of 2 UNIT 2 AND 3 ATTACHMENT 8.3 8

PLANT EVACUATION SCHEME j

3.3 Personnel in the CDM Center shall remain in the Center, complete pre-evacuation CDM Procedures as may be required and report to the Senior Supervisor present for additional instructions.

4 Visitors and Contractors within the Site boundary shall report to the AWS Warehouse North Entrance Receiving Area and await the instructions of the Assembly Area Coordinator.

5. The Assembly Area Coordinator (s) shall ensure a list of all personnel is prepared and provide any additional instructions tu those assembled at the Assemoly Area.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 REVISION 1 Page 1 UNITS 2 AND 3 OCT 9 1981 - o, EW EP SITE EVACUATION AND ACCOUNT g 1M931 cp

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7"N 2 E R$g * '

l 1.0 OBJECTIVE ylf; @

This procedure provides directio n4lAg .

1.1 evacuation of non-essential personnel assigned emergency response function) from ge ,. ~:

y evacuation may be precautionary in anticipation conditions. The Emergency Coordinator is responsible Q implementation of this procedure. .

1.2 Should complete evacuation (all personnel) of the SONGS Site become necessary, the basic instructions in this procedure, v'th appropriate changes, should still be followed to the extent practicable.

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station Unit 2 and 3 Emergency Plan 2.2 Emergency Procedure 5023-VIII-11, " Recognition and Classification of Emergency Conditions" 2.3 Emergency Procedure 5023-VIII-15, " General Emergency" C)

U 2.4 Emergency Procedure S023-VIII-32, " Local Area Evacuation and 3

( Accountability" 2.5 Emergency Procedure 5023-VIII-33, " Plant Evacuation and Accountability" 2.6 Emergency Procedure 5023-VIII-61, "Re-entry" 3.0 PREREQUISITES 3.1 Declared General Emergency, or:

3.2 Radiation dose rates, radiodine concentrations, and associated permissible occupancy times in excess of those in " Criteria for Mandatory Onsite Evacuations" (Attachment 8.1) in major portions of the plant.

3.3 A Site Evacuation should be considered when:

3.3.1 Significant ground level releases have occurred or are projected, or:

3.3.2 Other safety hazards, such as toxic gases, fire, or flammable gases which affect large areas of the plant and/or site, or:

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l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 REVISION 1 Page 2 UNITS 2 AND 3 O

V 3.0 PREREQUISITES (continued)

Adverse weather conditions, such as floods,

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3.3.3 hurricanes, or tornades, are present or are expected to occur. In the case of adverse weather, advance weather warnings will normally provide adequate time for an orderly dismissal of plant personnel, without the need for evacuation.

s 3.3.4 Personnel Accountability must be completed within 30 minutes 4.0 PRECAUTIONS 4.1 Evacuation of the Control Room should only ae implemented in the event of:

4.1.1 Uncontrollable fire in the Control Room, or:

4.1.2 Heavy smoke or toxic or flammable gases in the Control Room, or:

4.1.3 Radiation dose rates, radioactive iodine cor.centrations, and associated permissible occupancy times exceeding those in " Criteria for Mandatory

, - c^tt ch e=t 8 1)

O o# site avece 14

( NOTE: Evacuation of the Control Room should only be implemented after respiratory protective equipment and other protective measures prove inadequate.

4.2 The actual decision to implement a Site Evacuation is the responsibility of the Emergency Coordinator. The decision should be based upon the Emergency Coordinator's evaluation of the magnitude and severity of the situation.

4.3 Prior to ordering an evacuation of site personnel, the Emergency 99ordinator should determine, based on the best information available, that evacuation is the protective action that will result in the lowest personnel expcsure. In ordering an evacuation, the Emergency Coordinator should consider (1) dose rates at Assembly Areas, onsite and along evacuation routes; and (2) whether or not these conditions can be mitigated prior to personnel receiving significant exposures.

4.4 Evacuations sh mld be accomplished either before or after the )

passage of the release, and evacuation routes should be chosen l

l that lead personnel away from the path of the plume.

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..- SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-34 UNITS 2 AND 3 REVISION 1 Page 3 O 4.0 PRECAUTIONS (continued) 4.5 The condition under which a Site Evacuation would be initiated could involve significant release offsite with resultant contamination of environmental surface.c offsite. Under these conditions, delaying Site Evacuation to monitor and/or decontaminate personnel or vehicles would be superfluous, in light of the potential for re-contamination offrite. In this case, personnel should be directed to pnceed directly to the upwind offsite assembly area for monitoring. If all offsite assembly areas are within sectors fror., which the population is being evacuated, the Emergency Coordinator, in cooperation with SCE management, State and County Agencies, shall designate an assembly area at which personnel monitoring will be performed.

In this event, vehicles will be monitored as provided in the emergency plans of the affected jurisdiction.

5.0 CHECK-OFF LISTS 5.1 Site Evacuation Checklist.

6.0 PROCEDURE 6.1 Evaluate information available on initiating event. If additional time or information is needed prior to making the O^ eecisie# se imaieme#t site ev c# tio#. ereer ei #t ev c# tie #

in accordance with procedure 5023-VIII-33, " Plant Evacuation and

(' Accountability".

6.2 Direct the Security Leader to appoint an officer to act as Assembly Area Coordinator, and dispatch him to the Assembly Area.

NOTE: Upon arrival, the Assembly Area Coordinator will establish communications with the Emergency Coordinator at the TSC.

6.3 Prior to ordering a Site Evacuation direct the Health Physics Leader to dispatch teams to survey affected parking lots in accordance with Procedure 5023-VIII-45, " PERSONNEL AND VEHICLE MONITORING."

6.4 If monitoring teams report the presence of contamination in parking lot (s) perform the following:

.1 Direct the Security Leader to restrict access to the contaminated parking lot (s).

~

.2 Inform the Assembly Area Coordinator of the problem with contaminated parking lots and the resultant need for car pooling using clean parking lot vehicles. ;

.3 Use this information to modify the evacuation annoer. cement !

if required.

NOTE: Prior to announcement, consideration should be given to whether evacuees are to be sent home or to off-site Assembly Areas.

l SAN ONOCRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 UNITS 2 AND 3 REVISION 1 Page 4 6.0 PROCEDURE (continued) 6.5 Have the following announcement made over the public address system.

" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: ALL PERSONNEL 1

WITH EMERGENCY ASSIGNMENTS REPORT TO YOUR DUTY STATIONS. ALL OTHER PERSONNEL REPORT TO YOUR DESIGNATED ASSEMBLY AREA AND AWAIT FURTHER INSTRUCTIONS PURSUANT TO ORDERLY EVACUATION OF THE SITE." (Provide any additional instructions neccessary).

or:

" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: ALL PERSONNEL EXCEPT THOSE WITH EMERGENCY ASSIGNMENTS SHALL EVACUATE THE SITE IMMEDIATELY. PROCEED IN YOUR CAR TO

[THE (NORTH / SOUTH) 0FFSITE AND AWAIT FURTHER ASSEMBLY AREA /YOUR HOME]

f3

\#- INSTRUCTIONS."

, (Provide any additional instructions neccessary) 6.6 Repeat the announcement two additional times. Initiate " Site Evacuation. Checklist," Attachment 8.3. If the emergency is radiological in nature, direct that the Radiological Emergency Siren (Thunderbolt) be sounded.

6.7 Inform Unit 1 Watch Engineer (Bell or PAX m [of incident and request that they initiate a Site Evacuation. '

6.8 Direct the Security Leader to implement Emergency Procedure 5023-VIII-35 " TRAFFIC AND ACCESS CONTROL", and to assure that i

personnel evacuate per the Attachment 8.2.

NOTE: If radiological conditions warrant, security personnel directing traffic should be equipped with appropriate respirators and protective clothing.

6.9 Implement Emergency Procedure 5023-VIII-24, " DIRECTION OF ONSITE EMERGENCY MONITORING."and to direct the Health Physics Leader to dispatch Emergency Monitoring Teams to the Assembly Area.

6.10 Direct the Health Physics Leader to implement procedure kl. 5023-VIII-45, " PERSONNEL AND VEHICLE MONITORING," unless to do so would conflict with the guidance in Precaution 4.5 of this procedure.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-34 UNITS 2 AND 3 REVISION 1 Page 5 O 6.0 PROCEDURE (Continued) 6.11 Initiate personnel accountability for Site Evacuation as follows (this should normally be delegated to the Security Leader):

6.11.1 Direct the supervising security officers at each of the Protected Area exits to determine the names of the individuals, who have not evacuated the Protected Area by using the sign out registor, and have them promptly report these names to the TSC.

6.11.2 Determine the names of the Emergency Team Members and operations personnel in the Control Room, TSC, and OSC.

6.11.3 Direct the supervising security officer to provide the TSC with the names of security personnel who are still at their posts.

NOTE: Ensu e that all personnel listed as being within the Protected Area are Emergency Team Members, operations or security personnel.

6.1'1. 4 If a complete accounting of all personnel within the Protected Area indicates a missing or trapped individual, report individual name(s) and last known location (s) to the Emergency Coordinator, and k( recommend that he implement procedure 5023-VIII-39,

" RESCUE".

6.12 On the basis of radiation surveys performed in conjunction with procedures 5023-VIII-24, 5023-VIII-25 (Step 6.9) 5023-VIII-45 (Step 6.10), send personnel home, retain them at the Assembly Area, or transfer them to an alternate Assembly Area, as appropriate.

6.13 Upon completion of accountability, or as mandated by conditions, have the Security Leader direct the Assembly Area Coordinator (s) to begin orderly evacuation to the designated (upwind) Offsite Assembly Area.

6.14 After Site Evacuation direct the Shift Sacurity Supervisor to begin a search of areas outsioe the Protected area to determine if any individuals have not evacuated or heard the warning signals.

7.0 RECORDS 7.1 None l

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 )

UNITS 2 AND 3 REVISION 1 Page 6 l 0

8.0 ATTACHMENTS

! 8.1 Criteria for Mandatory Evacuations l

8.2 Normal and Emergency Access Routes and Remote Assembly Areas Site Evacuation Checklist.

8.3 i

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K. BARR l HEALTH PHYSICS MANAGER i

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SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-34 UNIT 2 AND 3 REVISION 1 Page 1 of 1 ATTACHMENT 8.1 0 -

CRITERIA FOR HANDATORY ONSITE EVACUATIONS IMPLEMENT RADI0 IODINE

, WHOLE BODY EVACUATION CONCENTRATION i

! DOSE RATE (mrem / hour) WITHIN (v CI/cc) l Up to 600 8 Hours Up to IE-5 600 to 1000 4 Hours IE-5 to 2E-5 1000 to 2500 2 Hours 2E-5 to 4E-5 2500 to 5000 1 Hour 4E-5 to 7E-5 5000 to 10,000 30 min. 7E-5 to IE-4 10,000 to 20,000 15 min. IE-4 to 3E-4

]20,000 IMMEDIATELY ]3E-4

1. It is important to realize that there is no direct correlation between the whole body dose rates and the radioiodine concentrations; and the measurements or projections of each must be performed independently.

In the event that only a direct radiation determination is available, with no corresponding knowledge of the concentration or fraction of the total which is attributable to radioiodine, the most conservative assumptions specified in the USEPA Manual for Protective Action Guides would be. required. Such assumptions, based only on direct radiation determinations, would likely result in gross over-estimation of thyroid

dose commitment.

2. Whole body dose to non-emergency personnel should not exceed 5000 mrem from the event. The whole body dose rates specified above are based on 5000 mrem. This value is based on the USL' A PAG Manual specified upper limit for members of the general public. A.though this table specifies mandatory evacuation times, in the absence of significant cr.o ir..nts evacuations should be implemented to maintain personnel extosure as low as reasonably achievable and within specified quarterly exposure limits.

3. Maximum concentrations for specified time corresponds to approximately 25,000 mrem adult thyroid dose commitment. Radioiodine concentration vs. adult thyroid dose commitment based on Appendix D, (January 1979) to USEPA Manual of Protective Action Guides. Radiciodine nuclide distribution corresponds to four (4) hours following reactor shutdown.

() _

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34

UNIT 2 AND 3 REVISION 1 Page 1 of 1

' ATTACHMENT 8.2 1

NORMAL AND EMERGENCY ACCESS ROUTES l 4

AND REMOTE ASSEMBLY AREAS l l

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i SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 )

UNIT 2 AND 3 REVISION 1 Page 1 of 3 ATTACHMENT 8.3 SITE EVACUATION CHECKLIST (For use with Procedure 501-VIII-34)

1. Plant Evacuation Announced: ( YES / NO ) Time Site Evacuation announced:

( YES / NO ) Time

/

EMERGENCY COORDINATOR SIGNATURE DATE

2. Units 2 and 3 Control Room notified. / /

E.C. INITIAL TIME DATE g 3. a. " Traffic and Access Control" Procedure implemented:

( YES / NO )

Time

b. Beach evacuation initiated:

( YES / NO )

Time j

c. Emergency Radiation Monitoring Implemented:

( YES / NO ) Time

/

E.C. INITIAL DATE O

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O SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 UNIT 2 AND 3 REVISION 1 Page 2 of 3 ATTACHMENT 8.3

4. Accountability Implemented:

a. All involved individuals accounted for: ( YES / NO )

b. The follwing named individuals are unaccounted for (if applicable)

c. " RESCUE" procedure implemented if applicable. ( YES / NO )

/ /

E. C. INITIAL TIME DATE

([])

( 5. Reason for evacuation:

/ /

l. C. INITIAL TIME DATE

6. Summary of plant radialogical status:

/ /

E. C. INITIAL TIME DATE i

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.O SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-34 UNIT 2 AND 3 REVISION 1 Page 2 of 3 ATTACHMENT 8.3

7. Offsite agencies notified: ( YES / NO )

Sumary of subsequent actions taken:

^

/ /

E. C. INITIAL TIME DATE O(' NOTE: AFTER THIS CHECKLIST IS COMPLETED AND IS NOT REQUIRED FOR IMMEDIATE USE, FORWARD IT TO THE ADMINISTRATIVE LEADER.

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I EMERGENCY PROCEDURE S023-VIII-35 SAN OH0FRE NUCLEAR GENERATING STATION REVISION O Page 1 UNITS 2 AND 3 SEP 9 1981 O /

V TRAFFIC AND ACCESS CONTRO

'0"Y d

g ~b 1.0 OBJECTIVE 1.1 In the event of an emergency in e f.

radioactivity, it may be necessary to l Nuclear Generating Site. This procedure prov .

the Emergency Coordinator and Station Security vehicle and personnel ingress and egress during a si evacuation. The Sect.rity Leader is responsible for R

/

implementation of this procedure. y 4 ggg

2.0 REFERENCES

g, 2.1 SONGS-2 and 3 Emergency Plan.

2.2 Emergency Procedure 5023-VIII-34, Site Evacuation and Accountability.

2.3 Emergency Procedure 5023-VIII-45, Personnel and Vehicle Monitoring.

3.0 PREREQUISITES A site evacuation has been declared by the Emergency Coordinator.

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3.1

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4.0 PRECAUTIONS 4.1 Any type evacuation shall be conducted in an orderly manner to prevent personnel injury or property damage or both.

5.0 CHECK-OFF LIST 5.1 None 6.0 PROCEDURE 6.1 Site Evacuation Traffic Control.

6.1.1 If notified of a contaminated parkirl area prevent any vehicle from the contaminated par king lot from leaving the site.

6.1.2 Restrict personnel access to contaminated parking areas. Establish all vehicle egress control points in accordance with Figure 7.3 of the SONGS-2 and 3 Emergency Plan.

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1 EMERGENCY PROCEDURE SO23-VIII-35 SAN ONOFRE NUCLEAR GENERATING STATION Page 2 REVISION O UNITS 2 AND 3

.r(,S/ !

6.0 PROCEDURE 6.1 (continued) 6.1.3 Request the California Highway Patrol to assist in directing evacuation vehicles to the Offsite Assembly Area / or onto Rt. 5. t e

NOTE: Every effort should be made to block access to Route 5 if the decision is made to utilize Offsite Assembly Areas rather than dispatch of evacuees to their residences.

6.1.4 Have the personnel in the Onsite Assembly Area instructed as to which Offsite Assembly Area (North or South) is to be used, parking lots that the vehicles are impounded because of contamination, sharing of vehicles by people who have had their vehicles impounded and the proper way to ride in a vehicle to the Offsite Assembly Area (windows up, vents closed, no riding in open vehicles etc.).

6.1.5 Have the traffic from the site directed to the designated Offsite Assembly Area. Insure that at

-least nne lane is kept open for incoming emergency O vehicles.

(' 6.2 Site Access Control.

6.2.1 Personnel entering the site after a Site Evacuation shall require proof of entry authorization. Such proof can come in the form of personal recognition by a San Onofre Plant Staff Member, SCE indentification card or similar 1.0. Additionally, these persons shall be authorized entrance by the Emergency Coordinator or the Administrative Leader. This authorization may be verbal (via phone) cr by written roster.

6.2.2 If required by the Emergency Coordinator, all vehicles shall be escorted or directed to an approved parking lot via approved routes. Escorts should be Security Officers but may be Health Physics Technicians or other designated individuals.

7.0 RECORDS i 7.] None 1

i EMERGENCY PROCEDURE 5023-VIII-35 SAN ONOFRE NUCLEAR GENERATING STATION Page 3 REVISION O UNITS 2 AND 3 l

8.0 ATTACHMENTS 8.1 Evacuation Route and Assembly Area Diagram.

l l

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K. P. BARR HEALTH PfiYSICS MANAGER O .

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eV SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-36 PAGE 1 UNITS 2 & 3 REVISION NEW

.SEP 9 1981 THYROID PROPHYLAXIS Y

1.0 OBJECTIVE 4 $ I

g. k >

This procedure provides guidance for determining when potassium iodide (KI) should be issued to SONGS 2 & 3 personnel, for thyroid bloclPJiicelyen minimize I-131 uptake. The Health Physics Leader is responsible for implementing this procedure. OCT 141981

2.0 REFERENCES

CDM SITE 4

2.1 NCRP Report No. 55 - Protection of the Thyroid Gland in the Event of Releases of Radioiodine 2.2 EPA - 5201/1-75-001, Manual of Protective Action Guides 2.3 NUREG - 0654, Rev 1 Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants n 3.0 PREREQUISITES V An emergency condition involving release of radioactive material has been

( declared at the Units 2 & 3 San Onofre Nuclear Generating Station as provided

~

in the SONGS 2 & 3 Emergency Plan.

4.0 PRECAUTIONS 4.1 All Station Emergency workers should be tested for sensitivity to Iodine prior to issue or use. This is normally done during respiratory protective device user qualification.

4.2 Unless medical personnel are available to administer potassium iodide (KI), only the Health Physics Leader or his designee shall administer KI.

4.3 KI shall be administered only when the thyroid dose is estimated to be 10 rads or greater based on estimated or measured I-131 airborne con-centrations.

4.4 Only one 130 mg KI tablet (100 mg of iodide) shall be administered daily to each individual involved.

4.5 After KI administration has been initiated for an individual, daily KI administration shall continue for the individual for at least 6 additional consecutive days but in no case shall the total length of admiristration exceed 10 consecutive days (for a total iodide dose of about 1 gram).

' EMERGENCY PROCEDURE S023-VIII-36 SAN ONOFRE NUCLEAR GENERATING STATION PAGE 2 REVISION NEW UNITS 2 & 3 4.0 PRECAUTIONS (Cont'd) 4.6 The maximum efficiency for thyroid blocking is achieved if KI is administered before an I-131 uptake occurs or within__ two_ hours af ter an 1-131 uptake occurs. KI administration is of some value for thyroid blocking as long as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after an I-131 uptake occurs but is of little value after that.

4.7 The administration of KI must be documented.

4.8 Follow-up medical surveillance is required for individuals who take KI.

5.0 CHECK-OFF LISTS Not Applicable 6.0 PROCEDURE 6.1 Detemining the Need for KI Administration ,

6.1.1 The Emergency Coordinator or his designee shall detemine

(

the need for KI administration as follows:

NOTE: The following steps can be used to determine the need for KI prior to a planned uptake or after an uptake has occurred, i

J .1 Detemine by estimation or actual measurement the I-131 airborne concentration in the area of interest.

.2 Divide the I-131 airborne concentration by the Protection Factor (PF) of the respiratory protective equipment used.

If respiratory protective equipment is not used, the PF=1.

.3 Determine the proposed residency time of the individual (s) in the area.

I .4 Find the time determined in Step 6.1.1.3 on the vertical

' " Minutes" axis on the graph (Attachment 8.1).

!O

! 1

{

estaetnCy eRoCsouat So23-v111-se O San onorat nuttexa czutaarina 51x11on UNITS 2 & 3

- REVISION NEW PAGE 3 6.0 PROCEDURE (Cont'd) 6.1.1.5 Find the I-131 concentration determined in Step 6.1.1.2 on the horizontal "I-131 Concentration" axis on the graph and follow the line vertically until in intersects the time line located in Step 6.1.1.4.

.6 If the point of intersection is to the left of the curve on the graph, the projected dose to the thyroid is less than 10 rad and no further action is required as thyroid blocking is unnecessary.

.7 If the point of intersection lies on the curve or to the right of the curve, the projected dose to the thyroid is 10 rad or more and thyroid blocking is necessary. Con-tinue with Section 6.2.

6.2 Administering KI 6.2.1 Enter the name and social security number of each individual

' who will receive a KI tablet on a KI Issue Record form (see Attachment 8.2).

6.2.2 Enter the date of the first administration and the initials of the individual who is dispensing the KI tablets in the first column on the fonn.

6.2.3 Give one KI tablet to each individual requiring KI.

NOTE: KI is stored in the Control Room.

6.2.4 Continue to dispense one KI tablet each day to each individual listed on the form for at least 6 additional consecutive days but in no case for greater than a total of 10 consecutive days.

NOTE: The State Department of Health is responsible for administration of radioprotective drugs to the general population.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-36

/~'s PAGE 4 l

'V UNITS 2 & 3 REVISION NEW 6.0 PROCEDURE (Cont'd) 6.3 Medical Surveillance i

6.3.1 Medical surveillance is required for any individual (s) administered KI. The surveillance program will be

' established by the SCE Medical Department.

! 7.0 RECORDS 1

Record of KI Issuance shall be forwarded to the Administrative Leader, 1 the Health Physics Leader and the SCE Medical Department.

8.0 ATTACHMENTS

~

8.1 Graph of " Minutes" vs "I-131 Concentration" 8.2 KI Issue Record iO m K. P. E S.RR l HEALTH PHYSICS MANAGER

(

i i JSD:emb I

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. SAN OfiOFRE NUCLEAR GEtiERATING STATION EMERGENCY PROCEDURE S023-VIII-36

, UNITS 2 & 3 REVISION NEW ATTACHMENT 8.1

. PAGE 1 0F 1

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' SAN ONDFRE NUCLEAR GENERAT!NG STATION EMERGENCY P?.0CEDURE S023-VIII-36 UNITS 2 & 3 REVISION NEW ATTACHMENT 8.2

.e' PAGE 1 0F 1 Kl ISSUE RECORD Kl Administrati an 1 2 3 4 5 6 7 8 9 10 Date Date Date Date Date Date Date Date Date Date Int. Int. Int. Int. Int. Int. Int. Int. Int. Int.

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I

l SAN ONFRE NUCLEAR GENERJiNG 7ATION EMERGENCY PROCEDURE S023-VIII-37 m UNIT 2 AND 3 REVISION O Page I 9 1981

.(J 0 01 FIRE FIGHTI N

1.0 OBJECTIVE ClfEC T-If /0N t

This procedure decribes the actions (Jf9F)

' - l.Fg of a fire in Units 2 and 3.

[O

2.0 REFERENCES

2.1 SONGS -2 and 3 Operating Instruction S023-3.5-5.35, " PLANT FIRES" 2.2 SONGS -2 and 3 Health Physics Procedures 2.3 NUREG-0654/ FEMA-REP-1, " CRITERIA FOR PREPARATION AND EVALUATION OF RADIOLOGICAL EMERGENCY RESP 0;i3E PLANS AND PREPAREDNESS Tti R tic e i V E D SUPORT OF NUCLEAR POWER PLANTS" 2.4 SanOnofreNuclearGeneratingStationUnit2and3EmehIch41N.I a.n n.

ef c" 6 3.0 PREREQUISITES AE 100 CPM above background), cover the wound area and decontaminate other skin areas in accordance with Health Physics Procedure S023-VII-4.4, " Personnel Decontamination" (Reference 2.3).

E. If contamination levels in or around the wound exceed 100 CPM above back-ground, proceed as follows:

! 1. Prepare a thick detergent paste. j

2. Dip a cotton swab in the detergent paste and rub a small area of the skin immediately surrounding the wound, using a motion which starts by placing the cotton swab at the edge of the wound and then moves away from the wound (do not rub towards the wound). Use as many swabs as necessary to clean an area about 1 1/2" vide around the wound.

3. Moisten a swab in water and rinse the detergent from the skin sur- I rounding the wound, using the same motion as that used for applying '

the detergent paste. Use as many swabs as necessary until the skin is completely rinsed.

4. Blot the skin dry using clean, absorbent material.

O

SAN ONOFRE NUCLFAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-38 REVISION NEW ATTACHMENT 8.2 v ' UNITS 2 & 3 PAGE 2 0F 4

< MINOR CONTAMINATION INJURY TREATMEIR F. Survey the wound and surrounding area using a count rate instrument with a thin window G-M detector and open and closed window readings with an Ion Chamber (preferable) or G-M tube detector.

G. If contamination levels in or around the wound do not exceed 100 CPM above background, administer necessary first aid in accordance with the First Aid Manual to treat the wound. Survey remaining skin areas.

If other skin areas are contaminated (> 100 CPM above background),

cover the wound area and decontaminate other skin areas in accordance with Health Ph sics Procedure S023-VII-4.4, " Personnel Decontamination" (Reference 2.3 .

H. If contamination levels in or around the wound still exceed 100 CPM above background, repeat Steps I-E-1 through I-E-4, a maximum of two addition cycles. (A maximum of.3 decontamination cycles is recomended to prevent possible damage to the skin surrounding the wound).

I. Survey the wound and surrounding area using a count rate instrument with a thin window G-M detector and open and closed window readings with an Ion Chamber (preferable) or G-M tube detector.,

Q

(~ J. If contamination levels in or around the wound have been reduced to 100 CPM above backgorund or less at the end of 3 cycles, administer necessary first aid in accordance with the First Afd Manual to treat the wound.

- Survey rem'aining skin areas. If other skin areas are contaminated (>

100 CPM above background), cover the wound area and decontaminate other skin areas in accordance with Reference 2.3.

K. If contamination levels in or around the wound still exceed 100 CPM above background (it must be assumed that some or all of the radioactive-material is in the wound), notify the Health Physics Manager.

l L. After being notified that a wound may be contaminated, the Health Physics Leader shall call the following physician for medical advice:

Dr. J. F. Ross - Office: ,

]'-Home: (Later)

M. Further treatment of the wound will proceed following the advice of ,

the physician or will be performed with direct assistance by the physi-cian.

1 l

f 1} SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-38 REVISION NEW ATTACHMENT 8.2 UNITS 2 & 3 PAGE 3 0F 4 MINOR CONTAMINATION INJURY TREATMENT N. If the physician is to come to the station, the Watch Engineer shall call the Security Force to alert them and to give them instructions as to where to escort the physician when he arrives.

0. If skin areas other than the wound area are contaminated (> 100 CPM above b6ckground), cover the wound area and decontaminate other skin areas in accordance with Reference 2.3.

i e

O T

l l

l lO i

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.g SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 EMERGENCY PROCEDURE S023-VIII-38 REVISION NEW ATTACHMENT 8.2 PAGE 4 0F 4 MINOR CONTAMINATION INJURY TREATMENT II. If .the injury is not an open wound, proceed as follows:

A. If the individual was not in a radiological control area when the injury occurred, administer necessary first aid in accordance with the First Aid Manual.

B. If the individual was in a radiological control area when the injury occurred, perform a complete body survey using a count rate instru-ment with a thin window G-M detector.

C. If contamination levels on the skin in the area of the injury and on the remainder of the body do not exceed 100 CPM above background, administer necessary first aid in accordance with the First Aid Manual to treat the injury.

D. If wontamination levels on the skin in the area of the injury and/or on the remainder of the body exceed 100 CPM above background, decon-taminate in accordance with Health Physics Procedure, S023-VII-4.4,

" Personnel Decontamination" (Reference 2.3). Obtain contamination (mj readings with open and closed window readings from an Ion Chamber (preferable) or G-M tube detector.

E. If the skin in the area of the injury is contaminated and if decon-tamination is unsuccessful in 3 or less cycles, administer necessary first aid in accordance with the First Aid Manual to treat the injury.

F. If the skin in the area of the injury is contaminated and if decon-tamination is unsuccessful in 3 or less cycles, notify Health Physics Manager.

G. The Health Physics Leader shall call the following physician for medical advice:

Dr. J. F. Ross - Office: - Home: (Later)

H. Further decontamination and treatment of the injury will proceed follow-ing the advice of the physician or will be performed with direct as-sistance by the physician.

I. If the physician is to come to the station, the Watch Engineer shall call the Security Force to alert them and to give them instructions as to where to escort the physician when he arrives, and provide personnel monitoring as required by the Health Physics Leader.

O

o SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-38 ATTACHMENT 8.3 REVISION NEW UNITS 2 & 3 PAGE 1 0F 1 DIRECTIONAL MAP TO SOUTH C0AST COMMUNITY HOSPITAL Go through Dana Point See Figure IV-A

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t O SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-38 UNITS 2 & 3 REVISION NEW ATTACHMENT 8.4 PAGE 1 0F 1

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I' SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-38 UNITS 2 & 3 REVISION NEW ATTACHMENT 8.5 PAGE 1 0F 1 SOUTH C0AST C0fHUNITY HOSPITAL LAYOUT -

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/

EMER FNCY PROCEDURE 5023-VIII-39 SAN ONOFRE NUCLEAR GENERATING STATION REVI I i

PAGE 1 UNITS 2 & 3 IBBI SE ~

RESCUE % 'VED MP AE .

N 1.0 OBJECTIVE F0g 3 y This procedure provides instructions for the rescue of pe d 80 who may be trapped or disabled in some part of the station.

gency group leader is responsible for 4ctions prescribed m by this ,rpr

~'

cedure. t 7m 7. r ( ,

2.0 REFERENCES

VEb b 2.1 San Onofre Nuclear Generating 56ation Units 2 & 3 Emergency Plan 2.2 Health Physics Procedure, 5023-VII-1.0, " Health Physics Manual" 2.3 Emergency Procedure, 5023-VIII-31 " Emergency Exposure Control" 2.4 Emergency Procedure, S023-VIII-38, " Contaminated Injury" 3.0 PREREQUISITES r

An emergency condition has been declare,d at San Onofre Nuclear Generating Station, Units 2 & 3.

/

4.0 PRECAUTIONS All normal and emergency safety precautions are to be observed. Specific precautions are listed in the bcdy of the procedure.

5.0 CHECK-0FF LISTS _

5.1 Attachment 8.1 - Rescue Team Action and Checklist 6.0 PROCEDURE 6.1 General 6.1.1 Upon notification of a missing or trapped person, the Control Operator shall announce over the public address system that(If the rescue brigade should report to the area involved.

location of missing person is not known, the rescue briaade should be told to report to the Operations Support Center).

This message should be repeated.

6.1.2 The Watch Engineer shall acknowledge receipt of the alarm If the Centrol Room Operator does not to the Control Room.

receive an acknowledgment from the Watch Engineer in 2 minutes,

> he should repeat the announcement.

l

) SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-39 REVISION NEW PAGE 2 UNITS 2 & 3 -

6.0 PROCEDURE (Cont'd) 6.1.3 1' the location of the missing person is not knc.vn, the Ewergency Group Leader shall contact the Control Room to gather information and organize a search party to try to locate the missing person. The search party should in-clude a person from the Health Physics Group.

6.1.4 Once the location of the missing person is established, the Emergency Group Leader shall direct the rescue brigade to report to the crea. He shall also obtain two lifelines and appropriate radiation instruments from the Operations Support Center. (If the location is in a High Radiation Area, obtain a Teletector and 0-50R dosimeters from the erergency kit in the Operations Support Center). The Health Physics techni-cian at the location may provide additional input and radio-logical monitoring 6.1.5 The Emergency Group Leader shall direct personnel to do the 7s following if needed when instructed to report to the rescue (m,)

area:

e I .1 Two people (Assistant Control Operators on backshifts) should l

pick up a stretcher in the most convenient location. If the area is potentially contaminated, they should also pick up protective clothing for three people.

.2 One person (Plant Equipment Operator on backshifts) should pick up two self-contained air supplied masks to take to the rescue area.

' 6.1.6 At the rescue area, the Assistant Control Operator or indivi-dual appointed by the Emergency Group Leader shall be director of the rescue operations. The director and one man will enter the immediate area to assess the situation:

NOTE: As part of the assessment of the situation, Health Physics should provide radiological monitoring of the areas of interest.

.1 If the area is known to be contaminated or if an explosion or massive escape of steam is involved in an area where it s

. can be contaminated, protective clothing and respiratory protection shall be worn.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-39 UNITS 2 & 3 REVISION NEW PAGE 3 6.0 PROCEDURE (Cont'd) 6.1.6.2 If the area is smoke or steam filled, or if the area is in

! disarray because of fire or explosion, the men shall use lifelines and the self-contained air-supplied masks as necessary.

.3 If there is potential radiation in the area, radiation levels shall be monitored as the area is entered.

6.1.7 On the basis of this inspection of the area, the rescue should be completed or, if the rescue is complicated by the condition of the area, the brigade will retire to a safe area and plan the method of rescue. (See Section 6.2) 6.1.8 If offsite emergency response assistance is required, refer to the emergency telephone numbers list (" Notifications" S023-VIII-16).

, p 6.2 Specific Complications

d 6.2.1 High Radiation

(

.1 Changes from nonnal Health Physics Procedures.

If an individual is tirapped or disabled in an area in which the dose received during the rescue effort will be greater thara 300 mrem, the rescue must be carried out as expeditiously as possible to keep the dose to the victim as low as possible.

Therefore, for the rescue of personnel in which undue delay might result in the victim's death, the following modifications supersede the Health Physics Manual.

.1.1 Prior approval for exposures covered by this procedure are required except in imediate Life or Death situations.

.1.2 Exposures in excess of 10 CFR 20 limits are allowed provided the criteria in Emergency Procedure 5023-VIII-31, " Emergency Exposure Control" are followed.

.2 Action to be taken.

l

.2.1 Complete all the items in Sectior.s 6.1.4 through 6.1.7 but I

wear the 0-50R self-reading dosimeters and using the Tele-tector, enter the area and attempt to complete the rescue. .

l

.O EMERGENCY PROCEDURE S023-VIII-39 PAGE 4 SAN ONOFRE NUCLEAR GENERATING STATION REVISION NEW UNITS 2 & 3

-- t 6.0 PROCEDURE (Cont'd) 6.2.2 Fire .

.1 Rescue of a victim shall take precedence ever fire fighting uniess the fire can be put out quickly with no detrimentr.1 affect on the victim, or if it is necessary to suppress the fire to accomplish rescue.

.2 Action to be taken.

.2.1 Complete all items in Sections 6.1.4 through 6.1.7.

.2.2 Obtain rainsuits from the fire fighting supplies.

.2.3 One rescuer should spray water (using a hose and spray nozzle) over the others while they perfo m the rescue.

6.2.3 Steam or Hot Water

.1 Rescue of a victim shall take precedence over isolation of system unless:

.1.1 It is necessary tu isolate the system to perform the rescue.

.1.2 Tb "' ion of not isolating the system will seriously affect r safety or will place the lives of other personnel in immediate danger.

.2 Action to be taken.

.2.1 Complete all item.; in Sections 6.1.4 through 6.1.7.

.2.2 Obtain rainsuits from fire fighting supplies.

.2.3 One rescuer should spray water (using a hose and spray nozzle) over the others while they pei form rescue. 1 6.2.4 Wreckage

.1 Acti. a to be taken.

.1.1 Complete ail items in Sections 6.1.4 through 6.1.7.

~

.1.2 Obtain tools necessary to perfonn the rescue from the p maintenance shop.

V i .1.3 Enter the area and perform the rescue.

I l

I

4 4

t EMERGENCY PROCEDURE S023-VIII-39 l SAN ONOFRE NUCLEAR GENERATING STATION PAGE 5

' REVISION NEW

! UNITS 2 & 3 l ,

6.0 )ROCEDURE (Cont'd) 6.3 Action After Rescue 1

6.3.1 Remove the victim to the closest safe area and apply any required first aid.

6.3.2 If the victim is injured, advise the Control Room of the i

situation and take the following actions according to Emergency Procedure 5023-VIII-38, " Contaminated Injury". .

7.0 RECORDS

! Forward all records of rescue actions and radiation doses to the Admini-strative Leader.

8.0 ATTACHMENTS

! 8.1 Rescue Team Action and Checklist

]

lO (

4 K. P. BARR HEALTH PHYSICS MANAGER JSD:emb ,

I r

4

. ()

i 1

EMERGENCY PROCEDURE S023-VIII-39

f3 s/ SAN UNITS ONOFRE 2 & 3 NUCLEAR GENERATING STATION REVISION NEW ATTACHMENT 8.1 PAGE 1 0F 2 RESCUE TEAM ACTIONS AND CHECKLIST

1. Date: Time:

2. Emergency Group Leader in OSC:

3. Team Members: -From Organizational Group

a. (Director) b.

c.

Identity of Missing Person (s) Probable Location (s) Injury 4.

a.

b.

c.

() 5. Potential Conditions at Location (s) (Circle as appropriate)

a. Contaminated b. High Radiation c. Steam Release d. Smoke or Steam Filled

(

e. Fire f. Wreckage g. Loss of Illumination

6. As appropriate to conditions, obtain from OSC the following:

a. Two (2) life lines

b. Radiation measuring instruments

c. Dosimeters and TLD's

d. Telectors

e. 0 - 50R dosimeters Stretcher f.

9 Protective clothing for three (3) persons

h. Two (2) self-contained air supply masks i 1. Flashlights or spotlights

() j. Radio communication equipment

k. Other (specify) s

i SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-39 UNITS 2 & 3 REVISION NEW ATTACHMENT 8.1 PAGE 2 0F 2

~

RESCUE TEAM ACTIONS AND CHECKLIST

7. Authorization obtained for emergency exposure limits?

8. Inspection of area indicates conditions:

a.

b.

c.

9. Missing person (s) located: Time: Location:

10. Condition of missing person (s) (medical attention require?):

11. Notify Emergency Group Leader of condition:

12. Firs Aid Team arrives (if required): Time:

i t

I 13. Rescue complete: Time:

14. Rescue Team members return to OSC:

a. Time:

b. Time:

i c. Time:

15. Copy of this checklist to Emergency Group Leader:

Completed By:

Date Time 1

0 4

o

SAN ONOFRE NUCLEAR GENERATING STATION EM' *

PROCEDURE S023-VIII-41 UNITS 2 AND 3 R ISION 0 0 % '

0 8Ygf,0NSTRUCTION A

. CHEcyAPPL UP Usp gy(y C

N FOR y y TROLLE0 ONSITE MONITORING g 1.0 OBJECTIVE 1.1 This procedure provides instructions and guidance for conducting radiological monitoring onsite during an emergency.

1.2 Assigned Heelth Physics Technicians are responsible for implementation of this procedure.

P.0 REFERENCES 2.1 NUREG-0654, Rev.1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

O 2.2 Sen Onofre Nucie r Geaeratias Statioa uait 2 aad 3 Emerseacx ei #.

2.3 SONGS - 2 and 3 Health Physics Procedures.

2.4 EPIP S023-VIII-24. " Direction of Onsite Emergency Monitoring."

2.5 EPIP 5023-VIII-31, " Emergency Exposure Control".

7.6 EPIP S023-VIII-36, " Thyroid Prophylaxis."

2.7 EPIP S023-VIII-43, " Sample Coordination during an Emergency."

2.8 EPIP S023-VIII-44, " Emergency Contamination Control."

7.9 EPIP S023-VIII-61, "Re-entry".

O

1 i

l AN ONOFRE NUCLEAR GENERATING STATION EMEPGENCY PROCEDURE S023-VIII-41 Page ?

REVISION O NITS 2 AND 3

'O PREREOUISITES 3.1 An emergency condition has been declared at San Onofre Nuclear Generating Station, as provided in the SONGS Unit 2 and 3 Emergency Plan, and the Emergency Coordinator (Health Physics Leader) or his designee has ordered one or more of the following:

3.1.1 Onsite monitoring (airborne release);

3.1.2 Emergency center or onsite assembly area monitoring;

-and- .

3.2 The Health Physics leader has detemined the general path of the plume and has provided monitoring team members with specific instructions on areas to survey, types of surveys, and requiremeats for protective clothing and respirators.

-and-3.3 Appropriate monitoring equipment is available in emergency kits and currently calibrated.

g,4.0 V PRECAUTIONS 4.1 Except where specifically identified, survey equipment and laboratory analysis will oe perfomed in accordance with existing health physics and chemistry procedures.

4.2 For radiological accidents which occur during nomal working hours, sufficient health physics personnel will be available to support general monitoring teams. During other times, it may only be possible to deploy one monitoring team. In these curcumstances, the Emergency Coordinator (or HPL if available) will assign priorities for radiological monitoring based on the known or expected extent and severity of the release or radiological conditions while calling in additional personnel.

4.3 Monitoring teams must remain alert to their own exposure and request relief if their cummulative exposure approaches a SONGS-1 administrative control level. Exposure limit extensions may be authorized in accordance with procedure S023-VIII-31, Emergency ,

Exposure Control". l l

4.4 Comunications between the monitoring team and emergency control personnel will be via SCE radio. Since radio comunications at this frequency can be in'.ercepted by comercially available scanners, all comunications related to reporting survey data

/3 must be brief and factual, and free of exclamatory or alaming O expressions. To the extent possibic, survey points should be referenced by map designator rather than the actual location.

A SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-41 V UNIiS 2 AND 3 REVISION O Page 3 4

- 4.0 PRECAUTIONS (continued) 4.5 Since implementation of proper protective actions onsite and offsite and subsequent reconstruction of the event requires

> accurate infomation, observe the following guidelines:

. 4.5.1 Carefully word data transmissions to the TSC to minimize possible confusion. In particular, avoid abbreviations (such as " mrem", which could be confused with " rem"). Use the complete word or unit, i.e., " millirem".

4.5.2 Clearly identify survey locations, using predesignated survey location numbers and map coordinates, and equipment / building names, as available.

4.5.3 Preface radio comunications with the title or name of the For examp receiving party and your title or name." SONGS-2 and Wait for3 TSC, this is N the receiving party to acknowledge prior to relaying any data. End the message with ar :ppropriate temination phrase. For example: ...NE monitoring team, out".

4.6 Accurately document all sury?y data. Ensure that units O ssociated ith the det. re cie r- tater the e te. ti e-instrument serial number (s), and name of the surveyor on all sur records.

(,

4.7 In general, ion chamber instruments should be used to measure dose rates; however, a Teletector may be used where high dose rates or location make it necessary.

4.8 Do not use a GM instrument (except Teletector) in a high level radiation field because the detector may saturate causing the instrument to erroneously read "zem" or below scale.

4.9 If an instrument malfunctions or " pegs" out during survey operations, imediately exit the area by the same route used to e'nter it, and obtain a new instrument if necessary. A malfunctioning instrument should be appropriately tagged.

4.10 Ensure that appmpriate protective clothing and equipment (e.g.

respirators) is worn by all members of the survey party. If there is a potential for high beta dose rates, use protective eyewear.

4.11 Exposures of personnel in the survey party shall be in accordance with SCE administrative control limits. Monitoring teams must remain alert to their own exposure and request relief if their cumulative exposures approach these levels. The Emergency g Coordinator may authorize exposure limit extentions, if necessary y (S023-VIII-31 ) . All exposures shall be maintained as low as reasonably achievable by employing the following methods or techniques:

2 EMERGENCY PROCEDURE S023-YIII-41

.Q SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 REVISION O Page 4 e 4.0 PRECAUTIONS 4.11 (continued) 4.11.1 Limit the number of personnel in the survey party to the minimum number necessary to perfom the survey in a safe and efficient manner.

4.11.2 If time is available, plan the survey in advance to

- ensure gathering a maximum amount of data in a minimum time period. Conduct a pre-survey briefing to insure all members of the party understand their tasks.

i 4.11.3 Ensure that the party has all equipment and supplies it needs, including survey maps and foms.

Pre-number swipes and take other measures to minimize 1

time in the radiation field.

4 1

4.11.4 Use extendable probe instruments (such as the Teletector) to minimize exposure when monitoring " hot spots" or hard to reach areas.

4.11.5 Use available equipment or structures as shielding when appropriate.

- 4.12 Alaming dosimeters should be considered in addition to high range self-reading dosimeters. -

5.0 CHECK-OFF LISTS 5.1 None 6.0 PROCEDURE 6.1 Report to the Health Physics Leader at the Technical Support Center for briefing.

6.2 Obtain appropriate monitoring equipment from the monitoring kit (s) located in the storage locations. Equipment selected will depend on the type of survey assigned. Obtain and re-zero assigned dosimeter, if applicable. Obtain applicable survey maps and emergency survey log sheets, etc.

6.3 Turn on instruments and allow for 2 minute wamup. Check instruments for proper response using a check source.

6.4 Obtain a portable radio transceiver and check operation before l

1 eating to start survey. Keep the radio operational at all times i while perfoming surveys in order to maintain communications with

! the Health Physics Leader or other TSC personnel.

l l

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-41 l

'O- UNITS 2 AND 3 REVISION O Page 5

,_ 6.0 PROCEDURE (continued)

NOTE: The next three major sections of this procedure are as follows:

Section S.5, "In-Plant Monitcring," provides instructions and guidance for Monitoring Out-of-Plant monitoring w",ithin SONGS Unit 1; Section 6.6, applies to onsi of SONGS Unit 2 and 3; and Section 6.7, " Airborne Radioactivity Monitoring," applies to monitoring done either in-plant (6.5) or !

out-of-plant (6.6) .

6.5 In-Plant Monitoring 6.5.1 If the Health Physics Leader so directs, or if substantial airborne activity or contamination is suspected, or as mandated by cognizant REP (s), don protective clothing and/or respirators, as appropriate. Avcid the unnecessary use of respirators and protective clothing.

6.5.2 While enroute to the assigned survey location, and at any other time while moving about the plant, have the survey instrument turned on (with the beta window open, if applicable). Frequently observe the survey meter and O re' ort re dia9s to the "ea'th enssics ' der- a cord abnomal readings or other readings have special

, significance.

(

NOTE: If observed dose rates significantly exceed those to be expected, innediately notify the Health Physics Leader, then proceed with survey cnless otherwise directed.

6.5.3 Upon arriving at survey location, approach with caution and continue to monitor dose rates frequently as above. Take swipes and air samples as approgriate. Record general area dose rates and any significant hot spots" encountered.

6 General area dose rates should be conducted as follows:

.1 Open the beta shield (if applicable).

i .2 Hold the instrument probe about 3 feet (wai t height) above the ground and position for a maximum reading.

! .3 Take a reading. Allow sufficient time for the meter to stabilize. Document the reading.

NOTE: The type and extent of the survey will depend upon the nature of radiological conditions and the instructions given at the briefing.

lO

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-41 REVISION O Page 6 UNITS 2 AND 3 1

- 6.0 PROCEDURE (continued) 6.6 Out-Of-Plant Monitoring 6.6.1 If the monitoring is to be perfomed outside of the security fence, leave the station via the Security Processing Facility exit. Retain your film and dosimeter (s) while perfoming radiological monitoring.

6.6.2 Obtain an SCE vehicle, if available. Othemise, use any available privately-owned vehicle. There should be at 1 east 1/2 tank of gas. Obtain another vehicle if necessary l'

and practicable.

6.6.3 If the Health Physics Leader so directs, or if substantial airborne activity or contamination is suspected, don protective clothing and/or respirators, as appropriate.

Avoid the unnecessary use of respirators and protective clothing. If observed dose rates exceed 10 millirem per l

hour while monitoring out of doors, evacuate the area and/or seek shelter, unless othemise directed by the Health Physics Leader.

e.e.4 eerro m me suremeats ssisaed by the seaith ehrsics 'e der O as follows:

.1 Moving Dose Rate Monitoring

.1.1 Whila enroute to the first assigned monitoring location, and at any other time while moving about the site, have the survey instrument turned on, with the beta window open. Frequently observe the survey meter and report readings to the Health Physics '

le ader. If a level of 1.0 millirem per hour or greater is observed, imediately notify the Health Physics Leader.

(

.1.2 Take occasional beta-gama (beta-window open) readings with the instrument probe extended through an open vehicle window. Note and record any readings significantly higher than the average and document them.

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EMERGENCY PROCEDURE S023-VIII-41 l c SAN ONOFRE NUCLEAR GENERATING STATION REVISION O Page 7 l

\ UNITS 2 AND 3 l

7 6.0 PROCEDURE i

5.6.4 (continued)

. 2 Stationary Dose Rate Monitoring

. 2.1 Open the beta shield.

2.2 Hold the instrument probe about 3 feet (waist height) above the ground and position for a maximum reading.

1

. 2.3 Take a reading. Allow sufficient time for the meter to stabilize. Document the reading.

. 2.4 Nove the instnJment probe to about three inches above the ground and take another reading. Document the reading.

NOTE: The type and extent of the survey will depend upon the naturc of radiological conditions and the instructions given at the briefing.

6.7 Airborne Radioactivity Monitoring O NOTE: This section may apply to both in-plant monitoring (section 6.5) and out-of-plant monitoring (Section 6.6).

I 6.7.1 Place a clean particulate filter and a silver zeolite cartridge in the air sampler. The filters are installed such that the air flow passes through the particulate

" filter first.

NOTE: The HPL may change the sample volume from 10 ft 3 to another volume consistent with radiological conditions.

6.7.2 Record the sample flow rate, in efm, on thE survey f,onn.

On the DC pwered samplers, this is nonna11y 10 ft .

' Calculate the time necessary to obtain a 10 ft b sample.

' Sample Time, (minutes) = 10f t3 l Sampler Flow Rate, (cfm) 6.7.3 Position or hold the sampler such that the intake is neither touching nor in close proximity to potentially contaminated surfaces. Connect the sampler to the power supply, or for 12 VDC samplers, to the battery of the vehicle. Keep the engine running when drawing power from the vehicle battery.

O

' 6.7.4 Turn the sarpler on and record the sample start time on an

Air Sample Record Card (see Attachment 8.2).

N"pl$Nf $n (Ec b e Samh 'e"skhp kNm on Y b Sample Record Card.

I a '

n SAN ONOFRE NUCLEAR GENERK'ING STATION EMERGENCY PROCEDURE S023-VIII-41 Page 8 lD 4

UNITS 2 AND 3 REVISION O l i

e 6.0 PROCEDURE 6.7 (continued) l 6.7.6 Remove the filter and cartridge from the sampler.

6.7.7 Count each filter cartridge separately, using a G-M count rate instrument with a thin window detector for filters and a SAM 2 or equivalent for cartridges. Place the filter / cartridge on a clean surface and position the detector about one-half centimeter away from the j filter / cartridge.

NOTE: See appropriate SONGS-2 and 3 Health Physics procedure for SAM-2 operating instructions.

NOTE: If the GM instrument has a RESPONSE control, insure that it is set for the slowest response. This is necessary to i maintain an adequate minimum detectable count rate (MDCR).

The MDCR for typical background count rates and instrument response times are listed in Attachment 8.3. If the I background exceeds the highest background in Attachment 8.3, move to a location with a lower background.

O 6.7.8 Record readings, location, and time on the survey fom.

6.7.9 Report any radioiodine sample which exceeds 100 cpm above background to the HPL.

\'

6.7.10 Place the samples in a plastic bag with the Air Sample Record Card. At the end of the survey, return all samples and survey fomsAnaps to the Station, or to another location designated by the PHL for laboratory counting.

l 6.7.11 After all of the required data has been collected at the first survey location, establish radio contact with the HPL and report the following data:

.1 Survey location and time.

.2 Air sample volume.

.3 Background count rate.

.4 Gross counts for the particulate sample.

.5 Gross counts for the radioiodine cartridge (Identify if other than silver zeolite). j O s ^ver se 3 - foot ( eist hisa) reedias. i

.7 Radiation readings taken between survey points.

l I . _ _ _ . _ _ . _ _

ENERGENCY PROCEDURE S023-VIII-41 O SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 REVISION O Page 9 7

6.0 PROCEDURE 6.7 (continued) 6.7.12 Proceed to the next monitoring point and repeat for each monitoring location.

6.8 After all of the required data has been collected at the first monitoring point, establish radio contact with the Health Physics Leader and report all data.

4 6.9 Proceed to subsequent monitoring points and repeat appropriate steps.

6.10 Periodically, read pocket dosimeters of the entire monitoring team. Report these readings to the Health Physics leader at least every 30 minutes, or when accumulated exposure to any individual reaches 100 mrem.

6.11 After reporting the data from the last monitoring point, request l

further instructions from the HPL.

6.12 Other Monitoring O The basic monitoring for alpha contamination, neutron exposure

- rate, and surface contamination will be conducted using the 4

general methods established in SONGS Unit 2 and 3 Health Physics Procedures.

I s

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EMERGENCY PROCEDURE S023-VIII-41

,] SAN ONOFRE NUCLEAR GENERATING STATION CIITS 2 AND 3 REVISION O Page 10

,.- 7.0 RECORDS 7.1 Forward the results of all radiation monitoring and subsequent actions to the Administrative Leader.

8.0 ATTACMENTS

8.1 Emergency Radiological Survey Record 8.2 Air Sample Record Card

8. 3 Miniumum Detectable Count Rates J. L K. P. BARR HEALTH PHYSICS MANAGER t

TC:0108F/ge l

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i SAN ONOFE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-41

' 'O UNITS 2 AND 3 REVISION O ATTAC MENT 8.1 Page 1 of 1 1

' EMERGENCY RADIOLOGICAL SURVEY RECORD

, l DISTANCE: S ;

- LOCATION: ONSITE SURVEY ROUTE:

l MILES DATE:

1 0FFSITE 10 MILES l

INSTRUMENT TYPES & ID NOS: TEAM i LEADER i

l l ULUdtU j AIR WINDOW SAWLE AIR SAPPLE COUNT RATES CARTRIDGE O TYPE SuRvEv RExoING v0tuME iKGo raRTICul*TE IOoINE _

(cpm) GROSS (cpm) GROSS (cpm)

TIME (mR/hr) (ft3) C

( POINT SZ REMARKS l

i 1

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l SAN ONOFE NUCLEAR GENERATING S'TATION EMfRGENCY PROCEDURE S023-VIII-41 REVISION O Page 1 of 1 UNITS 2 AND 3 ATTACMENT 8.2 ,

AIR SAMPLE RECORD CARD Air Sample Location:

Date: , Surveyor:

Sampler ID No.:

Sampler Flow Rate: cfm Sample Start Time: 5 top Time:

Sample Time:

l mig.

Sample Volume: ft O

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n EMERGENCY PROCEDURE S023-VIII-41

.[] SAN ONOFE NUCLEAR GENERATING STATION UNITS 2 AND 3 REVISION O ATTACtNENT 8.3 Page 1 of 1 MINIMUM DETECTABLE COUNT RATES s

MDCR (com) l Response Time Background (cpm) 2 sec 5 see 10 sec 100 180 115 80 200 255 165 11 5 500 405 255 180 570 360 255 1000 3

700 445 31 5 1500 2000 81 0 51 0 360

- 2500 905 570 405 3000 990 625 445 3500 675 480 J 4000 725 51 0 4500 765 545 5000 81 0 570 O 7500 10000 990 700 81 0 15000 990 1

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D SAN ONOFRE Nt! CLEAR GENERATING STATION E.ERGENCY W

UNITS 2 AND 3 8 . j

$: O OFFSITE MONITORING AND SAMPLING CDIA b ce + -= ". eh !*

e es t,= r .c

.a [= ;[ >

,, (;d 1.0 OBJECTIVE k bs = L E* b ' -

1.1 This procedure provides instructions and guidance for conducting offsite radiological monitoring and sampling for accident assessment purposes during an emergency.

1.2 Assigned Health Physics Technicians are responsible for implementation of this procedure.

2.0 REFERENCES

2.1 NUREG-0654, Rev.1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

2. 2 San Onofre Nuclear Generating Station Units 2 and 3 Emergency Plan.

2.3 SONGS -2 and 3 Health Physics Procedures.

2.4 EPIP 5023-VIII-25, " Direction of Offsite Emergency Monitoring."

2.5 EPIP S023-VIII-31, " Emergency Exposure Control".

2.6 EPIP S023-VIII-36, " Thyroid Prophylaxis."

2.7 EPIP S023-VIII-43, " Sample Coordination during an Emergency."

O l

OAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0?3-VIII-42 PAGE 2 UNITS 2 AND 3 NEW I

/0 PRERE0VISITES 3.1 An emergency condition has been declared at San Onofre Nuclear Generating Station, as provided in the SONGS Units 2 and 3 Emergency Plan, and the Emergency Coordinator (Health Physics Leader) or his designee has ordered one or both of the following:

3.1.1 Offsite monitoring (airborne release);

3.1.2 Offsite Emergency Center or onsite Assembly Area monitoring;

-and-3.2 Emergency control personnel have detemined the general path of the plume and have provided monitoring team members with specific instructions on areas to survey, types of surveys, and requirements for protective clothing and respirators.

-and-3.3 Apprcpriate monitoring equipment is available in emergency kits, operable end currently calibrated.

4.0 PRECAUTIONS i 4.1 Except where specifically identified, survey equipment. operation and laboratory analysis will be perfomed in accordance with existing health physics and chemistry procedures.

4.2 For radiological accidents which occur during nomal working hours, sufficient health physics personnel will be available to support general monitoring teams. During other . times, it may only be possible to deploy one monitoring team. In these curcum tances, the Emergency Ceordinator (or HPL if available) will assign priorities for radiological monitoring based on the known or expected extent and severity of the release or radiological conditions while calling in additional personnel.

4.3 Monitoring teams must remain alert to their own exposure and request relief if their cummulative exposure approaches a SONGS-2 and 3 administrative control level. Exposure limit extensions may be authorized in accordance with procedure S023-VIII-31,

" EMERGENCY EXPOSURE CONTROL".

A.4 Comunications between the monitoring team and emergency control personnel will be via SCE radio. Since radio communications at this frequency can be intercepted by comercially available scanners, all comunications related to reporting survey data must be brief and factual, and free of exclamatory or alaming O expressions. To the extent possible, survey points should be referenced by map designator rather than the actual location.

l

l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-42 '

\ UNITS 2 AND 3 NEW P AGE 3 g 4.0 PRECAUTIONS (continued) l 4.5 Since implementation of proper protective actions unsite and l 1

offsite and subsequent reconstruction of the event requires '

accurate infomation, observe the following guidelines:

4.5.1 Carefully word data transmissions to the TSC to minimize possible confusion. In particular, avoid abbreviations (such as " mrem", which could be confused with " rem"). Use the complete word or unit, i.e., " millirem".

4.5.2 Clearly identify survey locations, using predesignated survey location numbers and map coordinates, and equipment / building names, as available.

4.5.3 Preface radio comunications with the title or name of the For examp receiving party and your title or name." SONGS-2 Waitand for 3 TSC, this is N the receiving party to acknowledge prior to relaying any data. End the message" with an aparopriate temination phrase. For example: ...NE monitoring team, out".

4.6 Accurately document all survey data. Ensure that units i

O essoci tea with the det. re cie r. cater the eate. time.

instrument serial number (s), and name of the surveyor on all survey records.

4.7 In general, ion chamber instruments should be used to measure dose rates; however, a Teletector may be used where high dose

! rates or location make it necessary.

' 4.8 Do not use a GM instrument (except Teletector) in a high level

! radiation field because the detector may saturate causing the instrument to erroneously read "zero" or below scale.

4.9 If an instrument malfunctions or " pegs" out during survey operations, immediately exit the area by the same route used to enter it, and obtain a new instrument if necessary. A

! malfunctioning instrument should be appropriately tagged.

4.10 Ensure that appropriate protective clothing and equipment (e.g.

respirators) is worn by all members of the survey party. If there is a potential for high beta dose rates, use protective eyewear.

l 4.11 All exposures shall be maintained as low as reasonably achievable by employing the following methods or techniques:

O l

t. .

i catastact eaoctouat so23-vttt-42 O sa" o"orat auc't^a Stata^'two s'atto" UNITS 2 AND 3 NEW PAGE 4

,, 4.0 PRECAUTIONS 4.11 (continued) 4.11.1 Limit the number of personnel in the survey party to the minimum number necessary to perfom the survey in a safe and efficient manner.

4.11.2 If time is available, plan the survey in advance to ensure gathering a maximum amount of data in a minimum time period. Conduct a briefing to ensure all members of the party understand their tasks.

4.11.3 Ensure that the party has all equipment and supplies it needs, including survey maps and foms.

Pre-number swipes and take other measures to minimize time in the radiation field.

4.11.4 Use extendable probe instruments (such as the Teletector) to minimize exposure when monitoring " hot spots" or hard to reach areas.

N 4.11.5 Use available equipment or structures as shielding s when appropriate.

4.12 Alaming dosimeters should be considered in addition to high 1

range self-reading dosimeters.

5.0 CHECK-OFF LISTS 5.1 None 6.0 PROCEDURE 6.1 Report to the Health Physics leader at the Technical Support Center for briefing.

6.2 Obtain appropriate monitoring equipment frer the monitorir g kit (s) located in the storage locations. EqAprett selectt d will depend on the type of survey assigned. Obtain and re-zero applicable. Obtain applicable survey maps assigned an dosimeter, mergency survey i{og sheets, etc 6.3 Turn on instruments and allow for 2 minute wamup. Check instruments for proper response using a check source.

6.4 Obtain a portable radio trr.nsceiver and check operation before leaving to start survey. Keep the radio operational at all times while perfoming surveys in order to maintain comunications with p>

s.

the Health Physics Leader or otner TSC personnel.

4 ratectacv eaoctouat so23-vitt-42 Osa" o"orat auc'tra atura^Ttwo statto" UNITS 2 AND 3 NEW PAGE 5 d .0 PROCEDURE (continued)

NOTE: The next two major sections of this procedure are as follows:

Section 6.5, "Offsite Dose Rate Monitoring".

Section 6.6, "Offsite Airborne Radioactivity Monitoring" These two sections and the collection of samples for later analysis should be executed concurrently as appropriate.

6.5 Offsite Dose Rate Mcr.itoring 6.5.1 Retain your film badge (s) and dosimeter (s) while perfoming offsite radiological monitoring.

6.5.2 Obtain an SCE vehicle, if available. Othemise, use any available privately-owned vehicle. There should be at least 1/2 tank of gas. Obtain another vehicle 'f necessary and practicable.

6.5.3 If the Health Physics Leader so directs, or if substantial airborne activity or contamination is suspected, or as O mandated by cognizant REP (s), don protective clothing V and/or respirators, as appropriate. Avoid the unnecessary use of respirators and protective clothing'. If observed

(

dose rates exceed 10 millirem per hour while monitoring out of doors, evacuate the area and/or seek shelter, unless othemise directed by the Health Physics leader.

6.5.4 Perfom measurements assigned by the Health Physics Leader as follows:

.1 Moving Dose Rate Monitoring

.1.1 While enroute to the first assigned monitoring location, and at any other time while moving about the site, have the survey instrument turned on, with the beta window open. Frequently observe the survey meter and report readings to the Health Physics Leader. If a level of 1.0 millirem per hour or greater is observed, immediately notify the Health Physics leader.

.1. 2 Take occasional beta-gamma (beta-window open) readings with the instrument probe extended through an open vehicle window. Note and record any readings significantly higher than the average and document them.

O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-42 f)V UNITS 2 AND 3 NEW PAGE 6 e 6.0 PROCEDURE 6.5.4 (continued)

.2 Stationaiy Dose Rate Monitoring

.2.1 Open the beta shield.

.2.2 Hold the instrument probe about 3 feet (waist height) above the ground anc position for a maximum reading.

.2.3 Take a reading. Allow sufficient time for the meter to stabilize. Doctanent the reading.

.2.4 Move the instrument probe to about three inches above the ground and take another reeding. Document the reading.

NOTE: The type and extent of the survey will depend upon the nature of radiological conditions and the instructions given at the briefing.

6.6 Offsite Airborne Radioactivity Monitoring 6.6.1 Place a clean particulate filter and a silver zeolite cartridge in the air sampler. The filters are installed 4

such that the air flow passes through the particulate filter first.

6.6.2 The HPL may change the sample volume from 10 ft 3 to another volume consistent with radiological conditions.

6.6.3 Record the sample flow rate, in cfm on the survey {om.

On the DC powered samplers, this is noma 11y 10 ft .

Calculate the time necessary to obtain a 10 ftS sample.

Sample Time, (minutes) = 10f t3 Sampler Flow Rate, (cfm) 6.6.4 Position or hold the sampler such that the intake is neither touching nor in close proximity to potentially contaminated surfaces. Connect the sampler to the power supply, or for 12 VDC samplers, to the battery of the vehicle. Keep the engine running when drawing power from the vehicle battery.

6.6.5 Turn the sampler on and record the sample start time on an Air Sample Record Card (see Attachment 8.2).

l'eN*aNecohd e Samh*e"sYop kN6n Y$ b Sample Record Card.

EMERGENCY PROCEDURE 5023-VIII-42 O SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 NEW PAGE 7 6.0 PROCEDURE 7

6.6 (continued) 6.6.7 Remove the filter and cartridge from the sampler.

6.6.8 Count each filter cartridge separately, using a G-M count rate instrument with a thin window deter. tor for filters and a SAM 2 or equivalent for cartridges. Place the filter / cartridge on a clean surface and position the detector about one-half centimeter away from the filter / cartridge.

NOTE: See appropriate SONGS-2 and 3 Health Physics procedure for SAM-2 operating instructions.

NOTE: If the GM instrument has a RESPONSE control, ensure that it is set for the slowest response. This is necessary to maintain an adequate minimum detectable count rate (MDCR).

The MDCR for typical background count rates and instrument response times are listed in Attachment 8.3. If the background exceeds the highest background in Attachment 8.3, move to a location with a lower background.

f.6.9 Record readings, location, and time on the survey fom.

! 6.6.10 Report any radioiodine sample which exceeds 100 cpm above background to the HPL.

6.7.11 Place the samples in a plastic bag with the Air Sample Record Card. At the end of the survey, return all samples and survey fomsAnaps to the Station, or to another location designated by the HPL for laboratory counting.

6.7.12 After all of the required data has been collected at the first survey location, establish radio contact with the HPL and report the following data:

.1 Survey location and time.

.2 Ai r sample volume.

.3 Background count rate.

.4 Gross counts for the particulate sample.

.5 Gross counts for the radioiodine cartridge (Identify if other than silver zeolite).

O .6 Average 3 - foot (waist high) reading.

.7 Radiation readings taken between survey points.

l

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-EMERGENCY PROCEDURE S023-VIII-42 4

-() SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 NEW PAGE 8 i

6.0 PROCEDURE (continued) r-6.7 Collect requested samples for later analysis.

6.8 After all of the required data has been collected at the first monitoring point, establish radio contact with the Health Physics Leader and report all data.

4 6.9 Proceed to subsequent monitoring points and repeat appropriate steps.

I 6.10 Periodically, read pocket dosimeters of the entire monitoring team. Report these readings to the Health Physics Leader at 1 east every 30 minutes, or when accumulated exposure to any l

individual reaches 100 mrem.

6.11 After reporting the data from the last monitoring point, request further instructions from the HPL. .

I 6.12 Other Monitoring 1'

The basic monitoring for alpha contamination, neutron exposure rate, and surface contamination will be conducted using the l

j v O general methods established in SONGS Units 2 and 3 Health Physics Procedures.

7.0 RECORDS 7.1 Forward the results of all radiation monitoring and subsequent j

actions to the Administrative Leader.

8.0 ATTACHMENTS 8.1 Emergency Radiological Survey Record 8.2 Air Sample Record Card 8.3 Miniumum Detectable Count Rates K. P. B ARR HEALTH PHYSICS MANAGER

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, SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-42 NEW PAGE 2 UNITS 2 AND 3 ATTAC MENT 8.2 1

AIR SAMPLE RECORD CARD Air Sample Location:

Date: Surveyor:

1 Sampler ID No.:

Sampler Flow Rate: cfm Sample Start Time: stop lime:

Sample Time: mig.

Sample Volume: ft O

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l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-42

'O V UNITS 2 AND 3 NEW PAGE 3

' ATTAC MENT 8.3 4

I MINIMUM DETECTABLE COUNT RATES 4

MDCR (cpm)

Response Time Background (cpm) 2 sec 5 see 10 sec 100 180 115 80 200 255 165 115 500 405 255 180 O iooo 1500 57o 700 3so 445 -

255 31 5 2000 81 0 51 0 360

( 2500 905 570 405 3000 990 625 445 4 3500 675 480 4000 725 51 0 4500 765 545 i 5000 81 0 570 7500 990 700 10000 81 0 15000 990 0097F/ge O

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-43 e^GE 1 O Units 2aa c rv'ston e< g ,

NOWOR CONSTRUcil W

. SAMPLE COORDINATION D JRING tE D7,gp , 47 i ABLE CONTR 5n 1.0 OBJECTIVF STICK FILL - _FOR CUHRENT INp R This procedure establishes a means for coordination and tracking AfD' during an emergency. This procedure allows for the appointment of a Sample Coordinator, establishes ar. Emergency Sample Log, and provides guidelines for sample priorities. The Chemistry Leader is responsible for the implementation of this procedure. .,

2.0 REFERENCES

2.1 NUREG - 0654, Rev.1. Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2 San Onofre Nuclear Generating Station, Units 2 & 3 Emergency Plan 3.0 PREREQUISITES 3.1 An emergency condition has been declared at San Onofre Nuclear Generating Station, Units 2 & 3.

' 3.2 Due to radiological conditions, a greater than normal volume of samples are being processed.

3.3 The Chemistry Leader or his designee, has appointed a Sample Coordi-nator.

3.4 The Sample Coordinator should be familiar with routine chemistry and Health Physics procedures, and Emergency procedures associated with sampling and analysis.

4.0 PRECAUTIONS 4.1 Personnel Exposures shall be in accordance with Emergency Procedure 5023-VIII-31, " Emergency Exposure Control".

4.2 Personnel Exposures related to transporting, handling and analysis should be maintained as low as is reasonably achievable.

5.0 CHECK-0FFLIFJS, 5.1 Sample Coordination Checklist (Attachment 8.1) 6.0 PROCEDURE 6.1 The Sample Coordinator shall inititate an Emergency Sample Log (Attach-ment 8.3) and ensure that all sampler and analytical results are properly Q logged.

EMERGENCY PROCEDURE S023-VIII-43 SAN ON0FRE NUCLEAR GENERATING STATION PAGE 2 REVISION NEW UNITS 2 & 3 r

6.0 PROCEDURE (Cont'd) 6.2 The Sample Coordinator shall assign a sequential sample number and a numerical priority number to each sample (if not already assigned) in accordance with Section 6.4 of this procedure.

6.3 The Sample Coordinator may request the Health Physics Leader / Chemistry Leader to provide the appropriate quantities of the following resources as are necessary to carry out his/her duties:

0.3.1 Clerical support 6.3.2 Sample " runners" 6.3.3 Transportation as necessary and available.

6.4 The Sample Coordinator shall assign a priority number of each sample if one has not already been assigned by the Chemistry Leader or an p appropriate member of the Technical Support Center (TSC) staff.

Attachment 8.2 of this procedure, " Guidelines for Assignment of Sample

, V Priority", shall be consulted to accomplish this, NOTE: The priority number assigned a given sample shall govern the urgency with which the sample is logged and transmitted, analyzed and the results returned to the originator.

Priority "1" samples should be logged, trans-mitted and analyzed immediately, and the results returned to the originator as ex-peditiously as possible.

6.5 Attachment 8.3 provides the fonnat for the Emergency Sample Log.

7.0 RECORDS Forward all records to the Administrative Leader after review.

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EMERGENCY PROCEDURE S023-VIII-43 i ,, SAN ON0FRE NUCLEAR GEiiERATING STATION REVISION NEW PAGE 3 i UNITS 2 & 3 1

i r-t 8.0 ATTACHMENTS i

l 8.1 Sample Coordination Checklist i

i 8.2 Guidelines For Assignment of Sample Priority 1

! -8.3 Emergency Sample Log Fonnat i

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n EMERGENCY PROCEDURE S023-VIII-43

'( )) SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 REVISION NEW ATTACHMENT 8.1 PAGE 1 0F 1

/-

1 SAMPLE COORDINATION CHECKLIST t

Initials i

l 1. Emergency Sample Log instituted.

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[ 2. All samples assigned sample and priority numbers.

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Af ter this checklist is completed it should be submitted to the Administrative Leader.

Emergency Sample Coordinator.

iO i Emergency Sample Log Completed: Hours Date:

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Reviewed By: Date: !

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' Chemistry Leader I

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-O saa oaorar auc' tan coaca^Tras STATroa UNITS 2 & 3 REVISION NEW ATTACHMENT 8.2 PAGE 1 0F 1 r

GUIDELINES FOR ASSIGNMENT OF SAMPLE PRIORITY

PRIORITY EXAMPLE 1 a. Post-Accident Assessment

b. Samples in support of accident mitigation operations or affecting personnel safety.

2 a. Post-Accident Surveillance

b. Samples in support of recovery operations.

3 a. Routine Surveillance

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The Chemistry Leader or his representative may assign priority numbers as conditions dictate; however, the Sampler Coordinator should attempi to follow these guidelines if the priority has not already been assigned.

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[MJRGENCY-SAMPLELOGFORMAT t

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' EMERGENCY PROCEDURE 5023-VIII-43 SAN ONOFRE NUCLEAR GENERATING STATION ATTACHMENT 8.3 REVISION NEW UNITS 2 & 3 PAGE 2 0F 2 EMERGENCY SAMPLE LOG FORMAT RESULTS RESULTS SAMPLE RECEIVED RESULTS XMIT SAMPLE XMIT DATE INITIALS INITIALS TIME DATE XMIT TO TIME XMIT TO TIME DATE O

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SAN ONOFRE NUCLEAR GENERATING STATI0f ll@GESR g8MgiggCTgVIII-44 PAGE 1 UNITS 2 & 3 ggfgg gg(y CRECK APPUCABLE CONYM5pf EC '

EMERGENCY C(WHIKAHKfDRMLIRRENT litf0$l1AiT{g#

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1.0 OBJECTIVE This procedure provides contamination control guidelines for emergency conditions, to minimize the spread of contamination during an emergency, and provide methods to identify and handle contaminated personnel.

The Health Physics staff is responsible for implementation of this pro-cedure. , , 7, q ,

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2.0 REFERENCES

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2.1 NUREG-0654, Rev.1. Criteria fer Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2 San Onofre Nuclear Generating Station, Units 2 & 3. Emergency Plan

(] 2.3 Health Physics Procedure 5023-VII-1.0, " Health Physics Manual" 2.4 Health Physics Procedure 5023-VII-4.2, " Bioassay Program" i.

2.5 Health Physics Procedure 5023-VII-4.4, " Personnel Decontamination" 2.6 Health Physics Procedure' S023-VII-7.2, " Airborne Radioactivity Surveys (Non-Routine)"

2.7 Health Physics Procedure 5023-VII-7.3, " Contamination Surveys" 2.8 Health Physics Procedure 5023-VII-7.4, " Radiation Surveys" 3.0 PREREQUISITES 3.1 An emergency condition has been declared at San Onofre Nuclear Generating Station, Units 2 & 3.

3.2 A release of radioactive material has occured which has caused significant levels of radioactive contamination.

3.3 There is reason to suspect personnel contamination has occured.

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i/s-~) SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-44 PAGE 2 UNITS 2 & 3 REVISION NEW 4.0 PRECAUTIONS 4.1 Personnel entering a contaminated area must be properly attired in protective clothing and respiratory protection in accordance with Health Physics Procedure S023-VII-1.0, " Health Physics Manual".

4.2 Medical treatment /First Aid to seriously injured individuals always takes priority over contamination control measures.

4.3 Definitive detection of inhalation or ingestion of rcdioactive material depends on positive results of either whole body ccunting or excreta

! analysis.

4.4 The Health Physics Group is responsible for controlling all food and water supplies at the plant during an emergency. Whenever an evacu-ation due to radiological conditions takes place, all food and water supplies within the evacuated area will be considered contaminated and measures will be taken to prevent their use.

4.5 Before any water or food may be consumed, the Health Physics Group must (s_)j verify that the water / food itself and the eating surfaces hre below emergency contamination guidelines for personnel (Attachment 8.1).

Random samples of food / water shall be analyzed for low level contamin-ation on a periodic basis.

5.0 CHECK-OFF LISTS 5.1 Contamination Control Checklist Spills and Releases (Attachment 8.2) 6.0 PROCEDURE 6.1 Contamination Control 6.1.1 It may become necessary to extend the boundaries of the con-trolled area. Appropriate access control and associated core taminattan control measures shall be established for any area in which contamination exists at levels higher than that specified for a clean area in the Health Physics Manual.

(Reference 2.3) 6.1.2 Personnel and equipment monitoring and release procedures shall remain in force to the extent possible. There may be exceptions applicable to emergency cunditions as follows:

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EMERGENCY PROCEDURE S023-VIII-44 "d SAN ONUFRE NUCLEAR GENERATING STATION REVISION NEW PAGE 3 UNITS 2 & 3 6.0 PROCEDURE (Cont'd) 6.1.2.1 If background dose rates at homal monitoring locations preclude detection of levals of contamination equivalent to the clean limit, monitoring locations shall be moved to a location where this can be done. However, if signi-ficant levels of contamination exist, it may be appropriate to perform a gross screening at the exit of highly contamin-ated areas, ft,11 owed by a more complete monitoring at a suitable location.

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.2 If dose rates (or other life threatening factors) within the contaminated area (or contro11ad area) warrant an im-mediate evacuation, personnel monitoring shall not be re-quired prior to evacuation. If possible, personnel exiting such areas should remove any clothing thought to be con-taminated, or don clean coveralls to minimize the spread of potential contamination, pending subsequent monitoring. In this case, appropriate monitoring should be performed at the desi9aated Asse; bis area.

O-i .3 Contamination limits for release of personnel, equipment, and areas, as specified in the Health Physics procedures, shall remain in effect to the maximum extent possible. The Health Physics Leader will determine when a change in contamination limits is applicable and will establish appropriate revised limits.

6.1.3 The conditions under which a Site evacuation would be initiated might involve sigr.ificant releases with resultant contamination of environmental surfaces offsite. Under these conditions, delaying site evacuation to monitor and/or decontaminate per-sonnel or vehicles would be inconsistent with maintaining i

exposures As low As Reasonably Achievable, and may be super-fluous in light of the potential for recontamination offsite.

The following procedures should be used:

.1 Personnel should be directed to the remote Assembly Area for monitoring.

> .2 If the Assembly Area is within sectors from which the population is being evacuated, the Emergency Coordinator, in cooperation with SCE management and State and county agencies, shall design-ate an Assembly Area at which personnel monitoring will be per-formed. In this event, personnel and vehicles will be monitored p the same as members of the general public in accordance with the d emergency plans of the affected jurisdictions.

o b SAN ONOFM NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0?3-VIII-44 REVISION NEW PAGE 4 UNITS 2 & 3 6.0 PROCEDURE (Cont'd) 6.1.3.3 For rescue efforts in which there is a potential for the imminent death of the victim, and for which the magnitude of radiological conditions in the affected area are generally known, one or two emergency squad members should proceed to the scene without protective clothing to assess the situation and render first aid. Other members of the emergency squad should don appropriate protective clothing and proceed to the area to assist. The initial emergency squad member (s) should leave the area and be monitored and/or decontaminated as soon as possible.

.4 For fire fighting efforts, normal fire fighting equipment (helmets, coats, boots, gloves, etc.) may take the place of protective ciothing. This apparel is as likely to provide protection from contaminated water spray as protective clothing.

6.2 Radioactive Spill or Release 6.2.1 If possible to do so in a safe manner, take immediate steps to terminate the spill or re M ase.

g Take steps to mitigate the consequence of the spill or release, e.g., perform the following actions as appropriate:

.1 Infom others in the area.

.2 Secure ventilation

.3 Infom the Health Physics Leader or Emerg:ncy Coordinator in l

his absence.

.4 Contain the contaminated area by barricading, closing doors, etc.

6.2.2 Don protective clothing and respiratory equipment as necessary.

NOTE: If personnal were contaminated or are suspected to be, and must be moved, consider donning clean, pro-tective clothing to contain the contamination.

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r 6.0 PROCEDURE (Cont'd) 6.2.3 Monitor the area to detemine the extent of the contamination spread. Smear and radiation / airborne surveys should be in accordance with Health Physics Procedures, 5023-VII-7.2, 7.3 and 7.4. (References 2.6 through 2.8) 6.2.4 Infom the Health Physics Leader of the local radiological conditions.

6.2.5 Properly barricade and post the area in ac.:ordance with nomal plant procedures and the guidelines in Attachment 8.1. Infom the Health Physics Leader when done and await further instruc-tions.

6.3 Contaminated Personnel __

6.3.1 Monitor personnel suspected of being contaminated as follows:

O 1 ouictis survey the eatire body of subsect. 4ac,uaia9 ciotaia9 with Geiger-Mueller and/or alpha detectors.

f .2 If radioactivity is found, remove subject's clothing and re-survey entire body.

.3 Mark contaminated areas and take care not to spread contamin-ation. Record the highest reading found and the size of con-taminated area for later skin dose calculations. (See Attach-ment 8.3)

. .4 In the case of suspected alpha contamination, take filter paper smears of representative areas and count.

.5 Special care should be taken to survey areas under the finger-nails, ear lobes and between skin folds (i.e., am pits, but-tocks, between toes) if individual has already showered.

.6 The ein is considered to be contaminated, if any radioaccivity is found. However, the guidelines in Attachment 8.1 may be used in emergency conditions.

6.3.2 If skin is contaminated to levels greater than the guidelines in Attachment 8.1, initiate personnel decontamination efforts in accordance with Health Physics Procedure S023-VII-4.4.

q (Reference 2.5) b

SAN ONOFRE N3 CLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-44 REVISION NEW PAGE 6 UNITS 2 & 3 6.0 PROCEDURE (Cont'd) 6.3.3 If inhalation of radioactive material is suspected, deter-mine if the individual is a potential inhalation case as follows:

.1 A history of possible exposure to airborne contamination, whether the employee was or was not using respiratory protective equipment, places him in the group of " potential inhalation cases".

.2 A positive Geiger-Mueller or alpha survey or a positive smear survey in the area of the nose and mouth places the employee in the category of " potential inhalation cases".

.3 Smear sterile moistened cotton tipped applicator gently about the openings of the nose (not deep in the nose) and then count.

Detectable contamination places the incividual in the category of a " potential inhalation case".

.4 All persons considered as " potential inhalation cases" will

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be analyzed in accordance with Health Physics Procedure S023-VII-4.2. (Reference 2.4) 6.3.4 If ingestion of radioactive materials is suspected, detennine if the individual is a potential ingestion case as follows:

.1 A positive Geiger-Mueller or alpha survey or a positive smear survey in the area of the mouth places an individual in the group of potential ingestion cases.

.2 Smear a sterile cotton tipped applicator within the mouth and count. Also, have the individual gargle with one ounce of water for 30 seconds, collect water and count. A positive result from either sample places an individual in the group 1

of potential ingestion cases.

.3 All individuals considered to be in the " potential ingestion group" will be analyzed in accordance with Health Physics Procedure S023-VII-4.2. (Reference 2.4) 6.3.5 Report all results to the Health Physics Leader and assure that individuals requ' ing follow up analyses, decontamination, l etc., are properly att .ded to. l 3

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-44 REVISION NEW PAGE 7

' UNITS 2 & 3 U

7.0 RECORDS Forward all records to the Administrative Leader after review.

4 8.0 ATTACHMENTS I 8.1 Emergency Contamination Guidelines J 8.2 Contamination Control Checklist Spills and Releases i

i 8.3 Personnel Contamination Record l

. 8.4 Nasal Smear Test Data 8.5 Contamination Control Summary Contaminated Personnel l.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-44 UNITS 2 & 3 REVISIOS NEW ATTACHMENT 8.1 PAGE 1 0F 1 EMERGENCY CONTAMINATION GUIDELINES CONTACT

SMEARABLE READING 220 dpm/100 cm 2 OR 100 cpm above bkgd.

Personnel Equipment - Release 220 dpm/100 cm 2 l

To Clean Area beta-gama AND 0.1 mr/hr 22 dpm/100 cm 2 alpha Equipment - Release 1000 dpm/100 cm 2 To Controlled Area beta-gama AND 2.5 mr/hr 100 dpm/100 cm 2 O aiPne l AREAS ** 500 dpm/100 cm 2 beta-gamma --

50 dpm/100 cm 2 alpha

Approximately 1/4" from surface

- Areas above guidelines should be barricaded and posted per nomal plant operating procedures.

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',V SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-44 UNITS 2 & 3 REVISION NEW ATTACHMEtG 8.2 i PAGC 1 0F 1 CONTAMINATION CONTROL CHECKLIST SPILLS & RELEASES IMMEDIATE ACTIONS (May be filled out later)

1. Actions taken to terminate and/or mitigate the spill / release (if applicable):

Initial Time Date

2. Radiological Monitoring Completed: Sunmary of Results:

Highest Smearable: dpm/100 cm 2; Highest

Contact:

mr/hr; Airborne: pCi/mi.

,em Extent of Contamination:

N. / ,

, Initial Time Date i

3. Perr.onnel contaminated (yes/no).

Description:

Initial Time Date

4. Area properly barricaded and posted. Health Physic:; Leader informed:

Initial Time Date

,r 3 kJ SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-44 REVISION NEW ATTACHMENT 8.3 UNITS 2 & 3 PAGE 1 0F 1 PERSONNEL CONTAMINATION RECORD NAME : COMMENTS:

EMPLOYER :

JOB TITLE:

PART BEFORE DECON AFTER DECON OF SMEARABLE FIXED SMEARABLE FIXED dpm , cpm dpm cpm INITIALS DATE TIME BODY f#'\

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v ^1 EMERGENCY PROCEDURE S023-VIII-44 V SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 REVISION NEW ATTACHMENT 8.4 PAGE 1 0F 1 NASAL SMEAR TEST DATA

-Area Individual Net Name Date Time Was In CPM DPM*

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If > 1000 dpm af ter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months decay, perfom Bioassay (HPP-S023-VII-4.2)

SAN ONOFRE NUCLEAR GENERATING 3TATION EMERGENCY PROCEDURE S023-VIII-44 UNITS 2 & 3 REVISION NEW ATTACHMENT 8.5 PAGE 10F 1 CONTAMINATION CONTROL SU N RY CONTAMINATED PERSONNEL POTENTIAL POTENTIAL FRISK RESULTS INHALATION INHALATION INDIVIDUAL BETA-GAMMA ALPHA CASE (YES / NO) CASE (YES / N0) DISPOSITION O

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Completed:

Health Physics Technician Date 3 Reviewed :

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u Health Physics Leader Date

SAN ONOFRE NUCLEAR GENERATING STATION- EMERGENCY PROCEDURE 501-VIII-46 REVISION 1 Page 1 UNIT 1 O CT 1 4 1981

,o V ONSITE SAMPLING RECE... v:D i-OCT 171931 1.0 ;D # @MME OBJECTIVE b u

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1.1 This procedure provides instructions and guidance for collection and analysis of containment air samples and reactor coolant samples during or following a major emergency.

1.2 The Health Physics leader, and Chemistry Leader are responsible for the implementation of their respective parts of this procedure.

1.3 Assigned Health Physics / Nuclear Chemistry Technicians are responsible for the actual collection and analysis of samples.

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station Unit 1 Emergency Plan.

2.2 ?ONGS-1 Chemistry Procedures.

2.3 E r.ergency Procedure 501-VIII-31 " Emergency E.:posure Control".

O 2.4 s ersencv ereceeere So1-vIII-43. SamPi e Coerdinetton durine an Emcrgency".

3.0 PREREQUISITE _S .

3.1 An emergency has been declared in accordance with emergency procedure 501-VIII-11, " Recognition and Classification of Emergencies," and the Emergency Coordinator has requested that the subject samples be collected and analyzed.

3.2 The following personnel protection equipment should be available for use in obtaining the sample.

3.2.1 0-1R and 0-5R pocked dosimeters.

3.2.2 Film badge and TLD finger rings.

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EMERGENCY PROCEDURE S01-VIII-46 SAN ONOFRE NUCLEAR UNIT 1 Ui l'GENERAJ"ING

' STATION REVISION 1 Page 2

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3.0 PREREQUISITES

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3.1 (continued) 3.2.3 Full Face Respirator w/cannister or self contained breathing apparatus.

3.2.4 Teletector or Xetex 302 extendable probe G-M tube survey meters.

3.2.5 Walkie talkies.

3.2.6 Protective clothing - full suit (two for each team l member).

i 3.2.7 Alarming integrating dosimeter.

3.2.8 Beta dose rate ion chambers (RO-2A or equivalent).

4.0 PRECAUTIONS 4.1 If procedure implemented during safety injection, then maintain constant communication with Control Room operators so that evacuation can be accomplished prior to initiation of long' term s recirculation.

g 4.2 Exposure to all personnel due to sampling and analysis operations

.- should be maintained as low as is reasonably achievable.

Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel.

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4.3 If exposure rates of sampling area exceed 20R/hr, discontinue procedure and notify Chemistry Leader of sampling termination.

4.4 G-M tube survey instruments can saturate at extremely high dose rates and subsequently register a false zero reading on the meter. Always monitor the sample area on the highest scale and switch to lower scale (s) as more accuracy is needed.

4.5 In severe accident conditions beta dose rates to the skin may be more limiting than gamma whole body exposure rates. If beta dese rates exceed gamma exposure rates by greater than factor of six, the Health Physics Leader should be consulted as to proper )

personnel protection and appropriate sampling procedures.

5.0 CHECK-OFF LISTS 5.1 None 1 A

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t SAN ONOFRE NUCLEAR' GENERATING STATION EMERGENCY PROCEDURE S01-VIII-46 UNIT 1 OCT 4 4 '961 REVISION 1 Page 3 0 6.0- PROCEDURE 6.1 Containment Atmosphere Sample l 6.1.1 The following sampling and collection apparatus shall be available for use.

' . 1 Two 50 m1 sample flasks and syringe.

i . 2 55 gallon concrete lined drum with shield plug.

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. 3 RADeCo Model GY-130 silver zeolite cartridge.

. 4 'Obtain a key to gate L-2 and high radwaste from the

- Watch Engineer or Security.

. 5 Large Plastic bags i . 6 Marking Pen -

6.1.2 Health Physics Leader (HPL).

y j . 1 The HPL shall request the Emergency Group Leader to form a two man sampling team of which one meaber is a qualified Health Physics Technician and the other is d a qualified Nuclear Chemi>try Technician.

il . 2 The HPL shall verify that the sphere isolation signal for the ORMS Channel 1211/1212 sample line has been

!, manually overridden, and in service for a minimum of

five (5) minutes prior to sampling.

! . 3 The HPL may obtain authorization of emergency exposure in accordance with Emergency Procedure

501-VIII-31, " Emergency Exposure Control," for

! Emergency Sampling Team members if appropriate.

. 4 The HPL should use Attachment 8.1, " Containment Air 4 Sample Data Sheet" to record results.

6.1.3 Emergency Sampling Team j .1 The Emergency Sampling Team shall assemble at or near J the OSC, and obtain the sampling and collection i apparatus and protective equipment listed previously.

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.1 They shall don their Protective Clothing and Respirators and preset their Alarming Dosimeters to 1000 mR.

.2 Proceed into the Controlled Area via Gate L-2 Access iO ae=te-

.1 Leave a complete change of clothing at Gate L-2.

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EMERGENCY PROCEDURE S01-VIII-46 SANONOFRENUCLEAR}{NpRATgGSTATION 4 18 REVISION 1 Page 4 UNIT 1

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6.0 PROCEDURE 6.1.3 (continued)

.2 Unlock the high radwaste storage area.

.3 Proceed to Ventilation Building.

.4 Close the two 1" brass ball valves immediately upstream and downstream of the moisture filter on the j containment return line ('234-1"-KP3). Put in place i the quick disconnect 50cc sample vial. Open the 1" brass ball valve on the bypass line to the moisture filter. Flush containment sample line through the 50cc sample vial for a minimum of two minutes.

.5 While sample line is being flushed proceed to General Atomic Stack Sampler.

.6 Collect charcoal cartridge and replace with RADeCo Model GY-130 Silver Zeolite Cartridge.

NOTE: Dose rates on cartridge may make removal impossible. Monitor to ensure eighteen inch gamma exposure rate is less than 20R/hr.

p V .1 l' lace the charcoal cartridge in a pre-labelled

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' plastic bag reading, " stack charcoal cartridge". If the sample is reading greater than 10 mR/hr at 1 foot take the sample to high radwaste storage and put it in the concrete lined 55 gallon drum. Make sure to hold the sample as far from your body as possible. If the sample is less than 10 mR/hr it may be transported to the Health Physics office when sampling is completed.

.2 Notify HPL of sampling time and flow integrator value.

.7 Return to ORMS Channel 1211/1212 sample point and collect 50cc gas sample.

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.8 Using syringe transfer Ice of sample collected to 50cc flask labeled " Dilution 50".

.9 Place both samples in appropriately labelled plastic bags.

.10 Close the 1" brass ball valve on the bypass line to

' the moisture filter and open the two 1" brass ball veives 4 mee4>te,x ePstree e#e ee "stre = er the O moisture filter on the containment return line (1234-1"-KP3).

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S01-VIII-46 UNIT 1 OCT 14199; REVISION 1 Page 5 7_s

'O 6.0 PROCEDURE 6.1.3 (continued)

.1 Have the Health Physics Leader notify the Emergency Coodinator to isolate the containment sphere sample line.

11. Check the radiation level. My sample reading greater than 25 mR/hr at 1 foot should be transported in the high radwaste stroage area concrete lined 55 gallon drum. Make sure to keep the samples as far from your body as passible while you transport the gas samples.

, .1 If both gas samples are greater than 25 mR/hr ,

additional dilutions should be made to bring :

the radiation level down to this point before any sample is transported to the Health Physics Office. Store the samples in the high radwaste concrete lined drum while obtaining additicaal gas sample containers.

.12 Transport samples to the Health Physics Office via Gate L-2 Access Route.

.1 Lock the High Radwaste Area gate.

.2 Change into clean Protective Clothing at Gate L-2 location. Lock the gate as you leave the area.

NOTE: Exercise good contamination control practice in t.aking the samples out of the controlled area.

.13 Transfer the samples to the reactor plant chemistry laboratory via the dumbwaiter in the reactor coolent sample room.

.14 Analyze G/A stack sample charcoal cartridge on Ge(Li) system in accordance with the instrument operating procedures.

.15 Analyze gas. sample on the Ge(Li) system in accordante with the instrument operating procedures.

.16 Determine hydrogen in containment airborne sample using Chemical Procedure 501-III-1.18, " Dissolved H by Gas Chromatography".

2

.17 Have the HPL notify the Emergency Coordinator of f}

L analysis results.

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S01-VIII-46 UNIT 1 - CT 1419u REVISION 1 Page 6

. /

k]J 6.0 PROCEDURE 6.2 REACTOR COOLANT SAMPLE 6.2.1 The following sample and collection apparatus shall be available for use.

.1 55 gallon concrete lined drum with shield plug.

.2 One (1) 100ml sample flask labeled "Undfluted Sample".

3

.3 One (1) 1000ml sample flask labeled " Boron-10 Dilution" - Fill the flask to the mark with -

demineralized water prior to sampling.

6

.4 One(1) 1000ml sample flask labeled "RCS-10 Dilution" - Fill the flask to the mark with demineralized water prior to sampling.

.5 Several 1 ml pipet tips.

.6 1 ml automatic pipet.

.7 Stopwatch.

.8 Obtain a key to gate L-2 and high radwaste from the Watch Engineer or Security.

. .9 Large Plastic bags.

i

.10 Marking pen.

6.2.2 Chemistry Leader (CL).

f

.1 The CL shall request the Emergency Group Leader to form a two man sampling team of which one member is a qualified Health Physics Technician, and the other a Nuclear Chemistry Technician.

.2 The CL shall verify that letdown flow has been ,

manually established so that the mixed-bed 4 demineralizers and the reactor coolant filter have been bypassed. The letdown flow must be established i a minimum of ten (10) minutes prior to sampling. ,

.3 The CL may obtain authorization for emergency !

exposures in accordance with Procedure, 501-VIII-31, j

" Emergency Exposure Control," for Emergency Sampling ,

Team Members if appropriate. l

.4 The CL should use Attachment 8.2, " Reactor Coolant Data Sheet" to record the coolant analysis results.

~

"4

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PRUCEDURE S01-VIII-46 UNIT 1 ! 43,9; REVISION 1 Page 7 V

6.0 PROCEDURE i 6.2.3 Emergency Samo11ng Team

.1 The Emergency Sampling Team shall assemble, at or near the OSC, the samplir.g and collection apparatus and protective equipment listed previously.

.1 They shall don one set of Protective Clothing and their Respirators and preset their alarraing dosimeters to 1000 mR.

.2 Proceed to the controlled area via Gate L-2 Access Route.

.1 Leave complete change of protective clothing at Gate L-2.

.2 Unlock High Radwaste Area before collecting i samples. j

.3 Prior to entering Boron Analyzer Room, one r.wmber of the team shall determine the radiation exposure rates

. in the room by entering the room with the survey meter on the highest scale. If working area (18" (q/ from sample line) is less than 20 R/hr, then continue

',, with sampling and collection.

.1 The inverse square rule should be utilized (exposure rate only) to estimate the working area exposure rates, i.e., (if 5 R/hr at 36 inches, than the 18" dose will be 20 R/hr).

.2 If exposure rate approaches 20 R/hr at 18",

discont.inue procedure, return to OSC and have Emerger,cy Group Leader notify HPL and CL.

.4 Flush approximately two (2) liters through the sample line into a bucket or drain. Obtain 1 m1 sample using the automatic pipet. Deliver to a 1 liter 3

volumetric flask marked " Boron-10 Dilution".

.1 Close sample valve.

.2 Leave sample room.

.3 Determine Im1 sample exposure rate. Take this reading in a low background area.

3 p .4 Mix sample (marked " Boron-10 Dilution").

V 3

5. Pipet Im1 of the " Boron-10 Dilution" sample in a :

' 6 1000ml volumetric flask marked "RCS-10 Dilution". l Mix the sample. ;

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S01-VIII-46 UNIT 1 . O.,i 141981 REVISION 1 Page 8 6.0 PROCEDURE 6.2.3 (continued)

.6 If the sample exposure rate reading obtained in Step 6.2.3.4 was below 1,000 mR/hr, then obtain 100ml sample in flask marked " Undiluted Sample".

.7 Make sure all samples are securely closed. Place each sample in an appropriately marked plastic bag and proceed immediately to the High Radwaste Stroage Area. During transport make sure to keep the samples as far from your body as possible.

.8 Transfer coolant samples to previously prepared DOT approved 55 gallon concrete lined drum.

.9 Cap top portion of drum with lead shield and seal ty ;

of drum. Ensure that the seal is secure.

.10 Relock high radwaste area.

.11 Check the status of manual initiation of long-term recurculation with the Operations Leader. If ,

long-term recirculation is about to be initiated, j O then immediately evacuate the area via the Gate L-2 Access Route making sure to lock the gate. j i

.12 Return to Health Physics Office via Gate L-2 Access Route making sure to lock the gate.

.13 Inform the Emergency Group Leader that the sampling ;

in the Boron Analyzer Room has been completed.

.14 Contact the CL and the HPL in the Technicial Support Center and indicate that an unpressurized reactor coolant sample has been obtained from the letdown line and is available for shipment offsite.

.15 Verify through the Operations Leader that the Control Operators have manually over-ridden the containment ,

isolation signal to valve CV-957 so that the reactor coolant sample line can be opened.

NOTE: If the radiation level obtained in Step 6.2.3.3 is less than 1.0 R/hr at 18" proceed with Step 6.2.3.16 thru 6.2.3.23. If greater than the above level notify the Chemistry Leader (TSC) 1 and request further instructions.

Od

.16 Following 50"GS-1 Chemical Procedures, cbtain a pressurized reactor coolant sample and a hydrogen gas sample.

l I

l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S01-VIII-46 UNIT 1 OCT 141981 REVISION 1 Page 9 6.0 PROCEDURE i

6.2.3 (continued)

.17 Following SONGS-1 Chemical Procedures, obtain an additional reactor coolant sample for boron and chloride analyses.

.18 Inform the Operations Leader that a pressurized reactor coolant sample has been obtained and that the -

sample line can again be isolated. *

.19 Determine hydrogen in reactor coolant following SONGS-1 Chemical Procedures. ,

i

.20 Determine chlorides in reactor coolant following :

1 SONGS-1 Chemical Procedures. g

.21 Determine boron in reactor coolant following SONGS-1 l Chemical Procedures.

.22 Determine gross coolant activity and degassed ,

activity using SONGS-1 Chemical Procedures. I

.23 Inform the CL in the Technical Support Center that a !

}

- pressurized reactor coolant sample and a hydrogen gas

- sample have been obtained and give the analysis !

results.

7.0 RECORDS 7.1 The Supervisor of Plant Chemistry shall review all analysis and transfer results to Administrative Leader.

8.0 ATTACHMENTS i 8.1 Containment Air Sample Data Sheet.

8.2 Reactor Coolant Sample Data Sheet.

2 kb K. P. BARR HEALTH PHYSICS MANiGER DM:0091F:sss O

EMERGENCY PROCEDURE S01-VIII-46 SANONOFRENUCLFpRGENERATINGSTATION UNIT 1 C: 14liSI REVISION 1 PAGE 1 0F 1 Q ATTACHMENT 8.1 CONTAINMENT AIR SAMPLE DATA SHEET

1. G/A Stack Sampler i

4 Sampling Time Flow Intergrator

2. Charcoal Cartridge Results I-131 pct /cc I-132 pCi/cc I-133 pC1/cc I-134 pCi/cc <

4 I-135 yCi/cc

'c Total

3. Gas Sample Results i Kr-85 yCi/cc Kr-85m pCi/cc Kr-87 yC1/cc Kr-87 pCi/cc

Xe-133 pCi/cc

^

Xe-133m pCi/cc Xe-135 vCi/cc f

Xe-135m pCi/cc i Total Hydrogen Content % j 4.

O l Signature Date

SAN ONOF,RE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S01-VIII-46 REVISION 1 PAGE 1 0F 1 UNIT 1 00714 seg

' ATTACHMENT 8.2 i

i REACTOR COOLANT SAMPLE DATA SHEET Hydrogen Concentration %

1.

ppm

2. Chloride Concentration _

ppm

3. Boron Concentration Gross Coolant Activity y C1/ml

4. .

Degassed Coolant Activity y Ci/mi 5.

4

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Signature Date 4

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l SAN GNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-45 O 'd UNITS 2 & 3 REVISION NEW ISol PAGE 1 1 I

f PERS0 D MD ING 1.0 OBJECTIVE k h This procedure ovi r%Ei ods, action levels and docu-mentation for th -

of ' personnel and vehicles during an evacuation.

The Health Physic er is responsible for the implemgaftogghis procedure. ,, y re p [ { g

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2.0 REFERENCES

lb[b OCI 141981 2.1 NUREG-0654, Rev.1, Criteria for Preparation and Eva@ldi6hT5f Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2 San Onofre Nuclear Generating Station, Units 2 & 3, Emergency Plan 2.3 Health Physics Procedure S023-VII-4.2, " Bioassay Program" 2.4 Health Physics Procedure S023-VII-4.4, " Personnel Decontamination" 3.0 PREREQUISITES O

v 3.1 An emergency condition Ns been declared at San Onofre Nuclear Gener-t ating Station Units 2 & 3.

3.2 An evacuation has been initiated in accordance with Emergency Procedures S023-VI!I-32, " Local Evacuation and Accountability", S023-VIII-33,

" Plant Evacuation and Accountability" or 5023-VIII-34, " Site Evacuation and Accountat111ty".

4.0 PRECAUTIONS 4.1 The safety of personnel shall take precedence over the monitoring of personnel and vehicles for the purpose of radiation / contamination control.

4.2 Monitoring of personnel an(/or vehicles shall be terminated, or not im-plemented, if such monitoring is known or suspectea to be increasing the hazard to personnel during evacuation.

4.3 Monitoring stations should be selected and monitoring operations should be conducted in such a manner as to maintain personnel exposures as low as is reasonably achievable.

5.0 CHECK-0FF LISTS 5.1 Personnel Monitoring Checklist For Local / Plant Evacuation (Attachment 8.1) 5.2 Personnel and Vehicle Monitoring Checklist For Site Evacuation (3

v' (Attachment 8.2)

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-45 REVISION NEW PAGE 2 UNITS 2 & 3 g7_)

6.0 PROCEDURE 6.1 Local and Plant Evacuations 6.1.1 Personnel involved in local evacuations should be directed.

to the Health Physics office area. If these facilities are not accessible, evacuated personnel should be directed to an appropriate alternate location.

6.1.2 Personnel involved in plant evacuations should be directed from the protected area to the AWS warehouse receiving entrance.

6.1.3 Personnel should be monitored for contamination, and if practic-able, evacuated personnel should pass through a portal monitor prior to frisking.

6.1.4 If conditions permit, an immediate attempt will be made to remove any contamination detected on personnel in accordance with Health Physics Procedure 5023-VII-4.4 (Reference 2.4).

6.1.5 If personal clothing items become contaminated, an effort will be made to reduce the levels to clean release limits (<.1 mr/hr l

(\ -) fixed and < 220 dpm/100 cm2 smearable) . If these levels cannot be obtained after reasonable efforts have been made, the items shall be disposed of as radioactive waste.

6.1.6 Dose estimates should be raade utilizing both self-reading dosimeters and TLD/ Film data.

6.1.7 Personnel who may have been exposed to airborne radioactivity, should have nasal contamination monitoring and bicassay per-formed in accordance with Health Physics Procedure S023-VII-4.2 (Reference 2.3).

6.1.8 The Personnel Contamination Record, Attachment 8.3, should be completed for contaminated individuals.

6.1.9 A listing of all personnel surveyed, with survey results, and personnel exposures should be complied, signed and dated by the Health Physics technician. This information should be submitted to the Health Physics Leader. ,

6.2 Site Evacuation I

NOTE: Personnel evacuated from the site may act have adequate time for contamination moni . iring onsite. ,

Therefore, the potential for contamination of

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'v vehicles is increased.

O SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-45 UNITS 2 & 3 REVISION NEW PAGE 3 6.0 PROCEDURE (Cont'd) 6.2.1 Prior to site evacuation, perform vehicle contamination monitoring on every tenth (10th) vehicle at the designated.

auto parking areas as indicated by meteorlogical conditions.

6.2.2 If some vehicles are determined to be contaminated, deter-mine extent of the contamination by surveying nearby vehicles.

It may be necessary to restrict access to parking lots or major portions thereof.

6.2.3 Report to the Health Physics Leader the results of the vehicle survey.

NOTE: All vehicles found to be contaminated should be documented on Attachment 8.5, Vehicle Survey Form.

6.2.4 Contaminated vehicles must be held for decontamination.

'O NOTE: Contaminated vehicles should be clearly marked

\ for easy identification.

6.2.5 Personnel will be monitored at the Assembly Area and should be resurveyed at the remote Assembly Area. If any personnel are found contaminated, they should be decontaminated in accordance with Health Physics Procedure S023-VII-4.4 (Ref-erence 2.4).

7.0 RECORDS Forward all records to the Administrative Leader after review.

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EMERGENCY PROCEDURE S023-VIII-45 3_' SAN ONO.EE NUCLEAR GEN'ERATING STATION PAGE 4 REVISION NEW

. UNITS 2'a 3 N

8.0 ATTACHMENTS 4 8.1 Personnel Monitoring Checklist For Local / Plant Evacuation 8.2 Personnel and Vehicle Monitoring Checklist for Site Evacuation .

- 8.3 Personnel Contamination Record 8.4 Vehicle Survey Record 4 8.5 Vehicle Survey Fom 5 K. P. BARR ~

HEALTH PHYSICS MAGER f-O:

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-( ) SAN ON0FRE NUCLEAR GENERATING STATION UNITS 2 & 3 EMERGENCY PROCEDURE S023-VIII-45 REVISION NEW ATTACHMENT 8.1 PAGE 1 0F 1 PERSONNEL MONITORING CHECKLIST FOR LOCAL / PLANT EVACUATION Initials

1. All personnel frisked for contamination.

2. If any individuals are found contaminated, decontamination procedures instituted and Attachment 8.3 completed.

3. Dose estimates made.

4. Nasal smears taken and Bioassay performed, if applicable.

5. Survey results and dose estimates recorded.

After this check-off list is completed it should be submitted to the Administrative Leader.

O

( Monitoring Performed By:

Completed: Hours Date:

Reviewed By: Date:

Health Physics Leader O

1 l

EMERGENCY PROCEDURE S023-VIII-45 i( ) 3AN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 REVISION NEW ATTACHMENT 8.2 PAGE 1 0F 1 PERSONNEL AND VEHICLE MONITORING CHECKLIST FOR SITE EVACUATION !

I Initials

1. Survey point established. Vehicles surveyed.

2. Contaminated vehicles held, Vehicle Survey Forms completed for each. (Attachment 8.5)

3. Personnel surveyed for contamination.

I 4. Vehicle Survey Record, Attachment 8.4 should be filled out for all vehicles.

4 After this check-off list is completed it should be submitted to the Administrative Leader.

!O Surveys Performed By:

I -

Completed: Hours Date:

1 4 Reviewed By: Date:

Health Physics Leader A

1

7 4

i .

' SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-45

UNITS 2 & 3 REVISION NEW ATTACHMENT 8.3 l

' PAGE I 0F I >

! PERSONNEL CONTAMINATION RECORD i~

Name : Coments:

7-tmployer :

- Job

Title:

After Decon

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Before Decon 4 Part Smearable Fixed Smearable Fixed Date Time of Body dpm com dpm com Initials i

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() SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 EMERGENCY PROCEDURE Sn23-VIII-45 REVISION NEW ATTACHMENT 8.4 PAGE 1 0F 1

/'

VEHICLE SURVEY RECORD Circle tag numbers of vehicles needing decontamination.

Get owner's address and inform him that his car may not be removed until decon-

~

taminated. ,

SCE Personnel Contract Personnel and Visitors Name/ License No. Name/ License No. Name/ License No. Name/ License No.

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A V SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-45 REVISION NEW ATTACHMENT 8.5 UNITS 2 & 3 PAGE 1 0F 1 i

, i f VEHICI.E SI'RVEY FORM i

1. This form should only be filled out for contaminated vehicles.

! 2. Ensure that all tag numbers and names are recorded on the Vehicle Survey Record.

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Passenger's Side e

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J; !MOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-51 UNITS 2 AND 3 NEW Page 1 RECORD KEEPING

/- 1.0 OBJECTIVE 1.1 To provide a sethod of documenting events and important data on an emergency. The Emergency Coordinator is responsible for implemtation of this procedure.

2.0 REFERENCES

2.1 NUREG-0654, Rev.1, Criteria for Preparation and Evaluatiuon of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

2.2 San Onofre Nuclear Generating Station, Units 2 and 3 Emergency Plan.

3.0 PREREQUISITES -

3.1 An emergency condition has been declared at San Onofre Nuclear Generating Station, Units 2 and 3.

4.0 PRECAUTIONS RECEIVrn 4.1 None OCT 141981 3

.M 5.0 CHECK OFF LIST q a= m a" r { [" DM SITE 5.1 None b

i Ew E

r y C-* h, 'r[, 3 8

s 6.0 PROCEDURE 6.1 The Emergency Log shall be official documentation of events during an emergency with one exception: the operations staff will log operational events in an Operations Log. The Operations Log will suffice for emergency documentation of operational events. All other important events should be logged in the Emergency Log. The Emergency Log may subsequently be used to reconstruct events. Entries may be corrected and expanded by comparision with other logs covered in the procedure. The Emergency Coordinator / Watch Engineer should delegate the record-keeping task of this log to the designated Emergency Communicator or another available individual. The below listed items are examples of events and data that should be recorded in the Errergency Log:

6.1.1 Significant events and the 1.imes at which they occur.

6.1.2 Reports made to the Emergency Coordinator (plant status, radiological conditions, etc.).

() 6.1.3 Notification made.

1 SAN-ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-51 UNITS 2 AND 3 NEW Page 2 v) 6.0 . PROCEDURE (Continued) l

/' 6.1 The Emergency Log (Continued) 6.1.4 Hazard assessment.

.1 Operation (not operational documentation effort)

.2 Radiological 6.1.5 Radiological monitor alarms.

6.1.6 Survey results, area and personnel.

6.1.7 Evacuations 6.1.8 Injuries and medical care 6.1.9 Meteorological information 3 6.1.10 Emergency teams dispatched (survey, first aid, repair, fire,etc.).

6.1.11 Re-entry efforts 6.1.12 Recovery efforts 6.1.13 Offsite dose projections 6.1.14 Any other item deemed necessary or pertinent.

6.2 Emergency Coordinators Log 6.2.1 The Emergency Coordinators Log is an unofficial bound notebook maintained by the Emergency Coordinator containing information which may be needed subsequently to reconstruct events. Entries are j entirely at the discretion of the Emergency i

Coordinator but may include the bases for decisions and recommendations.

6.3 Emergency Organization Logs !

6.3.1 The remaining logs, listed below, are unofficial and are used to provide a bound book for the notes, calculations and recommendations of each area of the ;

Emergency Organization. The responsibility for maintaining the log and, ultimately, for deciding

what information to log, belongs to the leader of each group. Each leader should log all pertinent 2 s data and events to facilitate casualty reconstruction

, s) at a later time.

I

SAN ONOFRE NUCLEAR GENERATING LTATION EMERGENCY PROCEDURE S023-VIII-51 eq NEW Page 3 UNITS 2 AND 3

,Ov 6.0 PROCEDURE

[ 6.3.1 (Continued)

.1 Operations Log -- Operations Leader / Emergency Advisor

.2 Emergency Team Log -- Emergency Group Leader

.3 Engineering Log -- Technical Support Leader

.4 Health Physics Log -- Health Physics Leader

.5 Administrative Support Log -- Administrative Leader

.6 Security Log -- Security Leader

.7 Chemistry Log -- Chemistry Leader 6.4 Emergency Plan Implementing Procedure (EPIP) Attachments 6.4.1 To avoid taking attachments from the hard bound sets of EPIPS an extra forms book will be kept at the control room (to be used in the TSC when activated) and the OSC. These shall be maintained as follows:

{ The books stall contain 10 copies of each attachment

.1 frcm all the EPIPS.

.2 Upon completion of these attachments each responsible person shall forward it to the Administrative Leader or the Station Services Manager if the TSC is not activated. -

4

.3 The Administrative Leader (or Station Services Manager) will ensure that attachments that have been used are replenished to maintain 10 copies of each.

! 7.0 RECORDS i 7.1 All completed records are to be forwarded to the Administrative 1 Leader (Station Services Manager if TSC is not activated). He shall ensure that all filled in attachments are filed in COM under respective procedure number and sequential event number as l per 6.2 of 5023-VIII-16.

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SAN ONOFRE NUCLcAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-51 UNITS 2 AND 3 NEW Page 1 of 1 O ATTACHMENT I GENERAL LOG FORMAT

[~ TITLE OF LOG (DATE)

(RECORDED BY)

(INITIAL CLASSIFIECATION OF EMERGENCY / TIME)

TIME /

Date" ENTRY INITIAL i

1 O .

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i

First page only

** Date only entered once per day at 0001

O DDB:0127F:jhm

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-51 I

UNITS 2 AND 3 NEW Page 4 1

I I

8.0 ATTACHMENTS I

f / 8.1 General Log Format i

i

=_

K. P. BARR

! HEALTH PHYSICS MANAGER DM:0066F:sss l

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SAN ONOFRE NUCLEAR GENERATING STATION. EMERGENCY PROCEDURE 5023-VIII-61 UNITS 2 AND 3 N PAGE 1 I q s ,

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N01 FOR CUllSTRUCTION MT9.RT-UP USF ONLY 1.0 OBJECTIVE gg F( C N1 Tlh;("h6 1.1 This procedure provides instructions for re-entry to the site, plant or to affected local areas within the plant when radiological conditions are largely unknown. Re-entry is made to perforn essential tasks such as rescue and life saving, controlling release of radioactive materials and preventing additional damage to plant equipment.

1.2 The Emergency Coordinator is responsible for activation of this procedure and may delegate responsibility for specific tasks and measurements to the Health Physics Leader.

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station Unit 1 Emergency Plan.

2.2 EPIP S023-VIII-31, " Emergency Exposure Control". RECEiVFn 2.3 EPIP S023-VIII-36, " Thyroid Prohpylaxis". OCT 141981 2.4 EPIP S023-VIII-39, " Rescue". CDM SITE 3.0 PREREQUISITES 3.1 An emergency condition at SONGS Units 2 and 3 has resulted in the evacuation of the site, or:

3.2 An emergency condition at SONGS Units 2 and 3 has re.sulted in the evacuation of the Plant, or:

3.3 An emergency condition at SONGS Units 2 and 3 has resulted in the evacuation of a local area within the site, and:

3.4 The magnitude and/or nature of the radiological hazard in the affected area is unknown, and:

3.5 Conditions have stabilized to the point that re-entry can be considered to assess the conditions, and perform vital operational or repair functions, or effect search and rescue.

C')

SAN ONOFRE NUCLEAR GENERATING STATION EMERGEH"Y PROCEDURE S023+VIII-61 UNITS 2 AND 3 NEW PAGE 2 l '( 4.0 PRECAUTIONS

- 4.1 Because of the unknown conditions within the site, the plant or the affected area, appropriate precautions for personnel safety shall be implemented. These include, but are not limited to the precautions described below:

4.1.1 Re-entry teams shall be composed of a minimum of two individuals, one of whom is a qualified Health Physics Technician. These individuals shall remain in visual / voice contact with each other at all times when in the affected area.

4.1.2 If the ventilation to the area has been isolated, and/or if there is reason to believe that the air within the area is toxic or an oxygen deficiency exists, appropriate ,

self-contained breathing apparatus (SCBA) shall be used.

In this case, in addition to the two man entry team, one or more additional individuals shall be assigned to remain outside of the affected area, in appropriate clothing and with SCBAs on standby, ready to enter the area to effect rescue.

4.1.3 Life-lines should be used in areas containing heavy smoke, or in areas where visual contact cannot be maintained with the re-entry team.

( ])

4.1.4 Personal ala rming dosimeters should be used if extreme conditions are suspected.

4.1.5 Protective clothing should be chosen on the basis of the suspected conditions, or if a reasonable estimation cannot be made, the protective clothing with the highest protection should be used.

4.1.6 If possible, areas should be ventilated prior to entry.

4.1.7 Exposures of re-entry personnel shall be in accordance with S023-VIII-31, " Emergency Exposure Control".

5.0 CHECK -OFF LISTS 5.1 Re-entry Team Equipment and Protective Gear.

5.2 Re-entry Checklist.

6.0 PROCEDURE 6.1 Initial Site Re-entry Note: This section of the procedure assumes that personnel have evacuated the site and have assembled at an offsite O assembly area:

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SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-61 UNITS 2 AND 3 NEW PAGE 3 O 6.0 PROCEDURE

- 6.1 Initial Site Re-entry (continued) 6.1.1 The Health Physics Leader shall assume the duties of Re-entry Coordinator, and shall organize and direct re-entry. If he is still in the TSC he shall appoint a

- senior Health Physics member offsite as Re-entry Coordinator.

6.1.2 The Re-entry Coordinator shall utilize all pertinent data asm'iable including survey data from adjacent areas, i

observations made by evacuated personel, and any other -

source to determine:

.1 Which plant areas are affected.

.2 Conditions in affected areas (hazards, radiological conditions, temperatures,etc.).

.3 If personnel are trapped and/or disabled in affected areas.

.4 If actions can be taken to reduce the potential hazards to re-entry personnel prior to or during

() re-entry.

.5 If re-entry can be delayed without affecting plant or personnel safety to allow for radioactive decay.

.6 Preferred route to survey area.

6.1.3 Form an appropriate re-entry team.

Note: Re-entry teams should be composed of volunteers and

' shall include at least one Health Physics member.

6.1.4 The Re-entry Coordinator shall direct each team member to obtain appropriate equipment and don appropriate protective clothing and respirators. Attachment 8.1 should be used as a guide for appropriate equipment and protective gear.

6.1.5 A vehicle should be obtained in which to approach the site. Gas tank level shall be greater than 1/2 full.

6.1.6 If available, plastic should be spread on the floor of the vehicle and seats, in order to minimize contamination.

6.1.7 As appropriate to the radiological conditions and/or re-entry team assignment, the Re-entry Coordinator should:

.1 Ensure that the team turns on and checks the

("]

\ operation of survey instrument (s).

- . - . - - - e w 7 y - - w-- -

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-61 NEW PAGE 4 UNITS 2 AND 3

! 6.0 PROCEDURE 6.1 (continued)

~

Note: If at any time the survey instrument appears to be malfunctioning, direct team to immediately retreat to a safe area. Be especially careful for unexpected low survey instrument readings. Some GM survey

. instruments will read "0" or a low value if the detector is saturated by extremely high radiation i levels.

f

.2 Ensure that the team approaches the site from upwind as much as possible and continuously monitors

radiation levels by extending the instrument probe I out the vehicle window.

1 .3 Continuously apprise the EOF of the progress of the re-entry team, conditions observed, and dose rates.

.4 Direct re-entry team members to check their pocket dosimeters per1odically and report the results. The i frequency of these checks should be consistent with the observed dose rate.

.5 If at any time during re-entry, observed dose rates exceed I rem /hr (or other predetermined livel), or if 1

j the exposure of any member of the re-entry team exceeds 2.5 rem, (or other specified maximum j allowable dose), direct the entire re-entry team to -

retreat to a safe area.

i .6 Direct the team to perform assigned surveys in l

accordance with emergency monitoring procedure, and i

4 to fully document all results.

! .7 Upon arrival of the team at the site boundary, direct them to enter the site and perform an additional j survey about halfway between the affected unit and

' the site boundary.

l

!' .8 If instructed to re-enter the plant, direct the team to approach the guardhouse, continuously monitoring i dose rate. Upon entry thru the gate report the

! progress and dose rates observed.

.9 If directed further, have the team re-enter the unit and continue as provided in subsequent sections of this procedure.

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1 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-51 UNITS 2 AND 3 NEW PAGE S 6.0 PROCEDURE (continued) 1 6.2 Restoration of Limited Site Access 6.2.1 The Emergency Coordinator and Health Physics Leader shall utilize all pe-tinent data available including area and process monitoring channels, survey data and observations made by Re-entry Team and Operations personnel to determine:

.1 Which plant or site areas are affected.

.2 The conditions (hazards, temperature, air quality, etc.) in the areas.

.3 Is is practical to reduce the potential hazards to re-entry personnel by ventilating, change flow paths or secure systems, etc.).

.4 If re-entry into specific areas can be deferred without affecting plany safety to allow for radioactive decay.

.5 Once the radiation levels are low enough so that personnel will not receive more than the 10CFR20 quarterly dose during their entry, stay, and exit from the plant, personnel may be assigned to enter the plant for specific tasks. These personnel will be equipped with appropriate protective clothing depending on contamination and airborne conditions.

6.2.2 Based upon radiological surveys of the site and the status of radioactive emissions, if any, from the plant, the Emergency Coordinator and Health Physics Leader shall determine a location for vehicle and personnel access control.

.1 The location shall be utilized for contamination monitoring and dosimetry issue and recording.

.2 Security shall be able to establish a reasonable degree of control over personnel and vehicle access to the site.

.3 Radiologica' controls such as type of respiratory equipment, protective clothing and dosimetry shall be specified and issued to all work groups entering the station. 1

.4 Operations and Maintenance personnel necessary to l s operate the station and effect repairs shall be accompanied by a Health Physics technician.

O .5 Access routes that minimize personnel exposures shall be established.

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l SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023.-VIII-61 UNITS 2 AND 3 NEW PAGE 6 D

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6.0 PROCEDURE (continued) 6.3 Re-entry to Plant and/or Local Areas Note: This section of the procedure may be used without the preceeding sections, if only certain areas within the plant have evacuated and isolated. Applicable steps may also be used subsequent to the implementation of the preceeding sections, if a Site Evacuation has taken place.

6.3.1 The Health Physics Leader (or other senior Health Physics individual) shall assume the duties of Re-entry Coordinator, and shall organize and direct re-entry.

6.3.2 The Re-entry Coordinator shall utilize all pertinent data available including area and process monitoring channels, survey data from adjacent area, observations made by evacuated personnel, and any other source to determine.

t

.1 Which plant areas are affected.

.2 Conditions in.affected areas (hazards, radiological conditions, temperatures,etc).

.3 If personnel are trapped and/or disabled in affected i (~TN) areas.

.4 If actions can be taken to reduce the potential

! hazards to re-entry personnel prior to or during re-entry.

.5 If re-entry can be delayed without affecting plant or personnel safety to allow for radioactive decay.

6.3.3 Form an appropriate re-entry team.

Note: When possible re-entry teams should be composed of volunteers and include at least one Health Physics member.

6.3.4 The Re-entry Coordinator shall direct each team member to obtain appropriate equipment and don appropriate protective clothing and respirators. Attachment 8.1 should be used as a guide for appropriate equipment and protective gear.

6.3.5 Ensure that the team turns on and checks the operation of the survey instrument (s).

Note: If at any time the survey instrumant appears to be malfunctioning, direct the team to immediate?y i

> retreat to a safe area. Be especially careful for gg unexpected low survey instrument readings. Some GM

() survey instruments will read "0" or a low value if the detector is saturated by extremely high radiation levels.

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k SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-61 l UNITS 2 AND 3 NEW PAGE 7 l 6.0 PROCEDURE 4 6.3.5 (continued)

.2 Direct the team to approach the affected unit / area, 1 continuously monitoring dose rates.

.3 Continuously apprise the TSC/ EOF of the re-entry team exposures, conditions observed, and dose rates.

.4 Direct re-entry team members to check their pocket dosimeters periodically and report the results. The frequency of these checks should be consistent with -

the observed dose rate.

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.5 If at any time during re-entry observed dose rates exceed I rem /hr (or other pre-determined level), or if the exposure of any member of the re-entry team exceeds 2.5 rem, (or other specified maximum allowable dose), direct the entire re-entry team to retreat to a safe area.

.6 Direct the team to perform surveys in accordance with emergency monitoring procedures and to full document all results.

i .7 Direct the team to perform appropriate inspections, i repairs, and operations.

.8 Direct team to perform appropriate rescue and first aid functions if trapped or disabled personnel are discovered in the area.

6.3.6 At the completion of assigned functions, direct the team to leave the affected area and return to the control point, remove protective clothing, and monitor prior to leaving the area.

6.4 Restoration of Limited Access to Unit / Area 6.4.1 Once radiation, contamination and airborne levels are low enough to permit a 40 bcur week without exceeding a dose of 200 mrem, the essential plant staff can resume a normal work week. Visitors and l non-essential personnel will still not be admitted.

6.5 Restoration of Normal Access to Unit / Area 6.5.1 Once radiation contamination and airborne levels are near normal, the plant will be returned to normal routine entry requirements.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-61 UNITS 2 AND 3 NEW PAGE 8 O 7.0 RECORDS i

- 7.1 Forward all completed check lists and survey forms to the Administrative Leader after they are no longer required for immediate use.

8.0 ATTACHMENTS 8.1 Re-entry Team Equipment and Protective Gear Check-list t

8.2 Re-entry Criterie Check-list i

K. BARR HEALTH PHYSICS MANAGER O

DM:0074/ryh i

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-61 UNITS 2 AND 3 NEW PAGE 1 of 2 j) ATTACHMENT 8.1 v

RE-ENTRY TEAM EQUIPMENT AND PROTECTIVE GEAR Health Physics /Re-entry Coordinator: Initial each applicable item below in the space provided as it is provided to the re-entry team (s). Do not initial items that are not provided.

INITIALS ITEM High range self-reading pocket dosimeters (2 per individual)

TLD badges (2 or more per individual)

Extremity TLD's - as appropriate Portable radio transceiver High range survey instrument (preferably with telescoping probe)

S

- as appropriate Intermediate range survey instrument e"% G-M survey instrument U Air samples and filters / cartridges Personnel air monitors - as appropriate Alarming dosimeters - as appropriate Area maps, survey forms, pencils Contamination swipes and envelopes

First aid / rescue equipment - as appropriate Appropriate protective clothing - if in doubt, require full protective clothing Appropriate respiratory protective equipment Keys - as appropriate O

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. SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-61

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. lTS 2'AND 3 NEW PAGE 2 of 2

- ATTACHMENT 8.1 NOTE: Only Self-Contained Breathing Apparatus (SCBA) should be useu for re-entry and/or rescue purposes. Air purifying respirators shall not be used if toxic gases or oxygen deficiency is present or suspected. Air hose respirators should not be used due to diffir.ulties in handling hoses in confined areas during emergencies.

(Data) (Re-entry Coordinato- / Designee)

NOTE: After this checklist is completed and is not required for immediate use, forward it to the Administrative Leader.

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SAN O!:0FP.'. .;L.AR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-61 UNITS 2 AND 3 NEW PAGE 1 of 2 ATTACHMENT 8.2

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RE-ENTRY CRITERIA CHECK-LIST (for use with procedure 5023-VIII-61)

Date CHECK-LIST INITIALS TIME ITEM .

Corrective actions completed with results as follows:

Surveys completed (Attach copies)

Radiation levels near those prior to emergency. List areas roped off 4

Type of access restored (circle)

Controlled / Unlimited i Restored access announcement made on PA system:

) (repeat twice): " Attention all personnel (attention all personnel), Recently (controlled or unlimited) to ( Specify area) is now permitted.

Units 2 and 3 notified.

Offsite agencies notified using: Follow-up Notification Form i

.i I Re-entry Coordinator Signature

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-61

UNITS 2 AND 3 NEW PAGE 2 of 2 j h ATTACHMENT 8.2

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1 NOTE: After this checklist is completed and is not required for immediate use, forward it to the Administrative Leader.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-62 ,

-(q , UNITS 2 AND 3 NEg Page 1 ACTIVATION OF T!!E RECR Mg RECEIVED e "'

U id Q T f B " "T U P b S F D OCT 1419gj FOR ST AR

1. OBJECTIVE pg Q'f h?EOgg .

gtE C0HTROL(tog / CDM SITE E,$T 1.1 The object <ve oV V g$ sed provide for the notificati 4- ac vation of the SONGS-2 and 3 Recovery Organizatio the transfer of control of emergency response operations from the Emergency Coordinator to the Recovery Manager.

1.2 The Emergency Coordinator has the responsibility for determining when an emergency condition at SONGS-2 and 3 has stabilized such that a recovery operation can begin. The Emergency Coordinator -

is responsible for implementing Part A of the procedure, while the Recovery manager is responsible for implementing Part B. The Emergency Coordinator and the Recovery Manager may make joint decisions in regard to the timing of the transfer of operation to the Recovery Organization.

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2.0 REFERENCES

.i

Le 3 a be a (ifVl fri, L } i-M{I 2.1 Emergency Procedure 5023-VII -11, " Recognition and Classification of Emergencies".

O V 2.2 SONGS-2 and 3 Emergency Plan.

2.3 Emergency Procedure 5023-VIII-61, "Re-entry".

2.4 Regulatory Guide No. 1.109.

3.0 PRE 0VISITES 3.1 An emergency response organization is functioning as a result of a declared emergency condition at SONGS-2 and 3 in accordance with the Emergency Plan.

3.2 The emergency conditions have stabilized to the point that the previous level of emergency response effort is ne longer required and the emergency is under control. The emergency condition may have been terminated.

3.3 The Emergency shall be considered under control and in the re-entry recovery phase only when the following general guidelines have been met:

3.3.1 Reactor and associated systems are considered to be in a safe, stable condition.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-62 NEW Page 2 p UNITS 2 AND 3

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3.0 PREREQUISITES (continued) 3.3 (continued) 3.3.2 Radiation levels in all in plant areas are stable or decreasing with time.

3.3.3 Release of radioactive materials to the environment from the plant are under control.

3.3.4 Any fire, flooding, or similar emergency conditions are controlled or have ceased.

3.3.5 Contaminated /injuret personnel, when the victim (s) has been transferred to a hospital, or has received appropriate medical treatment.

3.3.6 For emergency conditions classified as Unusual Events, when the specified corrective action has been taken and/or when the plant has been placed in the

() appropriate operating mode.

' t 3.4 Considerable plant damage has occurred and/or severe on-site radiological condit, ions exist as a result of the emergency such that the plant cannot resume normal operations with the normal organization.

3.5 The re-entry procedure may have be activated.

4.0 PRECAUTIONS 4.1 Recovery actions that plan for, or may result in, radioactive release will be evaluated by the Recovery Manager and his staff as far in advance of the event as possible. Such events and data pertaining to the release shall be reported to the off-site emergency response organizations and agencies listed in table 1 of Emergency Procedure 5023-VIII-16, " Notification". The follow-up notification form will be used for transmitting this

! information.

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5.0 CHECK-OFF LIST 5.1 Checklist fo- activation of the Recovery Orgar.ization (Attachment 8.3)

-v SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-62 NEW Page 3 UNITS 2 AND 3 6.0 PROCEDURE r

6.1 Part A, Emergency Coordinator Actions 6.1.1 Determine whether or not the emergency condition can be considered to be under control according to the prerequisites of Section 3.3. If the emergency appears to be under control, continue with this procedure, otherwise continue the emergency response actions required by the Emergency Plan Implementing Procedures.

NOTE: It is very unlikely that an Unusual Event will require activation of the recovery organization.

6.1.2 Notify the Recovery Manager to report to the Technical Support Center to.begin preparations for establishing the recovery effort.

NOTE: The Recovery Manager will be involved in the last phases of the emergency respoisse efforts in order to be familiar with the plant corditions. Other members of the

(]

V Recovery Organization will not be called for service until, at the discretion of the Recovery Manager, they are required.

6.1.3 Determine whether the criteria for termination are met, using Attachment 8.5 of Emergency Procedure 5023-VIII 11, " Recognition and Classification of Emergencies". If the criteria are met, proceed with this procedure, otherwise continue the emergency response actions required by the Emergency Plan.

NOTE: In case of a severe emergency involving off-site protective actions (such as sheltering and evacuation), the decision for termination shall then be made with the concurrence of the Recovery Manager, California State OES,0 range County, San Diego County, San Clemente, San Juan Capistrano, Camp Pendleton, California Department of Parks and the NRC. It will be the responsibility of the Emergency Coordinator to determine whether or not J

the concurrence of off-site agencies and organization is required for the termination decision.

Make the declaration of termination if appropriate.

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i 6.1.4 This declaration "can only be made" by the Emergency Coordinator, but may be arrived at jointly with others.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-62 NEW Page 4 m UNITS 2 AND 3 U

6.0 PROCEDURE (continued) 6.1 (continued) 6.1.4 (continued)

NOTE: This declaration and the subsequent notifications shall be made as promptly as possible after the criteria are met.

6.1.5 Announce or have announced over the station public -

address system, " ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL. THE EMERGENCY CONDITION (specify)

HAS BEEN TERMINATED AND THE PLANT IS IN A RECOVERY MODE. CHECK WITH YOUR SUPERVISOR PRIOR TO RE-ENTRY." (Make this announcement three times.)

6.1.6 Authorize notification of the termination of the emergency and the activation of the recavery phase to

! the off-site agencies and organizations listed in Table 1 (Attachment 8.1) of Emergency Procedure 5023-VIII-16, " Notification". Use the follow-up "ot4ric t'o" <=r- (^tt>ch e#* 8 5)-

O Determine jointly with the Recovery Manager whether 6.1.7

!. or not a Recovery Organization will be required and whether it will be short term or long term.

j

.1 Short-term recevery organization:

The Technical Support Organization under the direction of the Technical Support Leader will handle recovery efforts where post-accident conditions require minimal on-site support activity and are expected to be of short duration (several days).

.2 Long-term recovery organization:

In those cases where post-emergency conditions indicate that recovery operations will require extensive on-site support activity and extend over a long period of time (more than one week), SCE will shift from the existing emergency response organization to a long term recovery organization.

The functions of this long term recovery organization are listed in Section 9.0 of the Emergency Plan. The typical general recovery organization is shown in Attachment 8.1 and described in Attachment 8.2. The precise organization will depend upon conditions.

6.1.8 Activate the Re-Entry procedure.(5023-VIII-61) if re-entry is not already underway.

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4 SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE'5023-VIII-62 NEW Page 5 UNITS 2 AND 3

,- 6.0 PROCEDURE (continued) 6.1 (continued) 6.1.9 Brief the Recovery Manager on the existing plant conditions, any special plant situations and the status of personnel accountability.

6.1.10 Direct that all records related to the emergency be made available to the Recovery Manager (through transfer to the Administration and Logistics Manager).

6.1.11 Turn over management of emergency operations to the Recovery Manager.

NOTE: The Recovery Manager will subsequently establish a recovery center from which he will function.

6.2 Part B, Recovery Manager Actions.

6.2.1 Initiate a post-accident review. Following the termination of the emergency response phase of the accident and the commencement of recovery operation, l

appropriate evaluations to assess SONGS-1 conditions will be performed. The outcome of these evaluations will form the basis of recovery planning and licensee event reports to the USNRC. The scope of these evaluations will be consistent with the emergency classification, the nature of the initiating events, and the preliminary assessment of SONGS-1 equipment status. 3 6.2.2 Refer to Section 9.0 of the Emergency Plan for the organizational plan of the Recovery Organization.

6.2.3 Review the status of the re-entry operation if not complete and the immplications of the findings of the resulting investigation on the long-term recovery organizationsi requirements.

6.2.4 Activate the Recovery Support Organization and activate the recovery centers, as required.

6.2.5 Make notification to the off-site agencies and organizations listed in table 1 of Emergency Procedure 5023-VIII-16, " Notification", that a

\ recovery organization is now activiated.

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EMERGENCY PROCEDURE 5023-VIII-62 SAN ONOFRE NUCLEAR GENERATING STATION Page 6 1

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UNITS 2 AND 3 6.0 PROCEDURE (continued) 6.2 (continued) 6.2.6 Total Population Exposure Estimate The Recovery Manager / Designee shall make an estimate of the total population radiation exposure resulting from radioectivity releases (if any) during the emergency. Analyses will be perfomed to estimate -

population exposure from all applicable exposure pathways identified in Regulatory Guide 1.109. These analyses will utilize mordtceing and sampling data obtained during the emergency and the actual meteorological conditions. Emergency Procedures S023-VIII-42 and 23 provide guidana snd methods for analyzing the off-site radiological monitoring data.

6.2.7 Resumption of Operation SONGS-2 and 3 operation shall be permitted to resume only after repair or replacement of damaged systems and completion of any licensing review and approvals.

] 6.2.8 A report of the emergency and the recovery actions f shall be completed at the direction of the Recovery Manager or his designee.

7.0 RECORDS 7.1 All completed checklists and records are to be maintained by the Administrative leader (in the emergency response phase) and by the Administrative and Logistics Manager (in the recovery phase).

8.0 ATTACHMENTS 8,1 Typical Recovery Organization 8.2 Description of Recovery Organization 8.3 Checklist for Activation of the Recovery Organization.

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K. P. BARR HEALTH PHYSICS MANAGER f

JRB:0079F/sss I

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t SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-62 UNITS 2 AND 3 '4EW Page I of I ATTACHMENT 8.I f.-

TYPICAL GENERAL RECOVERY ORGANIZATION ,

VICE PRESIDENT, NUCLEAR ENGINEERING AND OPERATIONS RECOVERY MANAGER PUBLIC RELATIONS ADMINISTRATION AND LOGISTICS MANAGER MANAGER ADVISORY SUPPORT SCHEDULING AND PLANNING MANAGER MANAGER

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RADIATION PROTECTION PLANT OPERATIONS PANAGER PANAGER WASTE MANAGEMENT PLANT MODIFICATIONS MANAGER MANAGER TECHNICAL SUPPORT MAf4AGER I

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-62 j

NEW Page 1 of 2 f.

UNITS 2 AND 3 ATTACHMENT

8.2 DESCRIPTION

OF RECOVERY ORGANIZATION FUNCTIONS l

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1. Vice President, Nuclear Engineering and Operations The Vice President Nuclear Engineering and Operations of SCE is responsible for designating the senior personnel to fill dey positions in the long-term recovery organization.

2. Recovery Manager The Recovery manager is responsible for implementation and coordination of the overall technical aspects of the recovery operation. This includes overseeing the operations of the various functional groups and ensuring that all activities, proposed courses of action, and contingency plans receive proper analysis and coordination.

3. Public Relations Manager The Public Relations Maager is responsible for providing accurate, timely information to the public through the news media and coordinating with federsi, state, and local public relations officials. The Public Relations Manager is to be the single source for all public information.

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( 4. Administration and Logistics Manager

( The Administration and Logistics Manager is responsible for provicing necessary administrative / logistics requirements such as communications, manpower, transportation, commissary arrangements, accommodations, clerical support, records management, temporary office space and equipment.

5. Technical Support Manager The Technical Support Manager is responsible for providing technical engineering support, technical planning and analysis, control room technical support, procedure support, and data reduction and.managment.

6. Scheduling / Planning Manager ,

J The Scheduling / Planning Manager sets priorities, develops plans and schedules, coordinates and monitors the status of tasks, and reports on the work progress of all technical groups. Liaison with the Nuclear Regulatory Commission is also provided through the Scheduling / Planning Manager.

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SAN OC FRE NUCLEAR GENERATING STATION EMERGENCY FROCEDURE S023-VIII-62 A UNITS 2 AND 3 NEW Page 2 of 2

/V ATTACHMENT 8.2

7. Plant Operations Manager

The Plant Operations Manager is responsible for performing all plant operations and maintenance activities, terminating or minimizing off-site releases, stablilizing plant conditions, and restoring the plant's ability to function normally and respond to any further emergencies.

8. Radiation Protection Manager The Radiation Protective Manager is responsible for controlling and limiting personnel radiation exposures, development and /or approval of all health physics procedures, and in plant health physics management.

9. Waste Management Manager The Waste Management Manager is responsible for safely'and effectively managing the quantities of radioactive gases, liquids, and solids that might exist during the initial phases of recovery. Subsequently, this person is responsible for the development and implementation of short and long-term plans to manage and process contaminated solids, liquidr.,

and gases; quantifying the degrees of contamination of buildings and systems; and the establishment of processing priorities based on plant needs.

10. Plant Modifications Manager The Plant Modifications Manager is responsible for providing the engineerings, design, materials, and construction necessary to complete required modifications to plant systems, equipment, and structures.

11. Advisory Support Manager The Advisory Support Manager is responsible for objective review of potential problems, maintaining awareness of perceived plant and core status, and for providing independent assessment based on experience and judgment.

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SANONbFRENUCLEARGENERATINGSTATION EMERGENCY PROCEDURE S023-VIII-62 A UNIT! 2 AND 3 NEW Page 1 of 1

'U ATTACHMENT 8.3 CHECKLIST FOR ACTIVATION OF RECOVERY ORGANIZATION

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(Forward completed checklist to Administrative Leadar in TSC)

EMERGENCY COORDINATOR RECOVERY MANAGER __

ITEM INITIAL TIME DATE

1. Recovery Manager notified:

2. Termination criteria met:

Circle off-site agencies that give concurrence (if appropriate)

Cal. OES OC SDC SC SJC USMC PARKS NRC

3. Delcaration of termination:

4. Announcement on PA to SONGS personnel

, of termination:

5. Noticiation of termination to off-site

! I agencies. Begin:

Complete:

6. Required recover organization a) Short term (omit items 7-8):

b) Long term

7. Brief Recovery Manager on plant conditions and re-entry status:

8. Emergency Coordinator turns over managment of emergency operation to Recovery Manager:

Signed _ Date Time Emergency Coordinator Signed Date Time _

Recovery Manager ;

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s EMERGENCY PROCEDURE 5023-VIII-71 SAN ONOFRE NUCLEAR GENERATING STATION 91981 Paj,e 1 NEW EEP UNIT 2 AND 3

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NOT FOR CONSTRUCTION EM5094STARI41P USF ONLY

' CRECK APPLICABLE CONTROLLED STICK FILL FOR CURRENT INFORMATI0f!

1.0 OBJECTIVE AND REShmmluTY 1.1 To delineate the requirements for testing, evaluating, and documenting emergency drills as required by reference 2.1 and ensuring drills are carried out to measure emergency preparedness of SONGS personnel. The Emergency Planning Administrator is responsible for implementing this procedure.

R E C EI"--

OCT 141em

2.0 REFERENCES

2.1 San Onofre Nuclear Generating Station Units 2 and 3 Emef@ hth iF.

Plan.

3.0 PREREQUSITES 3.1 A complete scenario of the annual Radiation Emergency Exercise will be sent to the NRC for review and comment no less than 75 days prior to the scheduled drill. The NRC will be invited to observe the scheduled exercise by receipt of the Scenario.

4.0 PRECAUTIONS g . j 4.1 None.

5.0 CHECK-OFF LISTS (See attachment 8.1) 6.0 PROCEDURE 6.1 The Emergency Planning Administrator is responsible for the planning, scheduling and coordinating of all Emergency Plan related drills and exercises.

6.2 The Fire Brigade Training Coordinator is responsible to assist the Emergency Planning Admiristrator in conducting the Fire Emergency Drill l

6.2.1 At least one Fire emergency drill shall be conducted per calendar quarter per shift.

6.2.2 At least one Fire emergency drill every 12 months,

( +3 months) shall involve the participation of the Camp Pendleten Marine Corps Fire Department.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0?3-VIII-71 NEW Page 2

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6.D PROCEDURE (Continued) ,

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6.3 The Health Physics Manager is responsible to assist the Emergency Planning Administrator in conducting the following:

6.3.1 Radiation Emergency Exercise .

.1 A major exercise appropriate to a site or general emergency shall be conducted every 12 months, ( 1 3 months)

.2 Conduct of the exercise shall provide for the coordination with and participation of: offsite emergency response personnel, organizations and agencies; including those of state and county governments.

6.3.2 Radiological Monitoring Drill.

.1 The drill shall include collection and analysis of all appropriate sample media for both onsite and 3

offsite locations.

.2 A least one drill shall be conducted every 12 months, n

. V ( 13 months). I

< 6.3.3 Health Physics Drill.

.1 The drill will involve response tn, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment.

.2 At least one drill shall be conducted every 6 months

( 1 1 month).

NOTE: The Chemistry Supervisor will assist in development of all drills involving sampling.

The Station Services Manager is responsible to assist the 6.4 l

Emergercy Planning Administrator in conducting the Medical Emergency Drill.

6.4.1 Medical Emergency Drill l

.1 Involves the participation of some, if not all, of the local medical support personnel and i organizations, and will involve simulated cases of contaminated injured personnel and/or radiation overexposure

.2 At least one drill shall be conducted every 12 months,( 13 months).

SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-71 NEW Page 3 UNIT 2 AND 3 iO 6.0 PROCEDURE (Continued) .

6.5 The Station Assistant Maintenance Manager is responsible to assist the Emergency Planning Administrator in conducting the Repair and Damage Control Drill.

6.5.1 At least one drill shall be conducted every 12 months,

( 1 3 months) 6.6 The Station A:sistant Operations Manager is responsible to assist the Emergency Planning Administrator in conducting the -

Communications Links drill.

4 6.6.1 At least once per month the communications links to state and local government agencies within the 10 mile EPZ shall be operationally checked.

6.6.2 At least once every 3 months, ( ! I month) the commun* cations links to federal emergency response organizations and state agsncies within the 50 - mile EPZ shall be operationally checked.

6.6.3 At least once every 12 months, ( +3 months) the

' communications links between the nuclear facility, state O and local emergency operations centers and field assessment teams shall be operationally checked.'

6.7 Drill Implementation and Evaluation

! 6.7.1 All drill, will be planned, developed and conducted by the Emergency Planning Administrator through the use of the Drill packet. ( Attachment 8.1)

.1 The Drill Packet is a separate set of check-off sheets and forms that is used for any of the

' emergency drills conducted at the SONGS site.

.1.1 The purposes of the Drill Packet are:

a. To provide a step-by-step procedure for conducting a drill to ensure that all aspects of every drill are completed,

b. To provide a means of docume ting the fact tha6 a drill has been performed.

6.7.2 When a drill is required, the Emergency Planning Administrator shall obtain a Drill packet and begin at step 1, Attachment 8.1 of the procedure and then fc11ow the outline as indicated.

l SAN ONOFP.E NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-71

NEW Page 4 UNIT 2 AND 3

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,_ 6.0 PROCEDURE (Continued) 6.7.2 (Continued)

.1 The Drill Packet.shall not leave the Emergency Planning Administrator at any time during the conduct of the drill and he shall be responsible for ensuring that the entire Drill Packet is completed and j

i forwarded to the Training Department at the completion of the drill.

NOTE: Only Drill Evaluators and Observers not l directly involved may have access to the i

Drill Packet prior and during the Drill.

I j 7.0 RECORDS

! 7.1 None.

8.0 ATTACHMENTS 8.1 Drill Packet Check-off sheets

() 8.2 Drill Scenario Sheet 8.3 Emergency Drill Critique - Individual Action Item Assignment Sheet.

8.4 Emergency Drill Overall Assignment Sheet 1

8.5 Emergency Drill Evaluator and Observer Critique sheet D*

K. BARR l HEALTH PHYSICS MANAGER 0060F/KB/sss

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. O. EMERGENCY PROCEDURE S023-VIII-71

! SAN ONOFRE NUCLEAR GENERATING STATION Page 1 of 5 NEW l UNITS 2 AND 3

' A1TACHMENT 8.1 l

DRILL PACKET

1. Drill Classification and Scheduling t

The Emergency Planning Administrator shall check the appropriate' box l

below and note the date and time the drill is to be held.

DATE INITIALS Medical Emergency Date Time Fire Emergency Date Time Repair and Damage control Date Time Date Time Communications Links test Radiation Emergency Date Time Exercise Radiological Monitoring Date Time Health Physics Drill Date Time

2. Scenario Development and Routing The Emergency Planning Administrator and a designated assistant as indicated in section 6.1 of this procedure, shall be responsible for preparing the drill scenario. The scenario will be sent to the NRC for review and comment no less than 75 days prior to the drill.

DATE INITIALS Meet with designated assistant and develop emergency l

drill scenario Meet with the Supervisor of Plant Coordination and l

establish a date for the drill that will least affect plant operations'.

If the Drill will involve Corporate Management ensure that the personnel involved will be able to participate on the scheduled cate.

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- SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-71 NEW Page 2 of 5 UNITS 2 AND 3 ATTACHMENT 8.1 DRILL PACKET

3. Outsida Agency Notification The Emergency Planning Administrator is responsible for coordinating efforts with outside participating emergency personnel and organizations. Notification has been made to the agencies indicated below that will participate in or observe the drill DATE INITIALS l

Pendleton Coast Area Office - California Department of Parks and Recreations.

4 City of San Clemente.

Camp Pendleton - U. S. Marine Corps Base.

fg Orange County Control One - Department of Health

() San Diego County Office of Disaster Preparedness Station.

City of San Juan Capistrano Department of Energry (00E) Nevada Operations Office.

Nuclear Regulatory Commission, Bethesda, MD.

Resident Inspector and Region .

Ambulance Services.

(Specify)

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-71 UNITS 2 AND 3 NEW Page 3 of 5 ATTACHMENT 8.1 DRILL PACKET DATE INITIALS Other (Specify)

4. Notificatior of SONGS & SCE Departments DATE INITIALS a # ser =< "#cie r oa r t'e#,

O Supervisor of Hebth Physics and Emergency Planning SONGS Station Manager Assistant Station Manager Operations

< Supervisor Station Security.

Health Physics Manager Nuclear Affairs.

Media Relations.

All notifications will be made by m?co or phone contact prior to l sending the scenario to the NRC for review and comments. l

, l S. Observers The Emergency Planning Administrator is responsible for assigning Evaluators to monitor personnel and areas involved in the drill.

DATE INITIALS Assign all Evaluators and complete the Emergency drill Overall Assignment sheet (Attachment 8.4).

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCF9URE S023-VIII-71 UNITS 2 AND 3 NEW Page 4 of 5 ATTACHMENT 8.1 DRILL PACKET

6. Pre-drill Meeting DATE INITIALS Meet with all Evaluators and other personnel involved with the drill to brief them on scope, sequence of -

events and individual responsibilities.

Pass out Emergency Drill Evaluator and Observer Critique Sheets (Attachment 8.5) to all observers.

Prepare and pass out Drill Data Cards to appropriate observers.

Instruct each evaluator and observer to keep a log of all activities he observes during the drill to be turned in the Emergency Planning Administrator for

() reconstruction of the scenario.

Have all attending personnel fill out the appropriate Training Program Admin'.strative Form (PS50333).

7. Drill The Emergency Planning Administrator is responsible for commencing the drill as scheduled under part 1 of this Drill Packet DATE INITIALS Position all observers and ensure that the drill is initiated in a manner consistent with safe plant operations.

8. Post Drill Requirements.

Upon completion of the drill, the Emergency Planning Administrator is responsible for meeting with all evaluators and observers and holding a critique to review and discuss deficiencies and corrective actions.

DATE INITIALS Meet will all evaluators and observers to review their significant comments, and to collect all logs of observed activities Hold drill critique to review drill with all involved personnel.

Collect all Emergency Drill Observer Critique Sheets (Attachment 8.5)

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EMERGENCY PROCEDURE S023-VIII-71 SAN ONOFRE NUCLEAR GENERATING STATION NEW Page 5 of 5 -

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UNITS 2 AND 3 ATTACHMENT 8.1 DRILL PACKET

9. Action Items The Emergency Planning Admini.trator is responsible for initiating any >

Emergency Drill Critique Individual Action Item Assignment Sheets (Attachment 8.3) and assigning those action items to the EPAL (Emergency Planning Action List) computer tracking system with the appropriate priority code based upon recommendations as a result of the drill.

DATE INITIALS Initiate all required Emergency Det11 Critique Individual Actions Item Assignment Sheets (Attachment 8.3), and forward them to the appropriate manager for action. ;

10. Documentation of and Routing of Drill and Critique Re.sults.

DATE ~IhlTIALS ,

'- Prepare and distribute to all SONGS Department Heads a memorandum detailing the results of the drill.

Forward the completed drill packet to training.

Items included in the drill packet are the following; Training Program Administrative forms (PSS0333)

Drill Scenario and Cover Sheet (Attachment 8.2).

Copy of Drill memcrandum sent to all Department Heads.

Emergency Drill Observer Critique Sheets (Attachment 5)

Emergency Drtil Observer Assignment Sheet (Attachment 4)

Completed Drill Packet Cbeck-off Sheets (Attachment 1).

11. Action Iter Assignment Sheets

- The Emergency Planning Administrator shall maintain a file -f "open" Individual Action Item Assignment Sheets for each drill and enter these in the computerized SONGS Emergency Planning Action List (EPAL) under the appropriate Priority Code. Once all action items for a particular l

l f) drill are closed out, the Emergency Planning Administrator shall forward them to the Manager of Training for filing with the Drill Packet 1

EMERGENCY PROCEDURE SO23-VIII-71

' ' SAN ONOFRE NUCLEAR GENERATING STATION NEW Page 1 of 3 ,

UNITS 2 AND 3 l l ATTACHMENT 8.2 i

DRILL SCENARIO The folicwing Scenario was developed by:

SIGNATURE NAME TITLE

/

1.

/

2.

/

/ __

2.

Approval of Date of Exercise By:

(Annual Radiation Date Emergency Manager of Nuclear Operations Exercise)

O SONGS Station Manager Date Review and approval of Scenario By:

(Not participating Date drill)

Watch Engineer (SRO)

Date Emergency Planning Administrator NOTE: Only the Emergency Planning Administrator, one SRO not participating in the drill, and evaluators can Observers have access may to the drill scenario prior to the drill.

have a copy on the day of the drill for observation purposes. Copies of the scenario were issued to the following people: 1 SIGNATURE DATE ORGANIZATION COPY #

NAME

/ /

1.

/ /

2.

/ /

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-71 UNITS 2 AND 3 NEW Page 2 of 3

, c,

! ATTACHMENT 8.2 1

DRILL SCENARIO i

i Type of Drill:

I Date and time to be conducted:

Objectives: (including participation of offsite organizations) 1 1.

i 2 3.

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023 4III-71 i ' NEW Page 3 of 3 e UNITS 2 AND 3 ATTACHMENT 8.2 I DRILL SCENARIO Detailed Scenario: (Use Additional sheets as necessary)

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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-71 NEW Page I of I UNITS 2 AND 3

' ' ' ATTACHMENT 8.3 I EMERGENCY DRILL CRITIQUE INDIVIDUAL ACTION ITEM ASSIGNMENT SHEET DRILL ACTION DATE RESPONSIBLE DEPARTMENT ACTION ITEM DUE DATE ACTION RECOMMENDED L

Emergency Planning Administrator

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ACTION TAKEN:

ITEM CLOSE OUT DATE DEPARTMENT HEAD RETURN TO EMERGENCY PLANNING ADMINISTRATOR NOTE: EMERGENCY PLANNING ADMINSTRATOR FORWARD TO THE MANAGER OF TRA FILE WITH DRILL PACKET.

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EMERGENCY PROCEDURE S023-VIII-71 SAN ONOFRE NUCLEAR GENERATING STATION Page 1 of 1 NEh' UNITS 2 AND 3

' ATTACHMENT S.4 EMERGENCY DRILL OVERALL ASSIGNMENT SHEET TYPE OF EMERGENCY DATE l

i OBSERVER AREA 0F RESPONSIBILITY 1.

2.

, 3.

4.

5.

O e.

7.

8.

9.

10.

l 11.

12.

13.

14.

15.

16.

17.

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l O EMERGENCY PROCEDURE S023-VIII-71 SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 NEW Page 1 of I

' ATTACHMENT 8.5 EFERGENCY DRILL EVALUATOR AND OBSERVER CRITIQUE SHEET DATE OBSERVER / EVALUATOR TYPE OF DRILL .

AREA 0F RESPONSIBILITY TIME: EVENT:

COMMENTS (Include safety concerns, procedure adequacy and compliance, radiological (ALARA), material, etc)

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l EMERGENCY PROCEDURE S023-VIII-72 SAN ONOFRE NUCLEAR GENERATING STATION: NEW Page 1 UNIT 2 AND 3 DCT E s8 de EMERGENCYEQUIPMEdINX5NE0R \

1.0 OBJECTIVE gt) .

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2.0 REFERENCES

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2.1 San Ono ' e neFatingStationUnit2/3Emergeg.,PgpF, 3.0 PREREQUISITES 3.1 None 4.0 PRECAUTIONS 7 r=

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h" i 4.1 None . L L. E' L w e 5.0 CHECK-OFF LISTS See 8.0, Attachments 6.0 PROCEDURE

) 6.1 Responsibilities 6.1.1 It is the responsibility of the Emergency Planning Administrator to ensure that all emergency kits listed in Attachment 8 are inventoried when specified.

6.2 Instruction 6.2.1 Using the appropriate checklist (Attachment 8) perform the following:

.1 At quarterly ( + 1 month) intervals and after each use the Emergency Planning Administrator will designate Health Physics personnel to perform inventories of emergency equipment.

NOTE:

If a lockwire on an emergency equipment locker is found broken, the Health Physics staff will nctify the Emergency Planning Administrator, who will then direct an immediate inventory to be performed on that locker.

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UNIT 2 AND 3 6.0 PROCEDURE (continued) t 6.2.1 (continued)

.2 Health Physics personnel will break the lockwire, open the locker, visually inspect all equipment and replace any equipment showing deterioration. Note any replacement items in the appropriate column, and rote, under REMARKS, why the ittm was replaced.

.3 Verify that all items requiring them have expiration dates. If there is no expiration date on an item requiring one, replace the item with one possessing i

an expiration date.

.4 Replace all items with past due expiration dates.

Note the new item expiration date in the appropriate column of the checklist.

.5 Verify that calibration dates on instruments requiring calibration are not past due. Replace any instruments with past due calibration dates and note i

the new calibration date in the appropriate column.

.6 During the first inventory of the calendar year, replace all spare batteries with fresh batteries.

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NOTE Indicate that battery replacement has been accomplished in the " Remarks" section of the Inventory list for applicable items.

.7 Kit inventories are considered complete when all required items are present, all instruments are within the calibration and expiration dates and all instruments are functioning properly.

.8 After rectifying noted deficiencies, lockwire shut

' the emergency equipment locker door.

.9 Ater inventory, sign and date the attachment. All completed inventory lists will be forwarded to the Emergency Planning Administrator.

7.0 RECORDS 7.1 The Emergency Planning Administratcr shall forward the records to EDM with the appropriate n 9.

8.0 ATTACHMENTS 4

O 8.1 Attachment 1 - Emergency Response Kit V

8.2 Attachment 2 - Control Room Emergency Kit

EMERGENCY PROCEDURE SO23-VIII-72 SAN ONOFRE NUCLEAR GENERATING STATION Page 3 NEW i

UNIT 2 AND 3 0 (continued) l 8.0 ATTACHMENTS

? Attachment 3 - Operational Support Center Emergency Kit I . 8.3 8.4 Attachment 4 - Technical Support Center Emergency Kit i

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