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Public Version of Emergency Plan Implementing Procedures, Including Procedures EPIP-01 Re Classification of Emergency conditions,EPIP-02 Re Unusual Event & EPIP-03 Re Alert
	ML20050D369
Person / Time
Site:	Oyster Creek
Issue date:	03/12/1982
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20050D362	List: ML20050D364; ML20050D369;
References
	PROC-820312-01, NUDOCS 8204120160
	Download: ML20050D369 (175)
	v • d • e

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EMERGENCY PLAN IMPLEMENTING / ADMINISTRATIVE PROCEDUddS INDEX PAGE DATE 1 3/12/62 2 3/12/82 3 11/4*/o1 4

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, 3/12/o2 Page 2 of 3 EPIP AND EPAP TITLE LISTING EMERGENCY PLAN IMPLEMENTING PROCEDURES LASI LASf PROCEDURE # TITLE REV. NO. diV. Daft EPIP - 01 Classification of Emergency Conditions 2 3/2/82 EPIP - 02 Unusual Event 2 3/2/82 EPIP - 03 Alert 2 J/2/o2 EPIP - 04 Site Emergency 2 3/2/o2 EP IP -- 05 General Emergency 2 J/2/62 EPIP - 06 Not Issued ;

EPIP - 07 Personnel Injury 1 2/23/d4 4 EPIP - 08 Fire 1 2/10/o2 l EPIP - 09 Offsite Dose Assessment 1 2/23/o2 EPIP - 10 Emergency Radiological Survey - Onsite 0 2/19/dl I EPIP - 11 Emergency Radiological Survey - Offsite 1 J/u4/d2 EPIP - 12 Personnel Accountability 2 1/27/d2 EPIP - 13 Site Evacuation and Personnel Accountability Af ter Site

( . Evacuation 1 2/l7/d2 EPIP - 14 Damage Control 0 2/23/61 i EPIP - 15 Toxic / Flammable Gas Release 1 2/10/d2 EPIP - 16 Radioactive Liquid Release 0 2/23/dl l EP IP - 17 Activation of the Parsippany i Technical Functions Center 0 2/26/s2 l EPIP - 18 Activation of the Remote Assembly Area 0 2/23/ol i EPIP - 19 Emergency Dosimetry 1 2/17/o2 l EPIP - 20 Tornado /High Winds Delete 2/19/62 l EPIP - 21 Personnel Decontamination 1 2/19/d2 1 EPIP - 22 Search and Rescue Operations 0 2/24/61 EPIP - 23 Thyroid Blocking 1 2/19/82 EPIP - 24 Emergency Respiratory l Equipment 0 2/19/o2 i EPIP - 25 Activation of the Nearsite Emergency l Operations Facility 0 2/24/dl ;

EPIP - 26 Activation of the Technical Support Cente r 0 2/24/81 '

EPIP - 27 Activation of the Operations Support Center 0 2/24/dl EPIP - 28 Activation of the Farsite Emergency Operations Facility 0 2/24/dl EPIP - 29 Recovery Operations 1 3/04/o2

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,,a I 11/24/81 r Page 3 of 3 EMERGENCY PLAN IMPLEMENTING PROCEDURES LAST LAST PROCEDURE # TITLE REV. NO. REV. DATE A

ADMINISTRATIVE PROCEDURES EPAP - 01 Emergency Plan Implementing Procedure Format Delete EPAP - 02 No t Issued EPAP - 03 Not Issued EPAP - 04 No t Issued EPAP - 05 Emergency Equipment Inventory 0 2/27/81 EPAP - 06 Emergency Preparedness Training 0 2/24/81 EPAP - 07 Radiological Survey Team Training 0 2/24/81 EPAP - 08 Fire Brigade Training 0 2/24/81 EPAP - 09 Of fiste Fire Department Training 0 2/24/81 EPAP - 10 First Aid Training 0 2/24/81 EPAP - 11 Offsite Medical Personnel Training 0 2/24/81 EPAP - 12 No t Issued

(\ EPAP - 13 Emergency Plan Implementing Procedure /

Administrative Procedure Comment, Feedback and Evaluation Procedure 0 2/24/81 EPAP - 14 , Emergency Plan Implementing Procedure /

Administrative Procedure Review /

Revision Procedure 0 2/24/81 EPAP - 15 Emergency Response Mobilization (Proposal)

EPAP - 16 Maintaining Emergency Preparedness - 0 2/24/81

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' Procedure No. l

_EP E R.E MM EPIP-1 Page 1 Of 4 l Oate issued Effective Date Jersey Central 2,19,s1 3,9fe2 _ 3,19,s2

- Power & Light Company Revision No. Date 2 3/2/82 SUDject: Classification of Emergency Conditions Authertred By o qq 3 3 Director - Station Operations l ,

Appropkl/ 3/110( rrb.

uC i. % Cr 5@tl&LX i Projecg [

! Oyst$. Creek Nuclear denerating Station l

l l LIST OF EFFECTIVE PAGES DATE REVISION NUMBER l l

( 1 3/2/82 2 2 3/2/82 2 3 3/2/82 2 4 3/2/82 2 l

( ATTACINENTS Attachment 1 (5 pages) 3/2/82 2 l

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t NON-CONTROLLED E D cument Will Not Be Kopt Up To Date t

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Sootect: Procerure No.

Classification of Emergency Conditions EPIP-1 Aq3 2 af 4 Nges Revision N o. I"

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1.0 INTRODUCTION

1.1 The purpose of this procedure is to define tnose conditions wnicn f shall be classified as emergency conditions at Oyster Crees I Nuclear Generating Station and and to provide duidance in classifying such conditions.

1.2 Emergency classifications shall be made as soon as possible after confirmation of exceeding Eme rgency Action Mvels to ensure tnat proper protective and corrective actions are implemented and tnat appropriate offsite authorities are promptly notified (witnin 15 minutes). Utilization of this procedure during continuous emergency assessment activities will aid in the identification of changing emergency action levels prompting emergency conditton reclassification.

f i 1.3 Emergency conditions can be classified into one of four f categories. These categories are:

1.3.1 Unusual Event - The occurrence of an event or events that indicate or allow recognition of a potential degradation of the level of safety of tne plant, including contaminated injuries of plant personnel wnien require offsite emergency treatment. j I

I 1.3.2 Ale rt - The occurrence of an event or series of events f that indicate and allow recognition of an actual or i potential substantial degradation of tne level of safety l

, of the plant.

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l 1.3.3 Site Emergency - Accidents in wnich actual or linely I major failures of plant functions needed for protection of the public have occurred. This emergency class includes accidents wnich have a significant radiation release potential.

1 1.3.4 General Emergency -

Accidents vnich involve actual or I imminent substantial core degradation or melting witn {

potential for loss of Reactor Building (containment) !

integrity, and other accidents that nave large i radioactive release potential, suen as, fuel nandling l and waste gas system accidents.

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l 1.4 De finitions l 1

1.4.1 Emergency Action kvels - Define specific limits, parameters or equivalent status for establisning eacn emergency classification. Specific instrument readinds.

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Suspet: Frecxura No. l Classification of Emergeacy Conditions EPIP-1 PMa 3 of 4 seges l Revision N o. 2 Cate 3/2/d2

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alarm points and/or indications are also included for easy recognition of the emergency condition. Ine re is a natural progression of implementation criteria to be used by the Emergency Director as the initiating event escalates in severity, specific cnaracteristics of tne event are defined in order for tne Emerdency Director to implement the proper protective and corrective actions.

1.4.2 Emergency Ac tions are procedureal guides for use oy tne Emergency Director. These actions are specified in Section 4.0 of the Emergency Plan Implementing Procedures. The Eme rgency Director may omit specific actions that are not necessary for the emerdency condition and actions need not necessarily be performed in the order listed buti all should be completed witn ;

initials or N/A for non-applicable items.

1.4.3 Emergency Plan Implementing Procedure (EPIP) References are listed to alert the Emergency Director to otner EPIP's which may need to be implemented for specific situations.

~2.0 ATTACHMENTS 2.1 Attachment 1, Matrix of Emergency Action Leve ls for dmerdency Classification.

3.0 EMERGENCY ACTION LEVELS 3.1 As stated in Attachment 1 4.0 EMERGENCY ACTIONS 4.1 The Group Shift Supervisor / Emergency Director upon recognition of inplant or site conditions that have exceeded or nave a potential to exceed any emergency action level shall:

4.1.1 Immediately evaluate emergency initiating conditions for the highest emergency classification concition that may have been exceeded.

NOTE: Attachment I (Matrix of Initiating Condtttons tor Emergency Classification) of the procedure will i aid in rapid identification of the appropriate l emergency classification condition.

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, Sustect: hece:ure No.

Classification of Emergency Conditions EPIP-1 214e 4 :/ 4 3 ages Revision Ng 2 ate 3/2/82 4.1.2 Classify the emergency condition upon confirmation that emergency action levels have been exceedea as cefinea in Section 3.0 of EPIP-2, EPIP-3, EPIP-4 or EPIP-5, as appropriate.

4.1.3 Implement the appropriate Emergency Classification Procedure and assume the duties of the Emergency Director until properly relieved.

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, Sanen: P'ec:cre Na l Classification of Enargency Conditions EPIP-1 Fego L :f 5 2cges l Rension N o. 2 lafe 372j32

< e ATTACHMENT 1 HATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT EMERGSNCY EM6dGdnGY EPIP-2 EPIP-3 EPIP-4 LPIP-5 Radiological Effluent Releases Offsite/ Site offsite/ Site Pe rime ter Pe rime te r Gaseous Tech Spec. Tech Spec. >5mden/n r >50 mrem /n r Iodine Limits Limits for 1/2 nr Wnole Body Particulate Exceeded Excee'ded by a Whole body >250 mrem /nr factor of 10 >25 mrem /n r Cnild Inyrola Child Enyroid Liquid ' 10CFR20 Appendix B, Column 2 -- -

Limits exceeded in discharge canal Projected

Of fsite Doses .

Whole -

>10 mrem >50 mrem >100 mnem Body Child >50 mrem >250 mrem 3500 mrem Thyroid Reactor Pressure >1110 PSIG > 1239 PSIG >1375 PSIG --- =-

RCS Leakage (Into Primary l Containment) l Unidentified >5 gpm = -

l leak rate ]

1 Total leak >25 gpm >50 gpm WLOO gpm Reactor water )

rate or or Level cannot Requires or CRD pump be maintainea causes scram capacity is above top of exceeded Active fuel OE leak rate exceeds available l l

(. maxe up rate l

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Suoint: P4caturo No.

Classification of Emargency Conditions EPIP-1 Peg 3 2 sf 3 8cqos Revision N o. 2 :ste 3/2/d2 ATTACHMENT 1 (cont'd)

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENdRAL EVENT ALERT EMERGENCY 'ididGcNC Y EPIP-2 EPIP-3 EPIP-4 EPIP-5 RCS Total Iodine >8.0 uCi/cc >300 uCi/cc Indication of Activity fuel cladding degradation. ---=- ----

Los s o f coolaole geometry Of f-Gas Monitor >3,330 mr/hr >10,000 mr/nr Reading and and/or an Fuel cladding

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Fuel Status increase of failure -- -= -==-

666 mr/hr in 30 min.

RCS Isolation / Valve does not Main Steam Steam Line l RCS Safety / Close Line Break Break outside Relief Valve with MSIV Containment = ===

Status Malfunction w/o isolation causing leakage into Turbine Building Reactor Valid safety Failure to 1. LOCA w/

Protection circuit trip or initiate and -

failure or dCCS Systems Manual . complete a to perform

, Initiation " scram" Reac tor leading to core resulting in remains critical meltdown or ECCS activation - --

degration.

and discharge to Reactor Vessel 2. Transient plus failure or requisite core snutdown ;

systems could lead to melt-down witn j containment <

failure. f u

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- l Suotect: P*oce:ure No. l C1sssification of Emirgency Conditions EPIP-1 Fog 3 3 sf j seq:s Aevision Na 2 :ote 3fjf32 l l

f l ATTACHMENT 1 (cont'd) l MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION J PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT iMERGdNCY dMcRGdaCY EPIP-2 EPIP-3 EPIP-4 EPIP-5 Loss of Tech. Spec.

Containment requires ------ ---

Integrity shutdown Loss of 1. Loss of 1. Uncontroll- 1. Snutdown Engineered functions able decrease occurs out cecay l Saftey Features necessary to in fuel pool neat removal bring the water to capaoility j plant to below level is lost Gore shutdown of fuel degradation or

2. Loss of 2. Damage to melt could l Annunciators spent fuel occur.

in Control during 2. Iranstent j Room for refueling occurs in con- I

< l5 min. 3. Loss of junction wttn

3. Evacuation functions failure or core i of Control necessary to snutcown systems Room, Control achieve not Core meltdown established standby and containment l

, at local 4. Loss of failure likely. l stations witn- Annuncia to rs l in 15 minutes. in Control

4. Fuel hand- Room >15 min.

ling accident 5. Control at l l

or other local stations event resulting not establisned in unexpected witnin 15 min.

increase of implant radio- l activity levels l by a factor of l 100 Toxic or No habitability Habitability Enters Vttal I flammable gas problems problems but Area and release - near no vital areas restricts = ==

j or onsite effected or necessary l access re- access I stricted.

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, Suotect: Procerura No.

Classification of Emergency Conditions EPIP-1 Faqs 4 :f 5 seges Rowsion N o. 2 : ore 3/2/62 i

ATTACHMENT 1 (cont'd)

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY id6dGtNCf EPIP-2 EPIP-3 EPIP-4 EPIP-5 Security Security threat Ongoing Lmninent loss Loss or Compromise attempted entry compromise. of pnysical pnysical or sabotage No imminent. control of control or loss of plant plant occurs physical control of plant Loss of Power 'Offsite Power Offsite and Offsite and j or onsite power onsite power Onsite or but not both or vital D.C. Vital D.C.

power for exceeds 15 min. l 15 min.

(I Natural 1. Windspeed 1. Windspeed 1. Windspeed Phenomena > 75 mph >100 mph > L25 mpn i

2. Flood level 2. Flood 2. Flood Level l

< design level level near > design level l

with probable design level 3. dartnquane l flooding of 3 Tornado > SSE levels j evacuation strikes vital 0.22 g. l routes plant structures l 1

Fire Fire not under Affecting Affecting safety control within plant safety systems required == -----

10 minutes. systems not for snutdown l No safety required for- I systems shutdown l affected 1

4 Explosion No Damage to Affecting Affecting l within Security facility facility safety systems Protected Area affecting operations but required for -- ---------

operations not safety shutdown systems required for snutdown k

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Classification of Emergency Conditions EPIP-1 Peqe 5 Of 3 2cqes Revision N o. y ote g

Y ATTACRMENT 1 (cont 'd )

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICAIIOn PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUAUAL SITE GENERAL EVENT ALERT EMERGENCf dandGedCf EPIP-2 EPIP-3 EPIP-4 EPIP-3 Contaminated Require s Injury transportation

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to offsite hospital Aircraft Crash Onsite - no Strikes Affecting vital or station Station struc- structures of Missile Impac t .s truc ture s cure - No impact or fire affected damage to vital instrument Turbine Rotating Casing Failure component penetration

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failure with no casing

_ penetration i

Plant Status Requiring Warrants Warrants Any event l or conditions increased activation activations of potentially as evaluated awareness of of TSC, OSC Eme rg . Ct rs . , damaging tne by GSS plant opera- Monitoring plant resulting tions Teams, cg; in core degrada-precautiona ry tion or loss or public notice plant control I

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Procecure No.

Cate issuec e uve C te Jersey Central 1 3/1:/e: - 3/: /S:

, 2/22/s1

. Power & Light Company Revisen No.

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,, ,9 l duDject: Unusual Event AuthCrl:ec Sy Director - Station Operations A A A !

Apprb tat djilctJ -

W. . ; ft 3Tt w w D-l er Creek Nucle Generating Station LIST OF EFFECTIVE PAGE DATE REVISION NUdddR 1 3/2/82 2 2 3/2/82 *2 l

3 3/2/82 2 !

l 4 3/2/82 2 5 3/2/82 2 6 3/2/82 2 7 3/2/82 2

( 8 3/2/82 2 9 3/2/82 2 10 3/2/82 2

. l ATTACHMENTS i Attachment 1 (2 pages) 3/2/82 2 Attachment 2 (1 page) 3/2/82 2 Attachment 3 (4 pages) '3/2/82 2 Attachment 4 (1 page) 3/2/82 2 Attachment 5 (2 pages) 3/2/82 2 NON-CONTROLLED '

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Suotect:

P*oceruro No. I i Unusuni Evant EPIP-2 4 43 2 Of 10 8ecs !

mension No. 2 3/2/82 )

e 1.0 PURPO SE 1.1 The purpose of this procedure is to define the conditions that ~

shall be rega rded as an Unusual Event for Oyster Creek ~ Nuclear Station and to:

1.1.1 Ensure necessary actions are taken to protect the health and safety of the public.

1.1.2 Ensure necessary actions are taken to notify offsite emergency response organizations.

1.1.3 Mobilize the appropriate portions of the emergency response organization Eo initiate appropriate emergency actions. ,

1. 2 The Emergency Director is responsible for implementing this procedure.

1.3 Emergency Director responsibilities that may NOT be delegated

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include: l 1.3.1 Decision to notify offsite emergency management i l

s agener' e s.

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

1.3.3 Classification of Emergency Event 1.3.4 Determining the necessity for onsite evacuation based upon potential exposure to non-essential personnel, j 1.3.5 Authorization for emergenc7 workers to exceed 10 CFR 20 radiatio'n exposure limits. I 2.0 ATTACHMENTS .

2.1 Attachment 1, Communicator's Checklist 2.2 Attachment 2, Initial Notification Message 2.3 Attachment 3, Additional Information Message 2.4 Attachment 4, INP0/ANI Notification Message 2.5 Attach ent 5, OCNGS Station Status Checklist (BRP) l l

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EPIP-2 hCO 3 Of 10 Nges Unusual Event Revision N o. Octe 3.0 EMERGENCY ACTION LEVELS PARAMETER INITIATING CONDITION I

RADIOACTIVE 3.1 RELEASE EXCEEDS TECHNICAL SPECIFICAfION LIMIf EFFLUENTS Indications: Valid Stack Gas dign High Alarm.

Stack sample analysis for Iodine and/or l particulates exceed Tecn. Spec.

1 NOTE: PLANT STACK EFFLdENT IECdNICAL SPECIFICAfI0m The maximum r,elease rate of gross activity except l iodine and particulates witn half lives longer ,

tnan eight days shall oe limited in accordance l 0.21 with the rollowing equation: Q= wnere Q is the stack release rate (Ci/sec) of dross activity and 6 is tne average damma energy per disintegration (Mev/ dis).

CAUTION: IF THE READING EXCicDS 10 IIncs far.

ABOVE LIMIT, PROCEED IO TdE id.idt CLASSIFICATION iPIP-3.

Ihe maximum release rate of iodine and particulates witn half lives Londer enan eignt days shall not exceed 4 uCi/sec.

CAUTION: IF THE RELEAS6 RAI4 0F 100ldt,3 add PARTICULATES EXCEED 40 uCi/sec Fx0CLED TO THE ALERT CLASSIFICAIION EPIP-3.

NOTE: DISCHARGECANAL EFFLUENT TECHNICAL SPECIFICAIION O Ihe release of radioactive liquid effluents snall be limited such that the concentrations of radionuclides in the disenarge canal at ene site boundary shall no t- at any time exceed tne concentrations given in Appendix 3, Column 2 or 10CFR20 and notes 1-5 thereto. :

PROJECTED 3.2 CAUTION: IF OFFSITE DOSE DUE IO Tdi EVdHI IS edOJr.CIdu 0FFSITE TO EXCEEDED 10 mrem TO THE 4 HOLE BODY On DOSES 50 mrem TO THE CHILD IdYdOID, PROC 4r.D f0 fad 4 Lear EMERGENCY CLASSIFICATION EPIP-3

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Unusual Evant EPIP-2 40 .* :f to actes !

Revision N o. y :ste g PARAMETER INITIATING CONDITI'ON REACTOR 3.3 EXCEEDS 1110 PSIG PRESSURE CAUTION: IF REACTOR PRESSURE dXCEdDS 1239 PSIG, PROCEED TO THE ALERT CLASSIFICATION iPIP-3.

REACTOR 3.4 EXCEED TECHNICAL SPECIFICATION LLiIT COOLANT SYSTEM Unidentified leak in containment exceeds 5 GPM.

LEAKAGE As maybe indicated by "Drywell Sump Hi leak date" alarm and recorder indicator readings.

Total Leakage into containment from unidentified anc identified sources exceed 25 GPM. As may De indicated by "DWEDT Hi I4 vel" ala'rm g "Botn DWEDT Pumps dunning" alarm and leak rate calcuations using integrater readings.

CAUTIONS: IF REACTOR COOLANT LEA 4 RAIS dXCLEDS 50 GPM, PROCEED TO THE ALERT CLASSIFICATION iPIP-3.

REACTOR 3.5 EXCEEDS REACTOR COOLANT RADI0ACTIVIfY frCddICAL COOLANT SPECIFICATION f

SYSTEM i TOTAL Total Iodice concentration in coolant exceeas d.0

' IODINE uCi/cc as may be indicated by one of the following ACTIVITY alarms: " Reactor Water Hi-di Conductivity" og "dain Steam Line Hi Rad" E "Hi Rad Of f Gas" and confirmed oy sample analysis CAUTION: IF REACTOR COOLANT SYSTEM 10DIdi ACIIVIff EXCEEDS 300 uCi/cc, OR OFF-GASS AIR dJECIORS INDICATE GREATER TdAN 1.49 Ci/Sec CORRESPONDING TO A READING OF 10,000 mr/nr, PROCEED TO THE ALERT CLASSIFICATION iPIP-3.

OFFCAS . 3.6 OFF-GAS MONITORS INDICATE GREATER THAN 3,330 mr/nr MONITOR READING Corresponding indication of this value on any off das AND FUEL monitor will equate to 500,000 uCi/sec.

STATUS RCS 3.7 FAILURs'TO CLOSE FOLLOWING REDUCTION OF APPLICABL4 SAFETY / PRESSURE RELIEF VALVE As may be indicated by " Safely Valve or delter Valve STATUS Not Closed " Alarm and T,dgemeter display verified oy "Re lie f Valve Disenarge/delief Valve Downcorner Temperature Recorder Indicator og Accousticata Monitoring System.

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Suotect Presrure % ;l EPIP-2 Esse 5 sf 10 seges !

l Unusual Event

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PARAMETER INITIATING CONDITION l l

l OFF-GAS MONITOR INCMASE BY GREATER TdAN 666 mr/nr 1 WITHIN THIRTY MINUIES l Corresponding indication of this value on any off-gas l monitor will equate to greater enan 100,000 uCi/sec within thirty minutes. 7 i

I CAUTION: IF OFF-GAS MONITORS INDICAT6 GdsArtd fnAn i l 10,000 mr/hr CORRESPONDING TO A INDICATI0a OF f

1.49 Ci/see or IODINL ACfLVIIf SAcccus 300 !

uCi/ce , PROCETD TO TdE ALERI CLASSIFICATIUd EPIP-3. ,

I REACTOR 3.8 VAILD SAFETY CIRCUIT TRIP OR MANUAL INIIIATION RESULIING <

PROTECTION IN ECCS ACTIVATION AND DISCdARGE TO REACf0R Vessch $

SYSTEM LOSS OF 3.9 REQUIRES SHUTDOWN BY TECdNICAL SPECIFICATIONS ,

CONTAINMENT INTEGRITY Any condition whereoy Technical Specification 3.5.A is exceeded in the judgement of tne GSS. Primary containment integrity shall be maintained at all times when the reactor is critical or when temperature is l

' above 2120 F and fuel is in ene reactor, except wnile l performing low power physics tests at atmospneric pressure during or af ter refueling at power levels not to exceed 5 MWt.

3.10 REQUIRING SHUTDOW BY TECHNICAL SPECIFICAIIOns l LOSS OF l

ENGINEERING SAFETY At indicated by a loss of tne ability to meet any one l FEATURES of the conditions requiring ~ shutdown oy Tecnnical l Specification limiting condition of Operation in ene judgement of the GSS.

T0XIC OR 3.11 NEAR OR ONSITE T0XIC OR FLAMMAdLE CAS RELEASE.

FLAMMABLE GAS CAUTION: IF T0XIC OR FLAMMABLE GAS EdTERS fd8 FACILIff AND PRESENT HABABILITY PROSLEMS, PROCEED IO THE ALERT CLASSIFICATION SPIP-J.

SECURITY 3.12 SECURITY THREAT OR ATTEMPTED ENTRY OR SAdOTAGE COMPROMISE As judged by the GSS witn the advice of tne Site l Security Sergeant.

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Suspect: P'oca urs No. i EPIP-2 F10 o :f to 8:qes I Unusual Event 8 ewsion N o. , :ste g l

l PARAMETER INITIATING CONDITION j CAUTION: IF THE SECURITY COMPROMISE IS ON-GOIWG, PROCEEED TO THE ALidI CLASSIFIC4IIOn cPIP-3.

LOSS OF 3.13 UPON OCCURRENCE OF LOSS OF OFFSITE AC P042R POWER CAUTION: LOSS OF OFFSITE AND OdSIIE AC P0 win SUPPLIrs, l

PROCEED TO THE ALERT CLASSIFICAIION LPIP-3. t l LOSS OF ONSITE AC POWER CAPABILITY CAUTION: LOSS OF OFFSITE AND ONSITE AC POWER SdPPLIdd, PROCEED TO ALEAT CLASSIFICAIION iPIP-3.

CAUTION: LOSS OF PLANT DC POWER, PROCEED TO Tdd ALidt i EMERGENCY CLASSIFICAIION EPIP-3 l l

1 NAUTURAL 3.14 TORNADO / STORM PHENOMENA Warning, probable impact on plant. l l NOTE: Warning will be received from JCP&L System Dispatcher, Morristown, N.J.

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' Winds in excess of 75 mpn j l

CAUTION: IF, WIND SPEED EXCELDS 125 MPd, PROCEEu IO Inn ALERT CLASSIFICATION EPIP-3. l l

FLOOD i

Warning, probable impact, closure of evacuation routes.

CAUTION: IF WATER LEVEL IS NEAR DESIGN L4 VEL, PROCdia TO THE ALERT CLASSIFICAIION iPIP-J l

FIRE 3.15 FIRE NOT UNDER CONTROL IN 10 MINUTES f Fire in a permanent plant structure wnica cannot c,e controlled by the Fire Brigade witnin 10 minutes of discovery as judged by GSS with tne advice of tae Fire Bridgade Imader. ,

i CAUTION: FIRE POTENTIALLY AFFECTING SAFLTY Sf8Iiss, !

PROCEED TO THE ALERT CLASSIFICATION APIP-3. {

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Suspect: P*oce:urs No.

Unusual Event EPIP-2 40 7 :f 10 Hcs Revision N o. are . ,_

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PARAMETER INITIATING CONDITION EXPLOSION 3.16 WITHIN SECURITY PROTECTED AREA, NO SIGNIFICAdT EFFr.Cf WITHIN SECURITY CAUTION: KNOWN DAMAGE TO FACILIIY AFFECTIdG OPdxAIIda, PROTECTED PROCEED TO ALERT CLASSIFICAIION EPIP-3 i

AREA CONTAMIN- 3.17 TRANSPORTATICN OF INJURED CONTAMINAfsD INDIVIDUAL (s) fu ATED INJURY OFFSITE HOSPITAL AIRCRAFT 3.18 AIRCRAFT CRASH ONSITE ,

CRASH OR CAUTION: IF AN AIRCRAFI OR MISSILE SfdIES a sIAflon MISSILE STRUCTURE, PROCEED WITH ALERT CLASSIFICAIION IMPACT EPIP-3 .

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TURBINE 3.19 TURBINE ROTATING COMPONENT FAILURE CAddIING tuPIu Pt.Anf FAILURE SHUTDOWN l

CAUTION: TURBINE FAILURE CAUSING CASIdG PiddIAAII0a, PROCEED WITH ALERT CLASSIFICATION EPIP-3 PLANT 3.20 OTHER PLANT CONDITIONS EXIST THAT WARRANT INCRfAS60 STATUS OR AWARENESS ON THE PART OF STATE add /OR LOCAL OffSIfr.

' CONDITIONS AUTHORITIES OR REQUIRE PLANT SHUTDOWN UNDdd IECd. M P r.C.

AS EVALU- REQUIREMENTS OR INVOLVE OTdER TdANT N0ttui. CONfdOLLr.D ATED BY GSS SHUTDOWN INDICATIONS OR ALARMS ON PROCESS OR EFFLddaI n0dif0x3 NOT FUNCTIONAL IN CONTROL ROOD TO AN dXfdNI .tiquidiaG PLANT SHUTDOWN OR OTHER SIGNIFICANT LOSS OF ASSr.SSar.af OR COMMUNICATIONS CAPABILITY. ,

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. 1 Suatect:

- P'oceruro No. ,

Unusual Event -

EPIP-2 EM) a f 10 syss l 4evision N o. Osts .

/

Date:

4.0 EMERGENCY ACTIONS NOTE: After Completing Each Tasa, record time and initials or N/A (not applicable)

TIMd/IN1I1ALS 4.1 Upon recognition that any of the emergency action levels have been exceeded the Group Shift Super-visor shall assume the duties of the Emergency ,

Director. / /

4.2 Sound the appropriate alarm (as necessary) /

4.3 Announce (or have announced) the following message over the public address system:

ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL: THE PLANT IS IN AN UNUSUAL l EVENT CONDITION. PERSONNEL SdOULD CONIINud l WITH THEIR NORMAL DUTIES UNLESS FURTHER l INSTRUCTION IS GIVEN / c I

(Repeat the announcement) f 4.4 Announce to Control Room personnel that has assumed the duties of (name)

Emergency Director. /

4.5 Assign a Communicator to make notifications to persons and agencies listed in Attacnment L. /

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Sw. Pocacute No. ,

Unusual Event EPIP-2 "

193 9 3f 10 'c488 i Rowsion Na :ste ,,,,

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IIdt/IaIIIALS 4.6 Complete Attachmeht '2 " Initial Notification

---M6ssage"-and-give it to the Communicator for transmission to the New Jersey State Police within 15 minutes of event classification and to notify the Nuclear Regulatory Commission as soon as possible. /

4.7 If changes in onsite or offsite radiation levels are expected:

4.7.1 Initiate and continue offsite dose projections in accordance wita EPIP-9 /

4.7.2 Initiate onsite and offsite radio-logical surveys in accordance with EPIP-10 and EPIP-il. /

4.8 If fire is involved initiate EPIP-8 /

4.9 Periodically fill out Attachment 3 " Additional Information Message" and give it to tne Communicator for transmission to the Nuclear Regulator r

Consission. /

\

NOTE: Do not give the " Additional Information

Message" to the NEW JERSEY SIATE POLICE.

When Requested by the SRP, complete . Attacn-ment 5 "0CNGS STATION STATUS CHECKLIST MdSSAGE" and give it to tne communicator for trans-mission to the BUREAU OF RADIATION PROTECTION (ddP).

4.10 As required, initiate damage control activities in accordance with EPIP-14. /

4.11 If personnel are injured, implement EP IP-7. / I 4.1'2 Complete Attachment 4 "INP0/ANI Message" and give it to the Communicator for transmission. /

4.13 Based upon assessment of plant conditions:

4.13.1 Terminate the Unusual Event if no further emergency actions are required.

(Instruct Communicator to notify all agencies originally notifed and notify plant personnel via tne Public Address System.) /

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Susiect: Pocacuro No. ,,

Unusual Event EPIP-2 NO lu :1 10 H;es ;!

4evision No. Octe

/ C IL4r /IdIIIAL5 4.13.2 If recovery conditions have been met, initiate the Recovery Pnase in accord-ance with EPIP-29. /

4.13.3 If emergency action levels for an Unusual Event have been exceeded, escalate to the appropriate class in accordance with: Alert (EPIP-3) /

OR Site Emergency II. PIP-4) /

QR General Emergency (EPIP-5) /

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Sustect:

P ocxurs No.

NG3 1 :f 2 4;ss Unusual Event EPIP-2 aevision N o. Octe 2 J / ./ 0 4 l

ATTACHMENT 1 Date:

l COMMUNICATOR"S CHECKLIST - UNUSUAL EVENT IIaE/IdITIALS

1. Notify the on-duty Shif t Technical Advisor / l

2. Notify the senior Radiological Controls representative on shif t. /

3. Notify the on-call Emergency Director /

4. Notify the on-call Emergency Advisor /

i NOTE: The Emergency Advisor will notify tne VP- duelear Assurance, ,

the office of the President GPUN, and tne clanagement Oversight Committee. Instruct ene Emer,tency Advisor In These Duties.

5. Notify the New Jersey State Police within 15 minutes of classification. Use completed Attachment 2 " Initial Notification Message" with Emergency Director approval.

. Primary: State Hot Line (Notification Line) *

,~

Alternate: (609) 882-4200 (If Primary Is Out of Service) / 1 NOTE: If State Police Verification Call is not received within one )

minute, re-establish contact via state Hot Line and request {

verification call on the State Police Verification Line immediately.. Determine if Alternate Verification means is '

required. If so instruct State Police to verify oy dtaling l

~

(609) 693-6066 oz (609) 971-0220.

6. Notify the United States Nuclear Regulatory Commission Operations Center .

Use Attachment 2 Primary: NRC-ENS Line (Lift receiver from cradle)

Alternate: (1) Commercial via Bethesda (301) 492-8111 (2) Commercial via Silver Spring (301) 427-4050 l

(3) NRC-HPN Line - Dial 22 or *22 (Touch-cone)

(4) Commercial via Bethesda (301) 492-7000 / j

{

NOTE: Open-line communication with NRC is to be f maintanined on ENS Line enrougnout ene .j j

emergency' situation.

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7. Notify the Nuclear Regulatory Com:nission and otner -

agencies directe'd by the Emergency Director using ,

Attachment 3 Format. /

\ AfIACMidf 1 4 ** :no t..

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P*oceeure No.

l Sveiect:

8cge 2 :f 2 =c;es Unusual Event EPIP-2 Revision N o. 2 J/2/o2 i

)

ATTACHXENT 1 cont'd TIML/IdIIIALS

{ 8. Notify the following agencies using Attachment 4

! Format.

I

Institute of Nuclear Power Operations Tel: (404) 953-0904 /

American Nuclear Insurers Tel: (203) 677-7305 /

\

9. When requested, by the BRP, complete Attachment 5 and Transmit message via, the 8RP Auto ding Line located in the Emergency Command Center (Group <

Shift Supervisors Office) / /

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j

=ew Suotat: P oceoute No.

EPIP-2 814e :1ges Unusual Event t :f t mension N o. :ste ATTACHMENT 2 l

INITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERCISE, IHE aESSAGE WILL BEGIN AND END WITH THE PHRASE, "THIS IS A ." EXAaPLad:

"THIS IS A DRILL." "THIS IS A COMMUNICATIONS TEST." "THIS IS Ad EXERCISE." "THIS IS NOT AN EXERCISE --

I REPEAT- -- TdIS IS dof Aa EXERCISE." t i

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATIOd

(

THIS IS A NOTIFICATION OF AN UNUSUAL EVENT ,CLASSIFICAIION THIS EVENT WAS CLASSIFIED AT ~

ON (Iime - 24 hr. clock) (Date)

[ ] THERE IS NO RELEASE IN PROGRESS

[ ] WE HAVE A CONTROLLED R5 LEASE Id PROG.RESS

[.] WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS l

l ( [ ] NO PROTECTIVE ACTIONS ARE RECOMMENDED

[ ] WE RECOMMEND SHELTERING FOR THE FOLL0 DING DIRECfL0d4L SECTOR (S)

\ ._

[ ] WE RECOMMEND EV'ACUATION FOR IEE FOLLOWING DIRECII0dAL i SECTOR (S) l l

l APPRO7ED EMERGENCY DIRECTOR DATE TLV.-24 rid TIME NOTIFIED / VERIFIED THIS MESSAGE HAS SEEN fdANSdITTs0 IO: ,

/ [ ] NEW JERSEY STATE POLICE

/ [ ] UNITED STATES dQCLEAR dEGJLATodY COMaISSIGH (DATE) (COMMUNICATOR)

NOTE: VERIFICATION OF MESSAGES ARE COMPLETED OdLY Af fEA 4ECcIVING AGENCY HAS RESTATED MESSAGE CORRECTLY IN ITS EdIIREIY 3ACK

( TO THE OYSTER CREEK COMMUNICATOR l

, s AITACdaENI 2 1 I

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l Suoject: Procedure No.

EPIP-2 Page 1 Of A 7,

[ Unusual Event f

Aevisico No. . Cate 2 ! 3/2/82 i

ATTACHMENT 3 ADDITIONAL INFORMATION MESSAGE

(

Check ( ) all appropriate information DATE l

TIME

1. This is acting under the Direction of the Emergency (Emergency Director)

Director at Oyster Creek Nuclear Generating Station. The following is provided as additional information for the f

initial notification of the (circle one) Unusual event; Alert; s

i Site Emeraency; General Emeroencv. ,

7

2. DATE/ TIME OF CLASSIFICATION l

}

a. Time: (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock) ,

b. Date: Month _ Oay Year i

3. There (' circle one) is/is not an Emergency Classification change. The classification is: (circle one) Unusual Event; Alert; Site Emercency; General Emercency. ,

4. Plant Status Reactor (circle one) is/is not shutdown.

a.

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. ATTACHMENT 3 e%

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Subject:

Procedure No. '

EPIP-2 ,P39e 2' 4 '

f Unusual Event Aevision No.

Date 2 l 3/2/92 ATTACHMDIT 3 (cont'd)

b. The plant (circle one) is/is not in a safe condition

c. Reactor is subcritical, coolant is being maintained over the core, and containment integrity is satisfactory.

5. Type of release (circle one) a i rb o rr <i; liould; surface saill. !

6. Meteorological Data

a. Wind speed MPH

b. Wind direction (toward) i c. Stability class (circle one) unstable; neutral; stable

d. Precipitation (circle one) rain; sleet; snow l

7. Gaseous Radiological Data

( ,

a. Noble Gas release rate UCi/sec ,

b. Iodine 131 release rate uCi/sec

c. Release (circle one) has/has not terminated

d. Actual or estimated duration of release:

l 8. Liquid Radiological Date.

I

a. Release concentration uC.1/cc 1 ,

l b. Release rate uCi/sec

c. Release (circle one) has/has not terminated

d. Actual or estimated duration of release

e. Estimated total release uCi s ATTACHMENT 3

, , exam e m e.

[

Procedure No.

j l Suolect:

Unusual Event EPIP-2 Page 3 -- A 9 ,

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/ Revtsson Ph1 Cate ATTACH. Err 3 (cont'd) 2 4 3/2/62

( ! 9. Projected dose rates and integrated dose (Sased on actual or projected duration of release)

WHOLE BODY

a. Site Boundary mr/hr mrem

b. 2 miles mr/hr mrem t.

I c. 5 miles mr/hr mrem I

d. 10 miles mr/hr ,

mrem

10. Projected Iodine Concentration and Integrated Dose Commitment (Based on actual or projected duration of release) .

THYROID

a. Site Boundary uCi/cc mrem

b. 2 miles uCi/cc mrem

c. 5 miles uCi/cc mrem ,

t

d. 10 miles uCi/cc

mrem

11. Estimate of surface contamination dom /100 cm2 (obtain from field data) mrem /hr 1

12. Emergency Actions in progress:

a. Radiological survey teams onsite

b. Radiological survey teams offsite

c. Onsite fire brigade l d. Offsite fire department -

e. Damage Control l

1 l f. First aid teams onsite l

l g. Ambulance service l

h. Medical support l

1

1. Environmental surveys offsite 1

j. Other, specify ATTACHMENT 3

P'oceIuro No.

Suoiect: se qe 4 :f 4 seges Unusual Event APIP-2 8 evision N o. *ste

. J/./0.

e ATTACHMENT 3 (cont'd)

13. Additional support required (specify)-

14. The condition may change to an (circle one) Jnusual svent; Ale rt ; Site Emergency; General Emergency

15. Offsite population sector (s) (refer to Emergency Planning }

Zone Sector map) affected are ,

9

16. The following changes in protective measures are recommended for the population in these sectors.

a. None

b. Notify (projected offsite dose Take shelter (projected offsite dose )

c.

d. Evacuate (projected offsite dose

17. Approved (Emergency Director / Emergency Support director)

(Date) (Time)

18. Transmitted To: IIME: NOTIFIdD/VdRIFIdd.

a. United States Nuclear Regulatory

/

Commission.

b. New Jersey Bureau of Radiation

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Protection.

c.

/

t (Communicator) ,

(Date) l AffAC& %4f 3

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Pocature No.

Suotect: Eng) 1 :f 1 seges ! l' Unusual Event EPIP-?

8evision N o. :ste 2 a/;/o.

ATTACHMENT 4 NOTIFICATION TO: INSTITUTE OF NUCLEAR PowEd OPERATIONS & AMERICAN NUCLEAR INSUtudS MESSAGE FOL%T at Oyster Creen

1. This is '

(Name/ Title)

Nuclear Generating Station. We have declared an/an UNUSUAL EVENT condition at (Event Classification) (Time)

2. Description of Emergency:

3. Approved (Faergency Director / Emergency Support Director)

(Date) (Time)

Ti.ne

4. Transmitted To: Insitute of Nuclear Power -

Operations (404) 953-0904 To: American Nuclear Insurers (203) &77-7305 (Communicator) (Date)

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o P*cesouro No. !

Suotect: 8:qos Unusual Event EPIP-2 81 43 1 Of 2 8 evision N o. :ste J/./04

,r ATTACHMENT 5 OYSTER CREEK NUCLEAR GENERATING STATION STATION STATUS CHECKLIST FOR TRANSMISSIOa TO NEW JERSEY BUREAU OF RADIATION PROTECIION uate:

Time:

1. Date and Time of Incident: Date: Time: (24-ur. Clocs)

2. Accident Classification:(circle one) UNdddAL dVdNI ALr.xf SITE EMERGEdCY GENddAL sc14xGENCf

3. Type of Release:(circle one) GASEQUS LIQUID

4. Cause of Incident and System Involved (if known):

Is Reactor Shutdown: (circle one) Yes No 5.

u

6. Gaseous Release Information

. (a) Release Terminated: (circle one) ' Yes do (b) Estimated Duriation of Release: ifours (c) Type of Gaseous Release (circle one) 41evated Ground (d) Windspeed mph m/sec From: (0) Toward (0)

(e) Wind Direction: -

(Compass Point)

Affected Sector:

(f) Stability Class: (circle one) Unstable Neutral Staole (g) Release Rate Noble Gas: Ci/Sec.

(h) Release Race Iodine (if known) Ci/Sec.

7. Liquid Release Information (a) Release Terminated (circle one) Yes do (b) Estimated Duration of Release: _ tiours (c) Estimated Release Concentration uG/cc gpm (d) Release Rate AIfACwidat 5

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Ebececure to.

Svatect:

Unusual Event EPIP-2 8:Ge 2 *f : 2:qos a.,,sion N c. , cre 3: ;0.

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1 ATTACiciENT 5 (cont'd)

8. Projected Of fsite Doses (a) Whole Body Distance Miles) Dose Rate mrem /nr time to deaca PAG (nes. )

1.

2.

3.

4.

5. .

l (b) Child Thyroid .

Distance Miles) Dose Rate Rem /nr fime to deacn PAGlnrs. )

1.

2.

3.

4.

5.

9. Recommended Protective Actions:

L

10. Status checklist approved for transmission to NJddP oy imerdency Director / Emergency Support Director:

Signature Time

11. Status Checklist transmitted to NJBRP:

Time Transmitted to: (Name)

(Consnunicator) (Position) (Date)

AffACt & f j l

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Procecur@ No.

EPIP-3 P398 1 Cf to Date issuec l Effective Date Jersey Central u22/e1 1 2n:is: - 3,::,o, e Power & Light Company Revision No. a SUDject: Alert AulnCrtZec Sy

,nr Director Station Coerations

. (It $(Aidalld4.

Oyster k Nuclear Generating Station LIST OF EFFECTIVE PAGES DATE d4VIS10N NtJdddd ,

1 3/2/82 2 2 3/2/82 2 3 3/2/82 2 4 3/2/82 2 5 3/2/82 2 6 3/2/82 2 7 3/2/d2 2 8 3/2/82 2

( 9 3/2/82 2 10 3/2/82 2 ATTACHMENTS Attachment 1 (2 pages) 3/2/82 2 Attachment 2 (1 page ) 3/2/82 2 Attachment 3 (4 pages) 3/2/82 2 Attachment 4 (1 page ) 3/2/82 2 Attachment 5 (2 pages) 3/2/82 2 NON-CONTROLLED This Document Will Not Be f(ept

( Up To Date J

4 Scatect: P'tcarure No.

Alert EPIP-3 4 43 2 Of 10 4qes Revision N o. :ste 2 3/2/dz

/

1.0 PURPOSE 1.1 The purpose of this procedure is to define ene conditions tnat sna11 be regarded as an Alert for Oyster Creek Nuclear Station and to:

1.1.1 Ensure necessary actions are taken to protect tne nealen and safety of tne public.

1.1.2 Ensure necessary actions are taken to notify otisite emergency response organizations.

1.1.3 Mobilize the appropriate portions or tne emergency response organization to initiate appropriate emergency actions.

1.2 Tne Emergency Director is responsiDie for implementing enis procedure.

1.3 Emergency Director responsibilities that may d0f oe delegated include:

1.3.1 Decision to notify offsite emergency management agencies.

1.3.2 Making protective action recommendations as necesary to of fsite emergency management agencies.

1.3.3 Classification of Emergency Event.

, 1.3.4 Determining the' necessity for onsite evacuation oased upon potential eposure to non-essential personnel.

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

2.0 ATTACHMENTS 2.1 Attachment 1, Communicator's Checklist 2.2 Attachment 2, Initial Notification Message 2.3 Attachment 3, Additional Information Message 2.4 Attachment 4, INP0/ANI Notification Message 2.5 Attachment 5, OCGNS Station Status Checklist (BdP) s

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l Seapct: P'ocacura No.

Alert EP IP-3 Foo 3 :f 10 Ng:s Revision N o. Octe g .g; I

1 l

3.0 EMERGENCY ACTION LEVELS PARAMETER INITIATING CONDITION RADIOACTIVE 3.1 RELEASE EXCEEDS TECHNICAL SPECIFICATI0dS EFFLUENTS _

Indications: Valid Stack Gas High High Alarm Stacs samples analysis for Iodine ana/or particulates exceed ten times fecn. Spec.

NOTE: PLANT STACK EFFLUENT TECHNICAL SPECIFICATIONS

- The maximum release rate of gross activity except iodine and particulates witn nalf lives ,

longer enant eight days snall be limited in accordance with the following equation:

Q = 10 (0.21) where Q is tne stacs release E

rate (Ci/sec) of gross activity and 6 is tne average gamma emergy per aisintegration (Mev/ dis ) .

The maximum release rate of todines and particultes with half lives longer tnan eignt

/ days shall not exceed 40 uci/sec.

CAUTION: If the release corresponds to offsite radiation levels greater tnan 5 mrem /hr for 1/2 hr to tne wnole body or greater enan 25 mrem /nr to tne child tnyroid, proceed to tne Site Emergency Classification EPIP-4.

PROJECTED 3.2 0FFSITE DOSE DUE TO THE EVENI IS PROJECTED TO EXCEED OFFSITE 10 MREM TO THE WHOLE 80DY OR 50 MREM IO fHE CdILD DOSES THYROID -

NOTE: Projection data is obtained from Radiological and Environmental Dose Assessment activities.

CAUTION: IF THE OFFSITE DOSE 006 TO Idi tVcar is PROJECTED TO EXCEED 50 MREM WdOLE BODY OR 250 MREM CHILD THYROID, PROCT.ED f0 fd5 SI fe, EMERGENCY CLASSIFICATION EPIP-4.

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I Suotect: Pecc:tura No.

Alert EPIP-3 Fee 4 :f 10 8ec; s Revision N o. 2

ste ,j jeg a

PARAMETER INITIATING CONDITION REACTOR 3.3 EXCEEDS 1239 PSIG PRESSURE As may be indicated by " Safety or delier Valve dot Closed" alarm and verified steam flow steam pressure recorder indications.

CAUTION: IF REACTOR PRESSURE dXC4dDS Ind SAfdIY Lidif 0F 1373 PSIG, PROCEED TO THE SITE EMidGddCY CLASSIFICATION EPIP-4.

REACTOR 3.4 REQUIRES OR CAU::ES REACTOR SCRAM l COOLANT EXCEEDS 50 GPM TOTAL COOLANT LEAK RATE SYSTEM LEAKAGE As computed fron drywell equipment drain tank readings plus gallons pumped from drywell sump per elapsed time.

CAUTION: IF REACTOR C00LANI SYSTEM LEAK 6ACr.dDS 100 l GPM, PROCEED TO THE SITE ddERGddCf 1 CLASSIFICATION EPIP-4.

REACTOR 3.5 RCS IODINE ACTIVITY GREATdd THAN 300 uCi/cc COOLANT SYSTEM Determined from plant enemistry samples ACTIVITY OFFGAS 3.6 0FF-GAS AIR EJECTOR MONITORS INDICATE GREArid MONITOR THAN 10,000 mr/hr.

READING AND FUEL STATUS NOIE: Corresponding indication of tnis value on any off gas air ejector monitor will equate to 1.49 ci/sec.

CAUTION: IF DEGRADATION OF THE COR4 OCCORS, ud Idr.xn IS POSSIBLE LOSS OF C00LABLE GE0dEIdY, PROCEED TO THE SITE EMERGENCf CLASSIFICAIIUd EPIP-4.

ISOLATION 3.7 MAIN STEAM LINE BREAK WITH MSIV dALFUNCTION VALVE CAUSING LEAKAGE INTO TURBINE BOILDING STATUS CAUTION: IF THERE IS A MAIN SIdAd LIdd oddAK Oufslud 0F CONTAINMENT WITHOUT ISOLATION, PROCdd0 TO THE SIIE EMERGENCY CALSSIFICAII0d EPIP-4.

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Suotect: PeoisIuro No.

Alert EPIP-3 Foo 5f 10 8:q:s Revision N o. y :ste g, p .'

PARAMETER INITIATING CONDITION REACTOR _3.8_ REACTOR NOT SUBCRITICAL AFTER VALIO SCKAM SIGNAL PROTECTION SYSTEMS LOSS OF 3.9 COMPLETE LOSS OF FUNCTIONS NedDED TO ACdIdvd PLANI COLO ENGINEERED SHUTDOWN SAFETY !

FEATURES Cold shutdown mode switen in snutdown mode position, fuel in the reactor vessel, all operable control rods .

are fully inserted, and tne reactor coolant system ,

maintained at less than'2120 F and vented. ,

t CAUTION: IF LOSS OF FUNCIIONS NddDio f0 ACdidVc dOf STANDBY OCCUR, PROCEED IO Idd SIrd EMERGENCY MOST OR ALL CONTROL ROOH ALARMS ( AdadCI AfodS) LOSf Loss of wnien may involve an actual or potential substandard degradation of tne level of safety of tne plant as judged oy tne GSS.

(

A NOTE: Occurs on loss of 125 VDC.

CAUTION LOSS OF ALL CONTROL ROOM ALARMS (ANdUCIAiudS)

GREATER THAN 15 MINUTES OCCUdS WIIH PLANI WOI IN COLD SdUTDOWN, PROCidd EU fdd SIfc EMERGENCY CLASSIFICAIION EPIP-4.

CONTROL ROOM EVACUATION REQUIRd0 Od ANfiCIPAfdd C0ufdOL OF SHUTDOWN SYSTEMS ESTABLISdED Af LOCAL STATIONS WITHIN 15 MINUTES .

CAUTION: IF THE CONTROL ROOM IS 61AUArdD M 0 dcyVidco SHUTDOWN SYSTEM CONTROL AT LOCAL STAfl0NS IS NOT ESTABLISHED WITHIN 15 MINUTdS, PROCddo to THE SITE EMERGENCY CLASSIFICATION EPIP-4.

FUEL HANDLING ACCIDENT OR OIndd EVENf ddSOLfinG in UNEXPECTED INCREASE OF INPLAdf RADI0ACfiVIff LcVdLS of A FACTOR OF 100 CAUTION: IF MAJOR DAMAGE IO SPdNr FUdL IN fric dcACfod CAVIIY OR SPENT FUEL POOL OCCUds, OR Iddd4 IS AN WI4 CONTROLLED DECREAdd In iUch POOL WAfsn LEVEL T0 dELOW THE LdVEL OF FUEL: PROCddo f0 THE SITE EMddGdNCY CLASSIFICAIIon cPIP-4.

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PARAMETER INITIATING CONDITION T0XIC OR 3.10 ENTERS FACILITY, PRESENTS HABIIABILITY PROBLcMS FLAMMABLE GAS RELEASE CAUTION: IF T0XIC OR FLAMMABLE GAS ENfERS VIIAL Adnas NEAR OR AND RESTRICTS NECESSARY ACCESS, PROCEED IO ONSITE THE SITE EMERGENCY CLASSIFICAII0d EPIP-4.

SECURITY 3.11 ONGOING SECURITY COMPROMISE COMPROMISE As judged by the GSS on advise of tne Site security Sergeant.

CAUTION: IF THERE IS INMINENT LOSS OF PdYSICAL C0dIKOL OF THE PLANT, PROCEED TO THE SITE EdddGENCY CLASSIFICATION EPIP-4.

LOSS OF 3.12 LOSS OF ALL OFFSITE AND ONSITE AC POWER Fod LcSS IdAd POWER 15 MINUTES CAUTION: IF LOSS OF OFFSIIE POWER Aa0 ONs IIr. Powcd SUPPLIES EXCEED 15 MINUTES, PROCEED IO Tdd r SITE EMERGENCY CLASSIFICAIION EPIP-4.

s LOSS OF PLANT DC POWER FOR LESS THAN 15 MINUTES CAUTION: IF LOSS OF DC POWER Fod MORE THAN L5 MINUIES OCCURS. PROCEED TO IdE SIIE EMERGEdGY CLASSIFICATION EPIP-4. (

i NATURAL 3.13 TORNADO

. PHENOMENA (

Strikes vital plant structures (

l STORM Winds near design level, greater tnan 100 mpn.

CAUTION: IF WIND SPEED EXCEEDS 125 MILES PER doux, PROCEED TO THE SITE EMERGENCY CLASSIFICAII0a EPIP-4.

FLOOD Near Design level CAUTION: FIRE AFFECTING SAFETY SYSIEds REquidco FOR SHUTDOWN, PROCEED TO SIIE c.dcdGENCY s CLASSIFICATION EPIP-4.

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. Suspet: Proczura No. ;

Alert EPIP-3 40 7 of , n %Cs :

%sion N o. Oate yjjg 2

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PARAMETER INITIATING CONDITION FIRE 3.14 POTENTIALLY AFFECTING PLANT SAFETY SYSTFAS Fire jeopardizing tne operability of safety systems as judged by the GSS with advice of tne Fire ori d ade Iaader.

CAUTION: FIRE AFFECTING SAFEIf SYSInnS dr.ydidE0 fod SHUTDOWN, PROCEED TO SITE dafRGEdCf CLASSIFICATION RPIP-4.

EXPLOSION 3.15 KNOWN DAMAGE TO FACILITY AFFECTIdG PLAdf OPr.dAfidas WITHIN SECURITY CAUTION: KNOWN DAMAGE 'IO THE FACILIIY AFF6CIInd SAfr rY PROTECTED SYSTEMS REQUIRED FOR SdOTDOWN, PROCEdD TO Td4 AREA SITE EMERGENCY CLASSIFICAII0d EPIP-4.

AIRCRAFT 3.16 AIRCRAFT OF MISSILE STRIKES A STATION STRUCTURd CRASH O_R R CAUTION: IF AN AIRCRAFT OR MISSILE CRASH AFF6CIS VIfAL MISSILE INSTRUMENTS BY LMPACT OR FIRE, PROCHED IO TdE IMPACT SITE EMERGENCY CLASSIFICATI0d 4 PIP-4.

f

(

TURBINE 3.17 TURBINE FAILURE CAUSING CASING PENETRATION FAILURE PLANT STATUS 3.18 OTHER PLANT CONDITIONS EXIST TRAI WARRANf ACIIVAII0d 0F OR CONDITIONS THE TECHNICAL SUPPORT CENTER, Id4 OPERATIONS SUPP0df AS EVALUATED CENTER, AND PLACING OTHER KEY EMERGENCY PEASONNEL on BY GSS STANDBY 6

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Sootect:

P'ocature No. ll Alert EPIP-3 Foo o :f to recs -

Revision N o. Octe gg 2

7 t

DATE I

TIME / INITIALS 4.0 EMERGENCY ACTIONS NOTE: AFTER COMPLETING EACd IASK, record time and f initials or N/A (not applicable). I l

/ 4.1 Upon recognition tnat any of ene above ranergency Action levels have been exceeded, the Group Snift Supervisor I sha-11 assume the duties of the smergency Director. -

/ 4.2 Sound the appropriate alarm (as necessary). i

/ 4.3 Announce (or have announced) ene following message over the Public Address System: I ATTENTION ALL PERSONNEL, AITENTION ALL PERS0ddc.L: fdr PLANT IS IN AN ALERT CONDITION. ALL ON-CALL INITIAL i

EMERGENCY RESPONSE TEAM PERSONNEL d4 PORT f0 EMidGddGi STATIONS. ALL OTRER PERSONNEL AJAII FURTdid (

INSTRUCTIONS. EATING, DRINKING,. AND SMOKING Io l

< PR0dIBITED UNTIL FURTHER NOTICE.

Repeat Announcement

/ 4.4 Announce to Control Room personnel enat has assumed tne' (Name) duties of Emergency Director.

/ 4.5 Notify OCNGS Security, Ext. 6954, 6950 and otrect enem to activate the pagers of the On-Call Initial Emergency Response Team on duty (Team 1, 2 or 3)

/ 4.6 Assign a Communica tor to make notification to persons and agencies listed in Attacnment L.

/ 4.7 Complete Attachment 2 " Initial Notification Message" and give it to the Communicator for transmission to tne New Jersey State Police within 15 minutes of event classificaton and to notify tne Nuclear degulatory Commission as soon as possible.

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

ProceIure No, l . Svetect:

f Alert EPIP-3 40 9 f 10 Mqes 4evision N o. y Octe j

/' l I

l DATE TIME / INITIALS

/ 4.8 Activate The Operations Support Ce nte r (dPIP-27) ana The Tachnical Support Center (EPIP-26)

/ 4.9 Initiate Personnel Accountability in accordance wita EPIP-12 i

/ 4.10 Initiate and continue offsite dose projection in accordance with EPIP-9 t

/ 4.11 Initiate onsite and o,f f s ite radiolod'ical surveys in 1 accordance with EPIP-10 and EPIP-ll

/ 4.12 If fire is involved, implement dPIP-8 !

/ 4.13 Periodically fill out Attacnment 3, " Additional Information Message" and give it to tne Communicator for transmission to the Nuclear Regulatory Commission.

NOTE: Do not give tne " Additional Inf o rmation Message" to the New Jersey State Police.

/ When requested by tne ddP, complete Attachment 5 "0CNGS Station Status Cnecklist Message" and give it to the Communicator ror transmission to the Bureau of Radiation Protection (BRP).

/ 4.14 As required, initiate damage control activities in accordance with EPIP-14 i

/ 4.15 If personnel are injured, implement EPIP-7 l

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Sdtect: P'oceture No.

Alert EPIP-3 Eco iv:f 10 Ecqos

% sion N o. 3 Octe 3 ,j,,

s DATE _

TIME / INITIALS

/ 4.16 Complete Attachment 4, "INP0/ANI dessade" anc gtve it to the Communicator for transmission

/ 4.17 If a report of personnel accountaoility nas not oeen received within 30 minutes, contact Security (o954, 6950) for a status report

/ 4.18 If personnel are unaccounted for, implement Searen and Rescue (EPIP-22)

/ 4.19 Activate the Remote Assemoly Area (rPIP-ld) anc implement Site Evacuation (EPIP-13)after accountaoilty is complete.

4.20 Based on assessment of plant conditions:

/ 4.20.1 Te rminate the Ale rt if no furtner emergency actions are required (instruct cne Communicator to renotify all adencies originally notified and notify plant personnelvia the Public Address System.

/ 4.20.2 If recovery conditions nave oeen met, ,

init ir.,te the Recovery Pnase in accordance l with EPIP-29.

/ 4.20.3 If recovery conditions have not oeen met out site Emergency Action levels are no longer being exceeded, de-escalate to a lower emergency class by performing notifications required by EPIP-2 4.20.4 If emergency action levels exceed enose tor an Alert , escalate to tne approriate class

/ in accordance witn: Site i.mergency (rPIPw)

/ or General Emergency (EPIP-3) l l

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< Swo ,ct: P ectiuro No. ,

Alert EPIP-3 Pio 1 sf 2 8eq:s !

4evision N o, y Sofe )j j

/ .

ATTACHMENT 1 Date:

COMMUNICATOR 'S CHECKLIST - UNUSUAL EVENT

'~~

TIME / INITIALS

1. Notify the on-duty Shift Technical Advisor / (

2. Notify the senior Radiological Controls representative on shift. /

3. Notify the on-call Emergency Director /

4. Notify the on-call Emergency Advisor /

NOTE: he Emergency Advisor will notify tne VP- duclear Assurance, the office of the President GPUN, and tne Management Oversight Committee. Instruct tne Emergency Advisor In Rese Duties.

5. Notify the New Jersey State Police witnin 15 minutes of classification. Use completed Attachment 2 " Initial Notification Message" with Emergency Director approval.

/ Primary: State Hot Line (Notification Line)

Alternate: (609) 882-4200 (If Primary Is Out of Service) /

NOTE: If State Police Verification Call is not received witnin one minute, re-establish contact via state Hot Line and request verification call on the State Po lice Verification Line <

immediately. Determine if Alternate Verification means is required. If so instruct State Police to verify of cialind (609) 693-6066 or (609) 971-0220. .

6. Notify the United States Nuclear Regulatory l Commission Operations Center Use Attachment 2 Primary: NRC-ENS Line (Lift receiver fron cradle)

Alternate: (1) Commercial via Bethesda (301) 492-8111 (2) Commercial via Silver Spring (301) 427-4030 (3) NRC-HPN Line - Dial 22 or *22 (Touen-tone)

(4) Commercial via detnesda (301) 492-7000 /

NOTE: Open-line communication with NRC is to be maintanined on ENS Line throughout ene I

emergency situation.

7. Notify the Nuclear Regulatory Commission and otner agencies directed by the Emergency Director using j Attachment 3 Format. / l l

k AITACHdidI 1 l

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f , l Svatest:

P'octeuro No. l iPIP-3 Mqe 2 Of 2 4qes Alert

% vision N o. y Octe 7

ATTACitEdT 1 cont 'd IIME/ INITIAL:

. 8. Notify the following agencies using Attachment 4 Format.

Institute of Nuclear Power Operations Tel: (404) 953-0904 /

American Nuclear Insurers Tel: (203) 677-7305 /

9. When requested, by the BRP, complete Attachment' 5 and Transmit message via, the BRP Auto P.ing Line located in the Emergency Command Center (Group Shift Supervisors Office) /

t 1

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G ATTACtLENT 1 i

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" Suoiect: P*ocacure No.

Alert EPIP-3 8148 1 of 1 seges 4evision N o, ste y ,7

/

ATTACHMENT 2 INITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERCISE, THE dESSAGd WILL BEGIN AND END WITH THE PHRASE, "THIS IS A ." EXAaPLES:

"THIS IS A DRILL." "THIS IS A COMMUNICATIONS TESI." "IdIS IS AN EXERCISE." "THIS IS NOT AN EXERCISE --

I REPEAI --

IMIS IS N0f Aa EXERCISE."

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATION THIS IS A NOTIFICATION OF AN ALERT CLASSIFICATION THIS EVENT WAS CLASSIFIED AT _ Od (Time - 24 nr. clock) (Date)

[ ] THERE IS NO RELEASE IN PROGRESS

[ ] WE HAVE A CONTROLLED RELEASE IN PROGRESS

[ ] WE HAVE'AN UNCONTROLLED RELEASE IN PROGRESS

/

[ ] .NO PROTECTIVE ACTIONS ARE RECOMMENDED s

[ ] WE RECOMMEND SdELTERING FOR IHE FOLLOWIdG DIREG f10an SECTOR (S)

[ ] WE RECOMMEND EVACUATION FOR THE FOLLOWING OIRECfl0ah SECTOR (S)

APPROVED EMERGENCY DIRECTOR DATE TIME-24 da

_ ---- . _ _ . ----------- -a _ - - ----

TIME NOTIFIED / VERIFIED THIS MESSAGE RAS BEEN TRANSMITTED IO:

/ [ ] NEW JERSEY STATE POLICE

/ [ ] UNITED STATES NUCLEAR REGULAI0df C0daldSION (DATE) (COMMUNICATOR)

NOTE: VERIFICATION OF MESSAGES ARE COMPLETED OdLY AFTER drCdIViaG AGENCY HAS RESTATED MESSAGE CORRECTLY IN IIS ENf1 RETT 8ACK IO THE OYSTER CREEK COMMUNICAIOR v

ATTACHMENI 2 2 8- t --

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( Su2iect: Procidura No.

Alert EPIP-3 lPage1of 4 ,

Revision No. Cate

.,r-2 l 3/2/82

^

l ATTACHMENT 3 I '

ADDITIONAL INFORMATION MESSAGE ,

Check ( ) all appropriate information DATE !

!)

TIME I

., 1l

1. This is acting under the 1

the Emergency i Direction of l (Emergency Director)

Director at Oyster Creek Nuclear Generating Station. The following is provided as additional information for the initial notification of the (circle one) Unusual event; Alert; ,

Site Emergency; General Emergency.

l 2. DATE/ TIME OF CLASSIFICATION l i

a. Time: (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock)

b. Date: Month Day Year

3. There (circle'one) is/is not an Emergency Classification change. The classification is: (circle one) Unusual Event; Alert; Site Emeroency; General Emergency. ,

] 4. Plant Status

a. Reactor (circle one) is/is not shutdown.

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ATTACHMENT 3

_ _ _ _ _ _ _ _ -______-_-___._________m. _ _ _ - _ _ _ - _ _ _ _ . - . . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

~ ~

Suojict: Procsdure No, r Alert EPIP-3 l P39e 2 U 4 '

Revision No. ;Date ATTACIt m T 3 (cont'd)

b. The plant (circle one) is/is not in a safe condition

c. Reactor is subcritical, coolant is being maintained over the core, and containment integrity is satisfactory.

5. Type of release (circle one) airborne; liould; surface soill. !

i

6. Meteorological Data

a. Wind speed MPH

b. Wind direction (toward)

c. Stability class (circle one) unstable; neutral; stable

d. Precipitation (circle one) rain; sleet; snow

{

7. Gaseous Radiological Data

a. Noble Gas release rate uCi/sec

b. Iodine 131 release rate uCi/sec

c. Release (circle one) has/has not terminated

d. Actual or estimated duration of release:

l i .

8. Liquid Radiological Date )

I

a. Release concentration uCi/cc

b. Release rate UCi/sec

c. Release'(circle one) has/has not terminated

d. Actual or estimated duration of release

e. Estimated total release uCi ATTACHMENT 3 l 4

-~ - - -

,-,-,u--- -_- , -e.-- - - - - - - , , , , , . - - - , , - - , , . - ---n-m. ,, , r -,,- ,,- - , ., - - , . , . - - , , . , , . - - - ~ m_., -,

F

~

Subj:ct: Proc & dura No.

p Alert gprp_3 lPage 3 -

4 ' ,

Revisica No. Cate ATTACHMENT 3 (cont'd) 2 l 3/2/82 _

i 9. Projected dose rates and integrated dose (Based on actual or projected duration of release)

WHOLE BODY

a. Site Boundary mr/hr mrem i

b. 2 miles mr/hr mrem

c. 5 miles mr/hr mrem l l

\ l

d. 10 miles mr/hr mrem

10. Projected Iodine Concentration and Integrated Dose Commitment i

(Based on actual or projected duration of release) .

THYROIO

a. Site Boundary UCi/cc mrem l b. 2 miles uCi/cc mrem I

, c. 5 miles uCi/cc mrem ,

j d. 10 miles uCi/cc mrem j

! ' (

) 11. Estimate of surface contamination dom /100 cm2 (obtain from field data) mrem /hr

12. Emergency Actions in progress:

a. Radiological survey teams onsite

b. Radiological survey teams offsite

c. Onsite fire brigade

d. Offsite fire department

e. Damage Control l

f. First aid teams onsite j

g. Ambulance service

h. Medical support

1. Environmental surveys offsite

(. .

J. Other, specify _

ATTACHMENT 3

Susiect: P+ocerura No.

Alert EPIP-3 ho 4 sf 4 8cces Revision N o. Cate ,j j l

f Attachment 3 (cont'd)

( 13. Additional support required (specify)

[

14. The condition may change to an (circle one) Unusual Event; Alert; Site Emergency; General Emergency I

15. Offsite population sector (s) (refer to dmergency Planning, Zc,ne Sector map) af fected are ,

9 D

16. The following changes in protective measures are recommendeo for the population in these sectors.

a. None

b. Notify (projected offsite dose 1

c. Take shelter (projected of fsite dose )

d. Evacuate (projected of fsite dose ) l t

17. Approved (Emergency Director /dmergency Support Director) 4 (Date) (Time) f

18. Transmitted To: TIris: d0fIFIED/VdxIfir.D. j I

a. United States Nuclear Regulatory Commission. / I

b. New Jersey Bureau of Radiation Protection. /

c. I l

(Communicator) (Date)

Af fACreiddT 3 l

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Suspect: Peoreture No.

EPIP-3 40 1 af 1 4qee Alert 4evision N o. 2 ate r~ .

ATTACHMENT 4 NOTIFICATION TO: INSTITUTE OF NUCLEAR POWER

\

OPERATIONS & AMERICAN NUCLEAR INSUdidS MESSAGE FORMAT

1. This is at Oyster Creen ,

(Name/ Title) f Nuclear Generating Station. We have declared an/an l Alert condition at

, (Event Classification) ( Time) .

2. Description of Emergency:

3. Approved (Emergency Director / Emergency Support Director)

(Date) ( Time)

Time

4. Transmitted To: Insitute of Nuclear Power Operations (404) 953-0904 To: Anerican Nuclear Insurers '

(203) 677-7305 (Communicator) (Date) 1 AfIACMEN f 4 i

. _ _j .- ._______

+

Suenct: ProcsIure No. s Ale rt EPIP-3 '

F':0 'l of 2 _sms _

s Revision N o. " cto 2, .3/4/o; , j

~a f x ., - , ,

1 ATIActL4ENT 5 OYSTER CREEK NUCLEAR GEddRATING SIAIIOd STATION STAIUS CHECKLIST FOR IRAd514I:si10d '

TO NEW JERSEY BUREAU OF RADIATION Pit 0TdCTION. .

Da te :

Time:

~

)

1. Date and Time of Incident: Date: Time: (24-Hr. Clocx)

2. Accident Classification:(circle one) UNUSUAL r.VENI ALinf SITE EMERGENCY GENERAL dc1ERGENCY

3. Type of Release:(circle one) GASEOUS LIQUID , ,

4. Cause of Incident and System Involved (if known):

5. Is Reactor Shutdown: (circle one) Yes do

6. Gaseous Releash Information (a) Release Terminated: (circle one)

Yes ao l

(b) Estimated Duriation of Release: Hours .

(

t (c) Type of Gaseous Release (circle one) dievatea Ground l (d) Windspeed mph m/sec -

(e) Wind Direct' ion: From: -(0) Toward (0) l

. Affected Sector: -(Compass Point)

(f) Stability Class: (circle one) Unstable Neutral ' Stable (g) Release Rate Noble Gas: Ci/Sec.

(h) Release Rate Iodine (if known) __Ci / Se c .

I i (

7. Liquid Release Information (a) Release Terminated (circle one) Ye s no (b) Estimated Duration of Release: dours

(

(c) Estimated Release Concentration uCi/cc l I

(d) Release Rate gpm ,

Af facet tsa r 5

)

,- 2 -. ,

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Sectoct:

P'ocawe No.

Ale rt EPIP-3 so c , :f , 8cges Revision N o. Octe f

ATTACHMENT 5 (cont'd) . -

8. Projected Offsite Doses (a) Whole Body Dose 1(ate mrem /hr rime to Reacq PAGln rs . )

Distance' Miles)..

- - .a,.

g e 2.

3.

.-- 4. -

5. -

'(b) Chil'd Thyroid Distance Miles) Dose date dem/hr fime to Keacn PAG (nrs.)

1.

2.

3.

4. _

5.

9. Recommended Protective Actions:

10. Status Checklist approved for ' transmission to NJSRP oy line rdency Director / Emergency Support Director:

Sig. nature ' , Time

11. Status Checklist transmitted to NJ.SRP: ~'

Time I

Transmitted to: (Name)

(Communica tor) (Position) (Date)

)

I

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A f i' ACetind i ) '

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Procecura No.

_gpygg Jgg EPIP-4 Page 1 Of S Date issvac Effective Cate

- Jersey Central 2 m /41 3n:/s2 - 3/ :/s2 Power & Light Company Revision No. Cate p2/82

Subject:

site Emergency

~

Autnerized By qq Director Station Operations ApprMal op6L rp ,

LAi.d .[A ST(meaJa.

Oyster Cr k Nuclear Generating Station LIST OF EFFECTIVE PAGES DATE REVISION WUdddd 1 3/2/82 2 2 3/2/82 2 l

3 3/2/82 2 l 4 3/2/82 2

( 5 3/2/82 2 6 3/2/82 2 7 3/2/82 2 8 3/2/82 2 ATTACHMENTS Attachment 1 (2 pages) 3/2/82 2 Attachment 2 (1 page) 3/2/82 2 Attachment 3 (4 pages) 3/2/82 2 Attachment 4 (1 page) 3/2/82' 2 4

Attachment 5 12 pages) 3/2/82 2

(

NON-CONTROLLED This Document Will Not Be Kept Up To Date

, - - - _' -___.__)

l !

4a Svatect: Prococure No. .

P'48 2 5qos Site Emergency EPIP-4 2 3f 8 l l Revision N o. 2 ate l 2 J/2/o2 w

1.0 PURPOSE 1.1 The purpose of this procedure is to define tne conditions tnat shall be regarded as a Site Emergency for Oyster Creek Nuclear Generating Station and to:

1.1.1 Ensure necessary actions are taKen to protect tne health and safety of the public.

1.1.2 Ensure necessary actions are taken to r.o tif y ortsite ,

emergency rjesponse organizations.

1.1.3 Mobilize the emergency response organizations to initiate appropriate emergency actions.

1.2 The Emergency Director is responsible for implementing tais procedure.

1.3 Emergency Director responsibilities that may NOI oe delegatec include:

1.3.1 Decision .o notify offsite emergency management agencies.

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

1.3.3 Classification of Emergency Event.

1.3.4 Determining the necessity for onsite evacuation.

1.3.5 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits. l 2.0 ATTACHMENTS 2.1 Attachmen't 1, Communications Checklist 2.2 Attachment 2, Initial Notification Messake 2.3 Attachment 3, Additional Information Message l

2.4 Attachment 4, INP0/ANI Message 2.5 Attachment 5, OCNGS, Station Status Cnecklist (dRP) 1 k

n t..

4 Sostect: Prococure No.

P14e of 4qes Site Emergency Epip-4 -3 4 f Revision N o. Octe 3.0 EMERGENCY ACTION LEVELS PARAMETER INITIATING CONDITION RADIOACTIVE 3.1 RELEASE CORRESPONDS TO OFFSITE RADIATION EFFLUENTS LEVELS GREATER THAN 5 MREM /HR FOR 1/2 HOUR IO IHE ddOLE BODY OR GREATER THAN 25 MREM /HR TO THE CHILD TdYROLD Determine radiation level at Site Boundary of from offsite monitoring reports o r, by Offsite Dose Assessment Procedure EPIP-9 CAUTION: IF THE RELEASE CORRESPONDS IO 0FFSITE RADIATION LEVELS GREATER THAd 50 MREM /tta IO THE WHOLE BODY OR GREATER THAd 250 mREd/dR IO THE CHILD THYROID PROJECTED 3.2 0FFSITE DOSE DUE TO THE EVENT IS PROJECIED IO E/.CEED OFFSITE 50 MREM TO THE WHOLE BODY OR 250 MREM IO IdE CHILD 00sc.S f

THYROID l CAUTION: IF THE OFFSIIE DOSE DOE IO IdE EVEdT IS PROJECTED TO EXCEED 100 mRFA WHOLE BODY OR r

500 MREM CHILD IHYROID, PROCEED IO Itts GENERAL EMERGENCY CLASSIFICATION EPIP-5.

l l

REACTOR 3.3 EXCEEDS THE SAFETY LIMIT OF 1375 PSIG l PRESSURE As may be indicated by " Safety or Relier Valve noc Closed" alarm and verified by " Steam Flow Steam Pressure Recorder indication.

REACTOR 3.4 EXCEEDS 100 GPM i

COOLANT )

l SYSTEM Exceeds CRD pump capacity LEAKAGE LEAK RATE EXCEEDS AVAILABLE MAKE-UP dATE l

REACTOR 3.5 DEGRADED CORE WITH POSSIBLE LOSS OF C00LABLE COOLANT GE0 METRY.

SYSTEM ACTIVITY I INDICATING FUEL CLADDING - '

DEGRADATION ,

)

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Suotect: Proceaure %

Site Emergency EPIP-4 P198 4 f d 2cqee ,

Revision % " ate l

FARAMETER INITIATING CONDITION D

{ ISOLATION 3.6 BREAK OUTSIDE CONTAINMENT WITHOUT ISOLATION l

VALVE STATUS LOSS OF 3.7 UNCONTROLLED DECREASE IN FUEL POOL WAIER BELOW ENGINEERED LEVEL OF FUEL SAFETY ,

FEATURES MAJOR DAMAGE TO SPENT FUEL DURING REFutLING LOSS OF FUNCTIONS NECESSARY TO ACdIEVE dOf SIAdudi As may be indicated by a complete loss of: l Ability to insert control rods witn failure of Standoy l

Liquid Control System og all means to control reactor pressure og both normal and emergency makeup water to core NOTE: Hot Standby - planned snutdown trom 1004 power to hot standby witn reactor pressure 1020 PSIG and the reactor mode switen in "Run". , Reactor critical at 10% power.

turbine tripped and turning on gear.

LOSS OF ALL CONTROL ROOM ALARMS (ANNUNCIATORS) !

GREATER THAN 15 MINUTES WITH PLANT NOT IN COLD SHUTDOWN CONTROL ROOM EVACUATION AND LOCAL CONTROL OF r REQUIRED SHUTDOWN SYSTEMS NOI ESTAdLIddED WIfdia l 15 MINUTES T0XIC OR 3.8 ENTERS AREAS AND RESTRICTS NECESSARY ACCESS FLAMMABLE CAS RELEASE For safe operation or shutdown of tne plant wnen l NEAR OR required as determined by Group Shif t Supervisor. l ONSITE I l.

SECURITY 3.9 IMMINENT LOSS OF PHYSICAL CONTROL OF Ids PLANf COMPROMISE As judged by the GSS on advice of tne Site Security Sergeant.

I l

I

- _ - - - _ _ J

Sumtect: Perceiura No.

l Site Emergency EPIP-4 Pc48 5 Of a 2cqos l

Revision N o. Octe J/4/o2 PARAMETER INITIATING CONDIIION LOSS OF 3.10 LOSS OF OFFSITE POWER AND ONSITE AC POWER FOR POWER GREATER THAN 15 MINUTES LOSS OF PLANT D.C. POWER FOR MORE TRAN 15 dINufES NATURAL 3.11 TORNAD0/ STORM PHENOMENA ,

Winds in excess of design level, greater tnan 125 dPet EARTHQUAKE Greater than SSE levels 0.22g FLOOD Greater than design level or failure to protect equipment which'is required for safe shutdown or safety systems at lower levels

(

FIRE 3.12 FIRE AFFECTING SAFETY SYSTEMS REQUIRED FOR SHUTDOWN As judged by the GSS witn advice or tne Fire origade leader EXPLOSION 3.13 AFFECTS SAFETY SYSTEMS REQUIRED FOR SdUTDOWN WITHIN SEC'JRITY '

PROTECTED AREA 1

AIRCRAFT 3.14 CRASH AFFECTS VITAL STRUCTURES BY IMPACT OR CRASH FIRE OR MISSILE IMPACT PLANT STATUS 3.15 OTHER PLANT CONDITIONS EXIST TdAI WAR &lNI OR CONDITIONS ACTIVATION OF EMERGENCY CENTERS AND ci0NITORING AS EVALUATED TEAMS OR A PRECAUTIONARY PUBLIC NOTIFICAf10N BY GSS l

l l

3 8- 2 --

l

spect: Prtcaruro No, Site Emergency EPIP-4 F19e o of o 8cce)

Revision N o, Oate J# #

2 DATE TIME / INITIALS 4.0 EMERGENCY ACTIONS NOTE: AFTER COMPLETING EACH TASK, record time and initials or N/A (not applicable).

4.1 Upon recognition that any of the aoove Emergency Action l levels have been exceeded, the Group Shift Supervisor i shall assume the duties of tne

/ Emergency Director. l t

/ 4.2 Sound the appropriate aiarm (as necessary). .

4.3 Announce (or have announced) the following message over the Public Address System:

ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONdEL:

THE PLANT IS IN A SIfE EMERGidCY CONDIII0d. ALL ON-CALL EMERGENCY RESPONSE PERSONNEL REP 0df f0 EMERGENCY STATIONS. EAflNG, Odid4InG, Add 6dO41aG IS PROHIBITED UNTIL FURTHER NOTICE.

/ Repeat Announcement 4.4 Announce to Control Room personnel enat has assumed the (Name)

/ duties of Emergency Director.

4.5 Notify OCNGS Security, Ext. 6954, 6950 and direct enem to activate the pagers of the On-Call Initial Emergency Response Team on duty (Team 1,

/ 2 or 3) .

Instruct Security to contact one member to fill eacn position on the Full Mobilization Emergency

/ Duty Roster 4.6 Assign a Communicator to make notification to

/ persons and agencies listed in Attacnment 1.

s

P= t k.

t i

Suoiect: Peortura No.

Site Emergency EPIP-4 Pega 7 sf a seqes Revesson N o. Case 3,;,,,

3

( .

' I DATE l

TIME / INITIALS __ _

4.7 Complete Attacnment 2 " Initial Notification dessage" and give it to the Communicator for transmission to tne New Jersey State Police witnin 15 minutes of event !

classificaton and to notify the Nuclear Regulatory Commission as j

/ soon as possible. 1

4.8 Activate

/ The Operations Support Center (EPIP-27)

/ The Technical Support Center (EPIP-26)

/ The Nearsite Emergency ' Operations Facility (EPIP-23)

/ The Parsippany Technical Functions Center (EPIP-17) a,nd the Farsite Emergency Operations facility at

/ a reduced manning level (EPI.?-28) 4.9 Initiate Personnel Accountability in accordance l

/ with EPIP-12 l l

4.10 Initiate and continue offsite dose projections

/ in accordance with EPIP-9 4.11 Initiate onsite and offsite radiological surveys

/ in accordance with EPIP-10 and EPIP-11

/ 4.12 If fire is involved, implement EPIP-d 4.13 Periodically fill out Attachment 3, " Additional Information Message" and give it to tne Communicator for transmission to the Nuclear Regulatory

/ Commis s ion.

NOTE: Do not give ene " Additional Information Message" to the New Je rsey State Police.

When requested by tne udP, complete Attachment 5 "0CNGS Station Status Checulist Message" and give it to tne Communicator for transmission to the Bureau of dadiation Protection (BRP).

4.14 As required, initiate damage control activities

/ in accordance witn EPIP-14

/ 4.15 If personnel are injured, implement EPIP-7 ,

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P*ocatura No. l l Suotect:

E193 6 Of a 3eges i Site Emergency EPIP-4 Revision N o. 2cre 2 J/4/o2 DATE I TIME / INITI ALS I

4.16 Complete Attachment 4, "INP0/ ANI dessage" i

/ and give it to the Communicator for transmission 1 l 4.17 If a report of personnel accountability nas i not been received within 30 minutes, contact j

/ Security (6954, 6950) for a scatus report {

4.18 If personnel are unaccounted for, implement ;

! . / Search and Rescue (EPIP-22) !

l 4.19 Activate the Remote Assembly Area (EPIP-ld) l

/ if Site Evacuation is to be implemented. (

l i

4.20 Implement Site Evacuation (EPIP-13) upon j

/ completion of personnel accountability (

4.21 Based on assessment of plant conditions:

f j 4.21.1 If recovery conditions nave I

been met , initiate the decovery i / Pnase in accordance witn EPIP-29. .

4.21.2 If recovery conditions have not l

been met but site Emergency Action levels are no longer being exceeded, (

de-escalate to a lower emergency {

class by performing notifications I in accordance with:

/ Alert (EPIP-3)

/ Unusual Event (EPIP-2) 4.21.3 If emergency action levels exceed {

those for a Site Emer'gency, escalate i

/ to a General Emergency (EPIP-5) f k

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Setect: P*oczura No.

Site Emergency EPIP-4 49e i M2 4qss Rension N o. Octs 2 3/4/04 ATTAC&ENT I COMMUNICATOR'S CHECKLIST - SITE Er1ERGENCY DATE TIME / INITIALS l

/ 1. Notify the on-duty Snif t Tecnnical Advisor

/ 2. Notify the senior Radiological Controls representative on shift j l

/ 3. Notify the on-call Emergency Director

/ 4. Notify the on-call Emergency Advisor NOTE: The Emergency Advisor will notify tne VP-Nuclear Assurance , Office of the President j GPUN, and the Management Oversight Committee j Ins truc t the Emergency Advisor in tnese duties i

5. Notify the New Jersey State Police within 15 minutes of classification. Use completed Attacament 2 " Initial Notification Me s sage " witn Emergency Director approval Primary: State Hot Line (Notification Line)

/ Alternate: (609) 882-4200 (If Primary Line is out of service)

NOTE: If State Police Verification call is not received within one minute, re-e s taolis n contact via State tio t Line and request verification call on tne State Police Verification Line immediately. Determine it alternate verification means is required. It so, instruct State

Police to vertry of dialing (609) 693-6066 g (609) 971-0220

6. Notify the United States Nuclear Regulatory Commission Operati,ns Center. Use Attachment 2 format.

Primary: NRC-ENS Line (Lift receiver from cradie)

Alternate : 1) Ccmmercial via Bethesda (301) 492-8111

2) Commercial via Silver Spring

(~301) 427-4056

3) NRC-HPN Line-Dial 22 or *22 ( fouen-fone)

/ 4) Commercial via Bethesda (301) 492-7000 NOTE: Open-Line Communications with NRC is to oe maintained on ENS Line enrougnout tne emergency situation ATTACHMENT 1

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l Peccyrura No.

Suotect: l, Site Emergency EPIP-4 NO 2 Of 2 %qos .'

9evision N o. Octe g gj COMMUNICATOR'S CdECKLIST, CONTINOED:

(Attachment 1)

Time / Initials

7. Notify the Nuclear Regulatory Commission and otner agencies directed by the Emergency Director using l

/ Attachment 3 format j

8. Notify the following agencies using Attacament 4 tormat:

/ Institute of Nuclear Power Operations l Telephone: (404) 953-0904 i

/ American Nuclear Insurers Telephone: (203) 677-7305

9. When requested by the BRP, complete Attacnment 5 and transmit message via the BdP autoring line located in I

/ the Emergency Command Center (GSS Office) l t

i l

ATTAC&lENI 1

(

1 l

)

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- _ _ __ , ___- 1 Sveiect: P'oce uro No. .

Site Em2rgency EPIP-4 4 43 1 sf I %qes !

i 9evision N o. Oate g l l ATTACHMENT 2 INITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERCISE, THE ctESSAGE WILL BEGIN AND END WITH THE PHRASE, "THIS IS A ." EXAdP LES:

"THIS IS A DRILL." "THIS IS A COMMUNICATIONS TEST." "THIS IS AN EXERCISE. " "THIS IS NOT AN EXERCISE --

I REPEAI --

IHIS IS dof Ait EXERCISE."

(

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATION

- .- _ _ = _ ______.._

I THIS IS A NOTIFICATION OF A SITE EMERGENCY CLASSIFICATION THIS EVENT WAS CLASSIFIED AT OH (Time - 24 hr. clock) (Date)

[ ] THERE IS NO RELEASE IN PROGRESS

[ ] WE HAVE A CONTROLLED RELEASE IN PROGRESS

[ ] WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS

, [ ] NO PROTECTIVE ACTIONS ARE RECOMMENDED

[ ] WE RECOMMEND SHELTERING FOR THE FOLLOWING DIRECIIOun SECTOR (S)

[ ] WE RECOMMEND EVACUATION FOR THE FOLLOWING DIRECII0dn SECTOR (S)

APPROVED EMERGENCY DIRECTOR DATE TIME-24 dd

. _ _ _ . __. .. ==.

TIME NOTIFIED / VERIFIED THIS MESSAGE HAS BEEN IRANSMIIIED IO:

/ [ ] NEW JERSEY STATE POLICE

/ [ ] UNITED STATES NUCLEAR dEGULAI0df COMaISSIda (DATE) (COMMUNICAIOR)

VERIFICATION OF MESSAGES ARE COMPLETED OdLY AFIEd RECEIVIaG j NOTE:

AGENCY HAS RESTATED MESSAGE CORRECTLY IN ITS ENIIRETY nACK TO THE OYSTER CREEK COMMUNICATOR ;

ATTACHMENT 2 l l

l

~

l Su2j:ct: Procsdura No. l Site Emergency EPIP-4 l Page 1 of 4 ':,

Revision No. Date 2 l 3/2/82 I

i ATTACHMENT 3 I ADDITIONAL INFORMATION MESSAGE l

Check ( ) all appropriate information l

DATE i

TIME ,

1

1. This is acting under the Direction of the Emergency (Emergency Director)

Director at Oyster Creek Nuclear Generating Station. The following is provided as additional information for the initial notification of the (circle one) Unusual event; Alert; Site Emeroency; General Emercency.

2. DATE/ TIME OF CLASSIFICATION

a. Time: (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock) l

b. Date: Month Day Year

3. There (circle one) is/is not an Emergency Classification change. The classification is: (circle one) Unusual Event; -

Alert; Site Emergency; General Emergency. ,

4. Plant Status .

a. Reactor (circle one) is/is not shutdown.

(

. ATTACHMENT 3

1

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Subject:

Procedure No.

l

' Site Emergency '

, Revision No.

2 : Date3 /2/82 ATTACHMENT 3 (cont'd)

b. The plant (circle one) is/is not in a safe condition

c. Reactor is subcritical, coolant is being maintained over the core, and containment integrity is satisfactory.

5. Type of release (circle one) airborne; liouid; surface soill. i

6. Meteorological Data l

a. Wind speed MPH

b. Wind direction (toward)

c. Stability class (circle one) unstable; neutral; stable

d. Precipitation (circle one) rain; sleet; snow

7. Gaseous Radiological Data l

I a. Noble Gas release rate UCi/sec

b. Iodine 131 release rate uCi/sec

c. Release (circle one) has/has not terminated

d. Actual or estimated duration of release:

I l

( 8. Liquid Radiological Date a.

Release concentration uCi/cc

b. Release rate UCi/sec

c. Release (circle one) has/has not terminated I d. Actual or estimated duration of release

e. Estimated total release uCi l

l l

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ATTACHMENT 3

- = =

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Subject:

Procedure No.

p site Emergency gpyp.4 lPage 3 e 4 ' ,,

/ Revision No. . Cate ATTACHME!!T 3 (cont'd) 2 3/2/82 l _

9. Projected dose rates and integrated dose (Based on actual or projected duration of release)

! WHOLE BODY

a. Site Boundary mr/hr mrem

b. 2 miles mr/hr mrem

c. 5 miles mr/hr mrem t

d. 10 miles mr/hr mrem ,

J

10. Projected Iodine Concentration and Integrated Dose Commitment {

I (Based on actual or projected duration of release) . J l

THYROID

a. Site Boundary uCi/cc mrem

b. 2 miles uCi/cc mrem

c. 5 miles UCi/cc mrem

d. 10 miles UCi/cc mrem I

11. Estimate of surface contamination dom /100 l cm2 (obtain from field data) mrem /hr

12. Emergency Actions in progress:

l

a. Radiological survey teams onsite .

l

b. Radiological survey teams offsite

c. Onsite fire brigade

d. Of fsite fire department

e. Damage Control

f. First aid teams onsite

g. Ambulance service

h. Medical support

1. Environmental surveys offsite J. Other, specify

. 1 s ATTACHMENT 3

1 Ill Susiect: Proceture No.

EPIP-4 Faqe 4 Of 4 acqes Site Emergency Revision N o. Octe 3/ 10L 2 1 e i Attachment 3 (cont'd) l l

1 l 13. Additional support required (specify) i i

14. The condition may change to an (circle one) LJnusual Event; Alert; Site Emergency; General Emergency

15. Offsite population sector (s) (refer to Emergency Planning l Zone Sector map) affected are ,

I

16. The following changes in prdtective measures are recommended for the population in these sectors.

a. None

b. Notify (projected offsite dose ) I

\

c. Take shelter (projected offsite dose ) {

d. Evacuate (projected offsite dose )

17. Approved (Emergency Director / Emergency Support uirector)

I l

(Date) (Time)

18. Transmitted To: TIMd: dOIIFIED/Ver(IFIcu.

a. United States Nuclear Regulatory

(

Commission. / 1 1

b. New Jersey Bureau of Radiation )

Protection. /

c. /

l (Communicator) (Date) l l

l AITACdMENT 3 l l

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1 t

Suoioct: Procxurs No. l Site Emergency EPIP-4 PSO 1 Of 1 4cs I 4ension N o. Oofo y 3/4/04 ATTACHMENT 4 I

NOTIFICATION TO: INSTITUTE OF NUCLEAR POWER OPERAIIONS AND AMERICAN NUCLEAR INSURERS flf MESSAGE FORMAT l

1. This is at

( Name) (Title) !

Oyster Creek Nuclear Generating Station. We have declared A/AN f I

Site Emergency condition at (Event Classification) (Time)

2. Description of Emergency:

I i

j l

3. Approved ;

(Emergency Director /raergency Support Director) I (Date) (Time) 4

4. Transmitted to: Institute of Nuclear Power Operations

. (404) 953-0904 (Time)

American Nuclear Insurers I

(203) 677-7305 (Time) i (COMMUNICATOR) (DATE) 1 l

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5

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1

- ATIACHMENI 4 !

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Puc; cura No, Suspet: i Site Emergency EPIP-4 Pec3 1 Of 2 3eq:s 9evision Na y Octe 3j j3 f

ATTACHAENT 5 l OYSTER CREEK NUCLEAR GENERATING STATION STATION STATUS CHECKLIST FOR IRANSdISSION TO NEW JERSEY BUREAU OF RADIATION PROTECTION Date:

l Time:

1. Date and Time of Incident:Date: Time: -(24-Hr. Cloca) !

{

2. Accident Classification:(circle one) UNUSUAL EVENT ALERI SITE EMERGENCY GENERAL EMERGENCY - l

3. Type of Release: (circle one) ' GASEOUS LIQUID gl

4. Cause of Incident and System Involved (if known):

}

5. Is Reactor Shutdown: (circle one) Yes No

6. Gaseous Release Information (a) Release Terminated: (circle one) Yes ,

No (b) Estimated Duration of Release: Hours (c) Type of Gaseous Release (circle one) Elevated Ground (d) Windspeed mph m/sec (e) Wind Direction: From: (0) Toward (0)

Affected Sector: (Compass Point)

(f) Stability Class: (circle one) Unstable deutral Stable (g) Release Rate Noble Gas: Ci/Sec.

(h) Release Rate Iodine (if known) Ci/Sec.e

7. Liquid Release Information (a) Release Terminated (circle one) Yes No (b) Estimated Duration of Release Hours (c) Estimated Release Concentration uCi/cc f

(d) Release Rate gpm ATTACHMENT 5

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, 1 Sociect: P'ocaturs No.

EPIP-4 P14* 2 of 2 seqes Site Emergency Revision N o. Octe g ATTACliMENT 5 (cont'd)

8. Projected Of fsite Doses (a) Whole Body Distance Miles) Dose Rate mrem /hr Time to Reacn PAG (nrs. ) .

1. i

2. ,

3.

4.

5.

l (b) Child Thyroid Distance Miles) Dose Rate Rem /hr Time to Reacn PAG (nrs.)

1.

2.

3.

4.

5.

t

9. Recommended Protective Actions:

10. Status Checklist approved for transmission to NJBAP oy Emergency Director / Emergency Support Director:

Signature Time

11. Status Checklist transmitted to NJBRP:

Time Transmitted to: (Name)

(Communicator) (Position) (Date) l 1

AIfACMENT 5 l

(

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b EDIN-5 Page 1 Of 6 j Date issued effective Date l Jersey Central 2 m /81 2nus2 - 2nus2 i

' Power & Light Company Revision NO. .

l Date 3/2/82 uc k GENERAL EMERGENCY Authortred By aA ,

Director Station Onerations l Approfal/ C 4L k p s jfnJTQXMLyt.

l U d J. j l

Ovster k Nuclear Generatina Station List of Effective Pages Date itevision Number 1 3/02/82 2 2 3/02/82 2 1

l 3 3/02/82 2 4 3/02/82 2 1 5 3/02/82 2

?

! 6 3/02/82 2 I

( .

Attachments Attachment 1 (2 pages) 3/02/82 2 Attachment 2 (1 page) 3/02/82 2 Attachment 3 (4 pages) 3/02/82 2 Attachment 4 (1 pages) 3/02/82 2 l Attachment 5 (2 pages) 3/02/82 2 NON-CONTROLLFD l

This Document Will Not Be K[pt Up To Date

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- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._____________________________________A

4 Setect: Pucmure No.

GENERAL EMERGENCY EPIP-5 40 2 sf 6 4q:s t

9evision N o. Octe f

l 1.0 PURPOSE 1.1 Ihe purpose of this procedure is to define tne conditions tnat snail be regarded as a General Emergency for Oyster Creek Nuclear Station and to:

1.1.1 Ensure necessary actions are taken to protect ene nealtn i

and safety of the public.

1.1.2 Ensure necessa ry actions are taken to notity orisite emergency response organizations.

1.l.3 Mobilize the emergency response organizations to initiate' appropriate emergency actions.

1.2 The Emergency Director is responsible for implement 1nd tnis procedure.

l.3 Emergency Director responsibilities tnat may not ce delegated

(

include:

l.3.1 Decision to notify offsite emerdency management agencies.

1.3.2 Making protective action recommendations as necessary to of fsite emergency management agencies.

1.3.3 Classification of Emergency Event 1.3.4 Determining the necessity for o'nsite evacuation.

1.3.5 Authorization for emergency workers to exceed 10 CFtt 20 radiation exposure limits.

2.0 ATTACHMENTS 2.1 Attachment 1, Communicator's Cnecklist 2.2 Attachment 2 Initial Notification Message i

2.3 Attachment 3, Additional Information dessage 2.4 Attachment 4, INP0/ANI Message ]

.A. 1 2.5 Attachment 5, OCNGS Station Status Cneenlist ( BrtP) {

l 1

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1 suspen Pucerure N o.

GENERAL EMERGENCY EPIP-5 E'20 3 :f 6 Nges Revision N o. :: ate g

3.0 EMERGENCY ACTION LEVELS PARAMETER INITIATING CONDITION RADIOACTIVE 3.1 RELEASE CORRESPONDS TO OFFSITE RADIATION LEVELS GREATER EFFLUENTS THAN 50 mrem /h r TO THE WHOLE BODY OR GREATER THAN 250 mrem /hr TO THE CHILD THYROID AT SITE BOUNDARY.

Determine radiation level at site bounda ry or from offsite monitoring reports g by offsite Dose Assessment Procedure EPIP-9 PROJECTED 3.2 OFFSITE DOSE DUE TO THE EVENT IS PROJECTED TO OFFSITE EXCEED 100 mrem WHOLE BODY OR 500 mrem CHILD DOSES THYROID.

3.3 REACTOR WATER LEVEL CANNOT BE MAINTAINED ABOVE TOP OF ACTIVE FUEL LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS WITH A POTENTIAL LOSS OF THE THIRD BARRIER.

APPLICABLE TO ANY INITIATING EVENT THAT MAY LEAD TO THIS CONDITION OR ANY INITIATING EVENT THAT MAKES

( '

RELEASE OF LARGE AMOUNTS OF RADIOACTIVITY PRO BABLE.

FOR EXAMPLE:

(

Small or larg e LOCA's with failure of ECCS to perform leading to core melt or degradation. Loss of containment imminent.

Small or larg e LOCA occurs and containment performance is unsuccessful affecting longer term success of the ECCS. Could lead to core degradation or , melt in several hours without containment boundary.

Shutdown occurs, but requisite decay heat removal systems are . rende red unavailable. Co re l degradation or melt could occur in about ten hours I l

with subsequent containment failure.

Transient occurs plus failure of requisite core shutdown systems (scram or standby liquid control system) could lead to core meltdown in several hours with containment failure likely.

Any major internal or external events which could cause massive common damage to plant systems leading to any of the above OR b Loss of plant control

n. ..

Seag: Peorcturo No.

GENERAL EMERGENCY EPIP-5 F10 4 3f 6 Ecqos l

Rension N o. ,

Oefe

/

Date:

Time / Initials

/ 4.0 EMERGENCY ACTIONS Note: After Completing Each fa s et , record ' time ano incitials i

or N/A (not applicaole).

/ 4.1 Upon recognition enat any of tne aoove daergency Action levels have been exceeded, tne Group Snitt .su pe rviso r snait assume the duties of the Emergency Director.

/ 4.2 Sound the appropriate alarm.

4.3 Announce (or have announced) tne following message over tne l

/

f Public Address System: ATIENIION ALL P6dSONNEL, A11r.N 110d ALL PERSONNEL: THE PLANT IS IN A GENddAL c.dddudaGi CONDITION. ALL ON-CALL EMERGENCY RESPONSE PERSONddL nr.Pon t'

(

TO EMERGENCY DUTY STATIONS. EAIING, DdidKinG, And saVAlab l

IS PROHIBITED UNTIL FURTHER NOTICE.

Repeat announcement t

/ 4.4 Announce to Control Room personnel tnat Name has assumed tne duties of Emergency Utrector.

/ 4.5 Notify OCNGS Security, Ext. 6954, 6950 and direct enem to activate the pagers of Ine On Call Initial Emergency 1

Response Team on duty (Team 1, 2, or 3).

Ins truc t Security to contact one memoer to fill eaca position on the Full Mobilization Emergency Duty Roster.

4

/ 4.6 Assign a Communicator to make notification to persons ano agencies listed in Attachment 1.

o f

j

\

Suomet:

Proceruro No.

EPIP-5 ;D 5 g 6 eq.,

GENERAL EMERGENCY Revision N o. Octe

/

/ 4.7 Complete Attachment 2 "Ini tia l Notification Message" and l

give it to the Communicator for transmission to tne New _.

t Jersey Police within 15 minutes of event classification and to notify the Nuclear Regulatory Commis sion as soon as possible. l<

I

/ 4.8 Activate the Operation Support Center (EP1P-27),

/ the Technical Support Center (EPIP-26) and

/ the Nearsite Energency Operations Faciltiy (r. PIP-23).

/ the Parsippany Technical Functions Center (EPIP-17),

/ and the Fansite Emergency Operations Facility at a reduced I t

manning level (EPIP-28) l

/ 4.9 Initiate Personnel Accountability in accordance witn c.P1P-12.

/ 4.10 Initiate and continue offsite dose projection in accordan'ce i

with EPIP-9.

/ 4.11 Initiate onsite and offsite radiological surveys in accordance with EPIP-10 and EPIP-11.

f

/ 4.12 If fire is involved, implement EP IP-d j j.

/ 4.13 Periodically fill out Attachment 3,* " Additional Info rmation I

Message" and give to the Communicator for transmission to f the Nuclear Regulatory Commission.

Note: Do not give the " Additional Information dessage" to tne New Jersey State Police. When requested by tne ddP, complete Attachment 5 "0CNGS Station Status Cnec41ist ;

l 3

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Sotect: P'ocxure No.

GENERAL EMERGENCY EPIP-5 F19e 6 3f 6 seges Revision N o. 2cte 2 3/2/o2 7

Message" and give it to the communicator for transmission to the Bureau of Radiation Protection (8dP).

/ 4.14 As required, initiate damage control activities in accordance with EPIP-14.

/ 4.15 If personnel are injured, implement EPIP-7.

/ 4.16 Complete Attacnment 4, "INP0/Adl tiessage" ana g,ive it to tne Communicator for Transmission.

/___ 4.17 If a report of personnel accountability nas not oeen received within 30 minutes , contact Security (6954, 6950) for a status report.

/ 4.18 If personnel are unaccounted for, implement Searen ana Rescue (EPIP-22).

/ 4.19 Activate the Remote Assembly Area (EPIP-18)

/ 4.20 hpon completion of personnel accountability, implement Site Evacuation (EPIP-13).

4.21 Based on assessment of plant conditions:

/ 4.21.1 If recovery conditions nave oeen met, initiate tne Recovery Phase in accordance witn EPIP-29.

4.21.2 If recovery conditions ' nave not been met out General Eme rgency Action levels are no longer being exceeded, de-escalate to a lower eme rgency class by performing notification in acco rdance with:

/ Site Emergency (EPIP-4)

/ Alert (EPIP-3)

A. / Unusual Event (EPIP-2) e

' ;po g o.

Sooteen P9c0 M Na GENERAL EMERCENCY EPIP-5 4c3 1 sf 2 Nges i 4evision N o. 2

ate 3jjjaj

?

Date: ATTACHMENT 1 COMMUNICATOR'S CHECKLIST -GENERAL EMERGENCY t

Time / Initials

/ 1. Notify the on-duty Snif t Tecnnical Advisor

/ 2. Notify the senior Radiological Controls representative on shift.

l'

/ 3. Notify the on-call Emergency Director.

/ 4. Notify the on-call Emergency Advisor Note: The Emergency Advisor will notify tne VP-auclear l Assurance, the office of tne President GP0d, and J the Management Oversight Committee. (

INSTRUCT THE EMERGENCY ADVISOR IN THESE DUTIES 1

/ 5. Notify the New Jersey State Police witnin 15 minutes or classification. Us e completed Attacnment 2 " Initial Notification Message" witn Emergency Director approval. l Primary: State Hot Line (Notification Line)

Alternate:* (609) 882-4200 (If Primary Line is out of Service)

Note: If State Police Verification Ca ll is not received ;

within one minute, re-establisn contact via State l Hot Line and request Ve ri fica tion call on ene f State Police Verification Line immediately. '

De termine if alternata verification means is.

required. If so instruct State Police to verify ,

by dialing (609) 693-6066 or (609) 971-0220.

/ 6. Notify the United States Nuclear Regulato ry Commiss ion Operations Center l Primary: NRC-ENS Line (Lift receiver from caole) l Alternate: 1) Commercial via Bethesda (301) 492-8111

2) Commercial via Silver Sprind (301) 427-4u5o

3) NRC-HPN Line-Dial 22 or *22 (Touen-tone)

4) Commercial via Bethesda (301) 492-7000 Note: Open-line communications witn NRC is to be maintained f on ENS Line throughout tne emergency situation.

l

/ 7. Notify the Ocean County Operations Center Use Attachment 2 format Primary: Ocean County Hot Line Attacament i

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r

Suotect: Proc:curo No.

GENERAL EMERGENCY EPIP-3 5593 2 of 2 8cces Revision N o. 2 Oate y Attachment 1, continued.

s

/ 8. Notify Lacy Township Use Attachment 2 format Primary: (609) 693 - 6636

/ 9. Notify the Nuclear Regulatory Commission and otner agencies directed by the Emergency Director using attacnment 3 format.

10. Notify the following agencies using Attacnment 4 format I

Institute of Nuclear Power Operations l

/ Tel: (404) 953-0904 {

American Nuclear Insurers

/ Te l: (203) 677-7305

/

11. When requested by the BRP, complete Attacnment 5 and transmit message via the BRP Auto Ring Line located in Ine Emergency Command Center (GSS Of fice).

l t

t Attachment 1

p. g ..

l Suotect: Pecer. dura u

~EPIP-5 hit 1 :f 1 %qos GENERAL EMERGENCY i

Rowsion % I 2 l, Care 3/4/oz f l ATTACHMENT 2 INITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERG1dE, IdE MESSAGE WILL BEGIN AND END WITH THE PHRASE, "THIS IS A _." - EXMP Lt.S :

, "THIS IS A DRILL." "THIS IS A COMMUNICATIONS IES I. " "1HIS IS M, EXERCISE." "THIS IS NOT AN EXERCISE --

I REPEAI --

IrtIS IS dof e EXERCISE."

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATION

= - - - _ -- _= -

i = -- _

< THIS IS A NOTIFICATION OF AN GENERAL EMERGENCY CLASSIFICAIION l THIS EVENT WAS CLASSIFIED AT ON (Time - 24 hr. clock) (Date) 1 _ _ ==. --

[ ] THERE 'IS NO RELEASE IN PROGRESS i

j [ ] WE HAVE A CONTROLLED RELEASE IN PROGRESS l [ ] WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS NO PROTECTIVE ACTIONS ARE RECOMMENDED !

l [ ] '

[ ] WE RECOMMEND SHELTERING FOR IRE FOLLOWING DIRECf1dut SECTOR (S)

[ ] WE RECOMMEND EVACUATION FOR THE FOLLOWING DIMECflodAL I SECTOR (S)

APPROVED I EMERGENCY DIRECTOR DATE IIME-24 rtR TIME NOTIFIED / VERIFIED THIS MESSAGE HAS BEEN IRANSMIITED IO:

l / [ ] NEW JERSEY STATE POLICE .

j

/ [ ] UNITED STATES NUCLEAR REGULAIORY C0cidISS10d 1

I l / [ ] OCEAN COUNTY OPERATIONS CENTER 4

e

/ [ ] LACEY TOWNSHIP (DATE) (COMMUNICATOR)

NOTE: VERIFICATION OF MESSAGES ARE COMPLETED ONLY AFIER ttECEIVING

) AGENCY HAS RESTATED MESSAGE CORRECTLY IN ITS ENIIRETY BACK l i TO THE OYSTER CREEK COMMUNICAIOR ATTACHMENI 2

n- t --

4

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Subject:

Procidura No.

GENERAT. EMERGENCY EPIP-5 Page 1 of 4 ': , l Revision No. : Date I 2 l 3/2/82 _ l I :

i l l , ATTACHMENT 3 1

?

ADDITIONAL INFORMATION MESSAGE i I. ,

Check ( ) all appropriate information .

DATE TIME {

l

1. This is acting under the l Direction of the Emergency (Emergency Director)

Director at Oyster Creek Nuclear Generating Station. The i

following is provided as additional information for the initial notification of the (circle one) Unusual event; Alert; i .

Site Emergency; General Emergency.

2. DATE/ TIME OF. CLASSIFICATION

a. Time: (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock)

b. Date: Month Day Year .

3. There (circle one) is/is not an Emergency Classification change.-The classification'is: (circle one) Unusual Event; Alert; Site Emergency;. General Emergency.

f

4. Plant Status

a. Reactor (circle one) is/is not shutdown.

! \

! ATTACHMENT 3

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Su': ject: Prcctdure No. j r E IP-5, Page 2 0: 4 's GENERAT, EMERGENCY Aevision No. ; Date g _ __ 2 3/2/82 l _

ATTACHMENT 3 (cont'd)

b. The plant (circle one) is/is not in a safe conditior?

c. Reactor is subcritical, coolant is being maintained over

( the core, and containment integrity is satisfactory.

f l

5. Type of release (circle one) airborne; liould; surface saill.

6. Meteorological Data

a. Wind speed MPH I

b. Wind direction (toward)

c. Stability class (circle one) udtable; neutral; stable

d. Precipitation (circle one) rain; sleet; -snow l 7. Gaseous Radiological Data '

a. Noble Gas release rate uCi/sec I

b. Iodine 131 release rate uC1/sec

c. Release (circle one) hggjhas not terminatedE

d. Actual or estimateo ' duration of release:

8. Liquid Radiological Date

a. Rel. ease concentration uCi/cc

b. Release rate UCi/sec

c. Release (circle one) h-is/has not terminated

d. Actual or estimated ' duration of release

e. Estimated total release ^ uCi ATTACHMENT 3 i t

J l

. I Procedure No. Page 3 - 4 7 ,

Suoj:ct: EPIP-5 __

GENERAL EMERGENCY Cate Revisico No. 3/2/82 2 1 -_

l or ATTACHMENT 3 (cont'd) 9.

Projected dose rates and integrated dose (Based on actua ij

.- - projected duration of release)

WHOLE BODY _ _ mrem l mr/hr

a. Site Boundary mrem mr/hr

b. 2 miles _ mrem mr/hr

c. 5 miles mrem mr/hr

d. 10 miles itment 10.

Projected Iodine Concentration and Integrated Dose Comm of release) .

(Based on actual or projected duration THYROID _ _ mrem

_uCi/cc

a. Site Boundary _ mrem uCi/cc

b. 2 miles mrem ,

uCi/cc

c. 5 miles _ mrem, uC1/cc

(,

d. 10 miles dom /100

11. Estimate of surface contamination __

mrem /hr cm 2 (obtain from field data)

Emergency Actions in progress:

J

_12 a.

Radiological survey teams onsite b.

Radiological survey teams offsite c.

Onsite fire brigade

d. Offsite fire department

e. Damage Control 1

f. First aid teams onsite l

g. Ambulance service h.

Hedical support

1. Environmental surveys offsite !

s J. Other, specify ' l ATT ACHMENT 3 O

Swiect: P%ce:ura %

CENERAL EMERGENCY EPIP-5 2 1 ge 4 :f a actes Revision '4 0. j Octe )j;j3; 4

Attachment 3 (cont'd)

13. Additional support required (specify)

14. The condition may change to an (circle one) Unusual Event ;

Alert; Site Emergency; General Emergency

15. Offsite population sector (s) (refer to Emergency Planning Zone Sector map) affected are .

9

16. The following changes in protective measures are recommended for the population in these sectors.

a. None

b. Notify (projectea offsite done 1

c. Take shelter (projected of fsit.e dose )

d. Evacuate (projected of fsite dose >

17. Approved

( (Emergency Director / Emergency Support utrector)

(Date) (Time)

18. Transmitted To: IIME: Wo r IFIr 0/ Vr.itI fir u.

A. United States Nuclear Regulatory Commission. /

B. New Jersey Bureau of Radiation Protection. /

C. /

(ua te)

D.(Communicator)

Af fACat%t i 3

(

e l

l

7- t --

Pene wa Nr.

Sumtect:

GENERAL EMERGENCY EPIP-5 4 00 1 :f 1 teq:s

%sion N o. Octe I .

ATTACHMENT 4 NOTIFICATION TO: INSTITUTE OF NUCLEAR PO4Ed OPERATIONS & AMERICAN NUCLEAR INSUdidS MESSAGE FORMAT

1. This is at Oyster Creen (Name/ Title)

Nuclear Generating Station. We have declared an/an GENERAL EMERGENCY condition at (Event Classification) (Time)

2. Description of Emergency:

( 3. Approved (Emergency Director / Emergency Support Director)

(Date) (Time)

Time

4. Transmitted To: Insitute of Nuclear Power Operations (404) 953-0904 To: American Nuclear Insurers (203) 677-7305 -

(Communicator) (Date)

Af fACncir.nf 4

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Swetect: Pmecure No.

GEN 2RAL EMERGENCY 2 PIP-5 sa ge i sf 2 seges Revision N o. ste g j, 1

?

ATTACHMENT *5 OYSTER CREEK NUCLEAR GENERATING STATION STATION STATUS CHECKLIST FOR IRANSMISS10d TO NEW JERSEY BUREAU OF RADIATION PROTECTION Date:

fime:

1. Date and Time of Incident: Date: Time: (24-nr. Clocx)

2. Accident Classification:(circle one) UNOSUAL dVENT Accaf SITE dHERGdNCY GENddAL LHedGENCY

3. Type of Release:(circle one) GASEOUS LIQUID

4. Cause of Inciden't and System Involved (if Known):

/ 5. Is Reactor Shutdown: (circle one) Yes No

\

6. Gaseous Release Information (a) Release Terminated: (circle one) Yes No .

(b) Estimated Duriation of Release: dours (c) Type of Gaseous Release (circle one) Elevated Ground (d) Windspeed mph m/sec (0) Toward (0)

(e) Wind Direction: From:

Affected Sector: (Compass Point)

(f) Stability Class: (circle one) Unstabic Neutral Staole (g) Release Rate Noble Gas: Ci/Sec.

(h) Release Rate Iodine (if known) Ci/Sec.

7. Liquid Release Information Yes No (a) Release Terminated (circ le .one)

(b) Estimated Duration of Release: Hours (c) Estimated Release Concentration uCi/cc (d) Release Rate gpm AffACnaddf 5 A

3 7- t --

e destect: P+ caturo % l Asge 2 Of ; 8sges CENERAL EMERGENCY EPIP-5 4evision % Octe 2 2/4/ol w

ATTACHMENT 5 (cont'd)

8. Projected Offsite Doses (a) Whole Body Distance Miles) Dose Rate mrem /nr fime to deaca PAG (nrs. )

1.

2.

3.

4.

5.

(b) Child Thyroid Distance Miles) Dose Rate Rem /hr Time to Reaca PAG (n rs. )

1.

2.

3.

4.

5.

9. Recommended Protective Actions:

10. Status Checklist approved for transmission to NJddP oy 6nerdency Director / Emergency Support Director:

Signature Time

11. Status Checklist transmitted to NJdRP:

Time.

Transmitted to: (Name)

(Communicator) (Position) (uate)

Af fACtMr:d f 5

p- t -.

_E N E JM !h$hN Page 1 Of 11 Date issuec Effective Cate Jersey Central 2n3/s1 2n2/e2 - 3/22/s2 r Power & Light Company ' Revision No. Cate

/ 3/82 SUOject: Offsite Dose Projections Authorizec Sy Director - Stataan Cperations Appr 'a cor I- % h f4 Hbbt9Lt ).

Pro' ~ t:

C/ ster Creek Nuc ear Generating Station LIST OF EFFECTIVE PAGES DATE ddVISION NUMt$e.d

,t 1 2/23/82 1 2 2/23/82 -

1 s 3 2/23/82 1

, 4 2/23/82 1 5 2/23/82 1 6 2/23/82 1 7 2/23/82 1 8 2/23/82 1 9 2/23/82 1 10 2/23/82 1 11 2/23/82 i ATTACRMENTS Attachment 1 (1 page) 2/23/82 i Attachment 2 (2 pages) 2/23/82 '

1 Attachment 3 (1 page) 2/23/82 1 Attachment 4 (2 pages) 2/23/82 1 Attachment 5 (1 page) 2/23/82 1 Attachment 6 (3 pages) 2/23/82 1 Attachment 7 (1 page) 2/23/82 1 Attachment 8 (1 page) 2/23/82 1 Attachment 9 (1 page) 2/23/82 1

, NON-CONTROLLED This Document Will Not Be Kept Up To Date s

u Sepet: P?cceiure No. ,

ISO ? U 11 seges Offsite Dose Projections EPIP-9 l 4evision N o. Octe i

? -

1 1.0 PURPOSE The purpose of this procedure is to provide to Radiological Controls l 1

Personnel and the Environmental Assessment Command Center.

1.1 Techniques and methods for calculating projected doses (whole body and child thyroid) which might result from airborne releases of radioactive materials from OCNGS.

1.2 Documentation and Accountability if 10CFR20, Appendix B, Table II, Column 2 concentrations for liquid effluents have been exceeded in the discharge canal initiating an Unusual Event emergency classification.

1.3 The Shift Radiological Controls Technician will be responsible for implementation of this procedure until activation of the Environmental Assessment Command Center.

2.0 ATTACHMENTS 2.1 Attachment 1 Meteorological Parameters Table 2.2 Attachment 2 Postulated Of fsite Doses from Design Basis Accidents.

2.3 Attachment 3 Source Strength Determination Table.

2.4 Attachment 4 Atmospheric Dilution Factors -

Elevated and Ground Release.

2.5 Attachment 5 Whole Body Dose Factors 2.6 Attachment 6 Graph - Radioiodine Concentration vs. Child Thyroid Dose.

2.7 Attachment 7 - Offsite Dose Projection Table.

2.8 Attachment 8 - Of fsite Monitoring Dose Projection Table.

2.9 Operating Instructions - TRS-80.

e

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l suoiect: Peencure No.

! Offsite Dose Projections FPTP 0 N93 1 N l' 4'8 r 4evision N o. Ocre 1 2/23/82 i

l 3.0 EMERGENCY ACTION LEVELS 3.1 As required by an Emergency Implementing Procedure.

l 3.2 As directed by the Emergency Director or his designee. '

4.0 EMERGENCY ACTION - AIRBORNE RELEASES INITIALS 4 .-1 ~0btain Meteorological Parameters from Control Foom Instrumentation j located on the right of Panel 13R. Update Meteorology approximately l

every fif teen minutes.

NOIE: Of fsite organizations for meteorological data are: l l

Department of the Air Force Department of the Navy i 609-724-3568/3994 201-323-2334 4.1.1 Obtain Wind Direction ( ) from cha rt Recorde r and rec o rd on Attachment 1. (wind is from this direction).

I 4.1.2 Calculate conve rted Downwind value by the following equations and record on Attachment 1.

4.1.2.1 If Wind Direction value from 4.1.1 is between 0 - 180 , then:

(Wind Direction ( ) + 180 ) = Conve rted j

, Downwind Valu,e ( )

4.1.2.2 If wind direction value from 4.1.1 is between 181 - 360 , then:

(Wind Direction ( ) + 180 ) = Conve rt ed Downwind Value ( )

4.1.3 De termine affected sector based on converted downwind t I direction using the following table.

i l

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p. g ..

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Suoiect reccxure No.

l ~

Offsite Dose Projections EPIP-9 peq3 4 :f 11 : qes I

r 4evision N o. 1 2sts 2/23/82

/ ,

Affected Sector ;

Converted Downwind Direction (0) Compass Point - --

l 349 to 0, 0 to 11 .. N 1

11 to 34 NNE l

34 to 56 NE 56 to 79 ENE 79 to 101 . E 101 to 124 ESE 124 to,146 SE 146 to 169 SSE 169 to 191 S 191 to 214 SSW 214 to 237 SW 237 to 259 WSW 259 to 281 W 281 to 304 WNW 304 to 326 NW 326 to 349 NNW f l

Record Af fected Sector (Compass Point) on Attachment 1 and 7.

4.1.4 Obtain At (temperature dif fe rential) between 380 ft. and 33 ft. elevation of meteorological tower and record on Attachment 1.

4.1.5 De te rmine Stability Class from d t( ), Re fe rencing the following graph and constraints.

t

k. .

i

;p. g..

l Select: A'ocerura No. ,

m"o U * "

Of fsite Dose Projections

Revision N o. 2ste 1 2/23/82 UNSTABLE NFi!TPAL ST A RT F-

-4 .' 0 -3 .I0 -2!0 - 1.' 0 i

-3.3 ff( F) -1,1 o If de is between (-3.3 F and -1.1 F) condition is I NEUTRAL.

o If dt is / (-3.3 F) condition is UNSTABLE.

o If be is 7 (-1.1 F) condition is STABLE.

Record stability class on Attachment I and 7. Also, reco rd on Attachment 2 for Design Basis Accident dose projection if applicable.

4 .1. 6 Obtain Wind Speed in mph. Calculate Windspeed in m/sec.

mph X 0.45 m/sec = m/sec.

mph

(

Re cord Results on Attachment 1 and 7. Also, . record on Attachment 2 for Design Basis Accident dose projection if applicable. Counnunica te Windspeed (mph), Converted Downwind Value, Stability Class and Af fected Sector to the Emergency Director for the " Additional Update Message"

~

4.2 Design Basis Accidents - Initial Dose Assessment.

4.2.1 The following are FDSAR referenced Design Basis Accidents:

, - Refueling Accident i

1

- Control Rod Drop Accident

- LoN af Coolant inside Drywell

- Steam Line Break Outside Reactor Building 9

\

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Suoiect: Anc3:uro No.

Offsite Dose Projections com o '

4evision N o. Octe 1 1 2/23/82 l r e Upon assessment of a design basis accident by the Emergency Director, utilize Attachment 2, " Postulated Offsite Doses from Design Basis Accidents." De te rmine

- dose in REM for the current stability class and windspeed as determined from page 1 Attachment 2, for Design Basis Accidents 1-3.

Basis Dose (Rem) = Dose (Rem) for 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months release Windspeed (m/sec) 4.2.2 Record Results on Attachment 2, Page 2 and communicate to.

Einergency Director.

4.2.3 Pe rf orm further dose projections utilizing Sections 4.3 through 4.6.

4.3 . De termine the Sourc e Strength - Elevated Release. Record data and Results on Attachment 3.

4.3.1 Obtain Stack Gas Monitor Value from Panel 10R, Channel A or B in counts /sec.

NME: If Stack Gas Monitor is offscale, notify Radiation Controls to dispatch a technician to the downwind 0.25 mi.le location to obtain dose rate. Proceed to Section 4.7 to project source strength from dose rate.

4.3.2 On Attachment 3, c irc le each ventilation system that is operating (as verified by green light indication on Panel 11R) and sum to obtain total Stack Flow.

i

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Seetect:

P'ocsiurs No. l i #

Offsite Dose Projections ' PIP o 4evision N o. 2 cts 1 2/23/82 4.3.3 Obtain conversion factor for uCi/sec per count /see in Channel A or B from Panel 10R.

NOTE: Use same Channel ( A and B) for conversion factor utilized for Stack Gas Monitor Value.

l 4.3.4 Det etuine the Stack Correction Factor from the Graph on l

Panel 10R as a f unction of Total Stack Flow.

4.3.5 Calculate the sou rc e s t re ng th in ci/sec based on the f ormula:

(Stack Monitor counts /sec) (Conversion f actor uCi/sec) (1.0.E-06 Ci)- Ci count /see uCi = see f (Stack Correction Factor) 4.4 De te rmine the Sourc e Strength - Ground Release. Re co rd Data and

(

results on Attachment 3.

4.4.1 Calculate Source Strength based on the formula:

Air Sample Activity X Release Rate X Conversion Factor = Source Strength 3

uCi X g X 4.72E-04 = Ci/see cc min where: uCi/cc = Air concentration in source of rele.ase as determined by Radiation Controls Dept.

ft3/ min = Release Rate as assessed by the Emergency Director or his designee 4.72E-04 = 2.832E+04 cc X 1 min X 1.0E-06Ci ft3 60 see uci NOTE: If Air concentration and/or release rate a re unavailable. Notify Radiation Controls to ;

I k

Suoiect:

P*ccxure No. l I 43 A U ages l Offsite Dose Projections FPTD o 11 8evision N o. 2cte

' 1 2/23/S2 7

dispatch a technician to the downwind 0.25 mile location to obtain dose rate. Proceed to ,

i Section 4.7 to project source s t re ng th from dose rate.

4.5 Project offsite Dose Rate from Sourc e Strength Data. Record Data and Results on Attachment 7. ,

'5' for elevated ( s t a'c k release),

4.5.1 Record type of release

'G' for Ground. l i

4.5.2 Enter 'l' in "Sourc e Strength Method" column to indicate that Source Strength was determined from plant parameters.

4.5.3 Ca lculate Whole Body Dose Rate. Initially, project dose l rate at 0.25, 2, 5, and 10 miles downwind based on the fo rmula:

Dilution Factor X 1 X Source Strength X Dose Factor = Dose Rate

- windspeed

-l Xu (m-2) X 1 (m/sec) X Ci X mrem /hr = mrem Q U see Ci/md hr where: Xu = Atomospheric Dilution Factor from Attachment 4 Q based on type of release, stability class, and downwind distance.

. -l 1 = Inverse of windspeed in (meters /sec).

u Windspeed obtained from Attachment 1.

Ci = Source Strength determined on Attachment 3 l sec j i

mrem /hr = Whole Body Dose Factor from Attachment 5 as a ci/m 3 function of time af ter shutdown. Obtain time !

I af ter shutdown from Emergency Director or his designee. l

[

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p. t ..

g,ct: Puceruro No. >

Offsite Dose Projections EP IP -9 40 9 sf 11 23es l Revision N o. :ste '

7 2/23/82 r

4.5.4 Project integrated Whole Body Dese from the formula:

Dose Rate X Estimated Duration of Release = Integrated Dose mrem X hr = mrem hr where: mrem = Whole Body Dose Rate at downwind distance hr 1

hr = Duration of release as estimated by the Emergency Director or his designee. Default

. Value = Two hour s.

4.5.5 Obtain Integrated Child Thyroid Dose by referencing Attachment 6, comparing Whole Body Dose Rate to projected exposu re time (Default value = Two Hours). Calculate Child 'Ihyroid Dose Rate by dividing Integrated Child Thyroid Dose by Projected Exposure Time to obtain Rem /hr.

f f'

4.5.6 Calculate " Time to Reach PAG" (Protective Action Guides-EPA-520) for Whole Body Dose Rate and Child Thyroid Dose Rate by the formulae:

Whole Body " Time to Reach PAG" (Hr. ) = 1000 mrem /Whole Body Dose Rate (mrem /hr)

Child Thyroid " Time to Reach PAG" (Hr.) = 5 Rem / Child Thyroid Dose Rate (Rem /hr) 4.5.7 Once all data and calculations ~ are recorded on Attachment 7, communicate results to Emergency Director. Provide the Noble Gas Release Rate (Ci/sec), estimated duration of release (hr.), Whole Body Dose Rate (mrem /h r) and Integrated Dose (mrem), Child Thyroid Integrated Dose (Rem) and Iodine Concentration (uCi/cc) for Site Boundary 1

1 O

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Swapct: P'o r_II'0 No.

Offsite Dose Projections EPIP-9 I1O 10 8f 11 8 cts ,

4evision N o. :ste (0.25 mile), 2 mile, 5 mile, and 10 mile downwind locations. These parameters a re necessary for completion of the " Additional Information Update Message".

4.6 If applicable, calculate integrated Whole Body Dose and Ch ild Thyroid Dose from of fsite monitoring data on Attachment 8.

4.6.1 Obtain dose rate net counts per minutes (NCPM) and scaler efficiency from monitoring team. Calculate air j concentration in uCi/cc by the formula:

uCi = NCPM x 7. 5E-11 cc % Ef ficiency where: 7.5E-11 = 4.5E-07 uci/dpm x 100 %

6.0E + 5 cc 4.6.2 Record monitoring location and azimuth - distance (degrees f

- miles) as determined from EPIP-11, Attachment 1.

4.6.3 Compare air concentration to projected exposure time on {

t Attachment 6 to obtain Child Thyroid Dose.

4.6.4 Calculate integrated khole Body exposure by multiplying dose rate by projected esposure time (hr. ).

4.6.5 Once all data and calculations are completed, communicate results to Emergency Director. I I

1 4.7 Project Source Strength from Offsite Monito ring Dose Rate Data {

i utilizing Attachment 7.

4.7.1 Enter '2' in Sourc e Strength Method Column to indicate l

that Source Strength was determined from Of fsite Dose Rate.

4.7.2 Enter type of release -E' for Elevated (Stack Release),

'C' for Ground.

k l

Suotect:

Precaturo No. !

FPTP o I'83 d #'918 Offsite Dose Projections movision N o. 2 ate 1 2/23/s2 l l

. l l

l 4.7.3 Enter Monitoring location downwind distance in miles.

4.7.4 _

Calculate _ Source Strength based on the formula:

Dose Rate x windspeed = Source Strength Dose Factor x Dilution Factor mrem /h r x u (meter /sec) = Ci mrem /hr x XII (m-2 ) Ec Ci/mJ Q l where : mrem = Whole Body dose rate at downwind distance t hr from Attachment 8 U = windspeed in meter /sec from Attachment 1.

mrem /hr = Whole Body Dose Factor from Attachment 5 Ci/m J as a function of time after shutdown M = Atmospheric Dilution Factor f rom l Q Attachment 4 based on type of release, stability class, and downwind distance.

4.7.5 Project offsite dose rate at other downwind distances using Sou rce Strength determined in Section 4.7.4. Enter ;

'2' in the "Sou rc e Strength Method" column for each projection. Reference Section 4.5.3 -

4.5.6 for calculation methodology.

4.7.6 Once all data and calculations are complete, communicate results to Emergency Director.

4.8 Utilize the TRS-80 Computer "Offsite Dose Projections" program referencing Attachment 10, if the system is available.

t l

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3= l =-

p,ccaturo No.

Suelect:

824) 1 .f I =cqes Offsite Dose Projections EPIP-9 aevision N o. :ste 2/23/32 ATTACHMENT 1 METEORLOGICAL PARAMETERS TABLE Char

Affected Recorder Converted Sector Wind Wind Wind Downwind (Compass At Stability Speed Speed Time /

Direct'on (*) Va lue ( *) Point) (*F.) Class (mph) (m/sec) Initial 1.

2.

/

3.

/

4.

5. /

/

6.

7. /

8. /

9. /

10. /

11. /

(

12. /

13. /

14. /

15. /

16. /

17. /

18. /

19. - /

20. /

Attachment 1

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9-t=

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' Procedure No.

Eprp.3 Page i c! 2 D 's " '-

j Offsite Dose Projections Revision No. Date k #

ATTACHMENT 2 1 2/23/92 r UbiULMED OFFSITE 00SES FROM DESIGN BASIS ACCIDENTS Note: All doses are in REM Whole Body Dose for a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months release at a windspeed of 1 mph (0.45 m/sec)

1. Refueling Accident (Rem) - Basis Dose Distance . Stability Class (Miles) Stable Neutral Unstable 0.25 2.55E-04 2.55E-04 4.00E-04 0.50 2.09E-04 2.27E-04 3.45E-04 1.0 1.45E-04 1.91E-04 1.73E-04 2.0 8.82E-05 1.18E-04 6.27E-05

2. Control Rod Drop Accident (Rem) - Basis Dose i Distance Stability Class (Miles) Stable Neutral Unstable <

0.25 3.0E-01 3.09E-01 4.55E-01 ,

l 0.50 2.64E-01 2.82E-01 4.00E-01 1.0 -

1.91E-01 2.36E-01 2.09E-01 2.0 1.27E-01 1.55E-01 7.82E-02 ]

3. Loss of Coelant Inside Drywell Accident (REM) - Basis Dose Distance Stability Class (Miles) Stable Neutral Unstable 0.25 /.45E-06 7.55E-06 1.09E-05 0.50 6.36E-06 6.91E-06 1.00E-05 t '

1.0 4.64E-06 5.73E-06 5.09E-06 2.0 2.91E-06 3.64E-06 1.91E-06

4. Steam Line Break Outside Reactor Building (REM) - Basis Dose Distance Windsoeed Basis of 50moh, DO NOT DIVIDE BY WIND SPEED (Miles) Whole Booy Oase (Rem) 0.25 3.6E-06 0.50 2.0E-06 1.0 8.6E-07 2.0 3.2E-07 l 5.0 6.6E-08 )l 10.0 1.9E-08 Attachment 2 Page 1 of 2 e o 6

,' EPIP-9 ATTACHMENT 2 (cont'd) Page 2 of 2 Rev. 1 2/23/82 6Postulated Off site Doses for Design Basis Accidents Worksheet Date / /

Time / Initials fj/ Type of Design Basis Accident

/

Wind Wind 0.25 mi. 0.50 mi, 1.0 mi, 2.0 mi. f Affected Stability Speed Speed Dose Dose Dose Dose [

Sector Class (MPH) (M/Sec) (Rem) (Rem) (Rem) (Rem)

(Compass Point)

/

1. .

2. - /

3. /

4. /

5. / -

6. /

7. __

/

8. '!

9. /

10. _

l Attachment 2 Page 2 of 2 l l

l l

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

4 ATracitaENr 3

,r- aJate /

SOURCE STRENGi .)EEERcilNATION fA*LE / - .

1. Elevated Release A. TOTAL STACK AIR FIDd Reactor Turbine Old Radwaste New Radwaste Standoy Gas Otner Bldg. (Cfa) Treatment (Cfa) (Cria) rotat (Cr.a) Time / Ta t t a a t s Bldg. (Cfe) Bldg. (Cfa) Bldg. (Cfe)

/

1.

2.

. 3. -

4.

l S.

B. STACK RELEASE SOURCE STRENGTH Stack Monitor Conversion Factor Stack Correction (Counts /Sec) (uCi/Sec per count /sec) Factor Ci/uCi Ci/Sec Time /inttials 1.OE-06 /

1.

l

, 2. 1.OE-06 /

j 3. 1.0E-06 /

i 4.

1.0E-06 /

)

i 1.0E-06 /

5.

C. GROUND RELEASE SOURCE STRENGTH Air ,.

Source of Release Activity Release Rate Conversion

( Area or Location) (uCi/cc) (ft 3

/ min) Factor Ci/sec rime /inttials

1. 4.72E-04

2. _

4.71E-04

3. 4.72E-04 .

. 4. 4.72E-04 EPu>-9 MW Rev. 1 Page 1 of 1 j

l

5. 4.72E-04 1

at tacanesn L .)

l Suo;ect: Procxure No.

814e 1 :f 7 8cqos Offsite Dose Projections EPIP-o

! 4evision Na 2cte .

ATTACRMENT 4 l

Atmospheric Dilution Factors as a Function of Downwind Distance and Atmospheric

! Stability Class ,

1 (

(

ELEVATED RELEASE I

t Dilution Factor _X_u. (m" ) ;

9 !

Distance (miles) Unstable Neutral Stable O.25 4.57E-12 2.77E-21 1.31E-20 l 0.50 8. 6 9E-07 8.64E-22 4.12E-21 4

i 1. 0 3.40E-06 5.68E-12 2.39E-18 2.0 9.3 7E-07 3. 3 2E-08 6.4 8E-11 1 3.0 5. 2 5E-0 7 5.39E-07 3.24E-08 <

(

4.0 3.92E-07 1.0 8E-06 3. 7 7E -0 7 (

5.0 3. 29E-0 7 1.32E-06 1.12E-06 f 10.0 1. 8 7E-07 1. 2 0E -06 3.3 3E -0 6 l

From: "CRISO-Dispersion and/or Dose Isopleths for Emergency-Class A Model" by Pickard, Lowe, & Garrick, Inc.

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Attachment 4

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Suolect:

a ecorure No.

FPIP.o 8Ge 2 Of 2 3ctes Of fsite Dose Projections Revision N o. 2ste 1 2/23/S2 ATTACHMENT 4 (cont'd)

Atmospheric Dilution Factors as a Function of Downwind Distance and Atmospheric Stability Class ELEVATED RELEASE Dilution Factor Xu (m" )

Q Distance (mile s) Unstable Neutral Stable 0.25 4. 8 3 E-0 5 3.18E-04 8.91E-04 0.50 1. 6 9E-05 1. 35E -04 4. 8 6E -04 1.0 4.15 E-0 6 5.27E-05 2.26E-04 2.0 9. 06E-07 2.16E-05 1. 0 8E -04 3.0 5.11E-0 7 1.02E-05 5.81E-05 4.0 3.88E-07 6. 9 5E-06 4.18E-05 5.0 3. 2 6E -0 7 5.25E-06 3.21E-05 10.0 1. 8 7E-07 2.11E-0 6 1. 5 0E-05 ;

i From: "CRISO-Dispersion and/or Dose Isopleths for Emergency-Class A Mode l" by Pickard , Lowe , & Gar rick, Inc.

1 l

Attachment 4 i

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EPIP-9 Rev. 1 2/23/82 I Page 1 of 1

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ATTACH.VINT 5 MCIE BCDY DOSE FJCOR AS A H2CTICN Cr TDS AFIER SHUIDCDM i

TDS AFIER SIEnDCbs MCIE BCDY DOSE FJCOR (154S )

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0FFSIfE GO::E JJECf10h fMLE uate: /- /

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1. OFFSITE DOSE - Wi10LE 80bY EXPOSUME

.Affected Type inte rateo lids N' Sector Dist; Stability Xu '- (m-2 ) II Ci mnem/nr pose date tirs. or Dose Time to ' Time /

' Source (Compass of-taa t t aa ts (m/sec) sec Ci/ m3 indes/n r_ t(e l . adem neacu t%

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. Source (Compass Dist. Exposure Exp. Time Thyroid Thyroid fime to a liae /

adem/hr (ilR) Oose Mate deaca PAG Inattats St. Meth. Point) Mile Dose (nem) 1.

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EPIP-9 Hev.1 10.

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Attachment 7 ,

r" AfTAP "ENf 8 EPIP-9 2/23/82-9:v.1 P;gn 1 of 1 ,

0FFSITE MONITORING 90SE PROJECTION fAMLE Date - / /

1. INTEGRATED DOSES Integrated Wnole Body Integrateu Monitoring . Az imu th Dist. Air Conc. Projected (hr) Cnild Thyroid Dose Kate Wnole nody Time /

( Degree s) Miles (uCi/cc) Exposure Time Dose (dem) adem/ar Oose (mdem) Autctaas Location 1.

2.-

3.

4

.4.

l 5.

6.

7.

8.

9.

10.

2. aid SAMPLE ACflVITY Monitoring A zimuth Dist. Conversion Time /

Location ( Degrees) Hiles NCPM ___ Factor 4 Etticiency uCi/cc Anactals i

1. 7.5E-Il / ,

I l

2. 7.5E-Il /

7.5E-ll /

3. ___

4. 7.5E-11 /

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5. .

6. 7.5E-Il / f 7.5E-Il /

7.

8. 7.5E-11 /

7.5E-Il /

9. ~

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10.

Attachment 8 m______ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _

a Suaiect: Ftocaturo No. l Of fsite Dose Projections EPIP-9 ma qe t af 1 Ocqes .

8evision N o. L Octs ,

etaalo i _

ATTACdMENT 9 s

OPERATING _INSIRUCTIONS Offsite Dose Projections for Gaseous Releases TRS-do

1. Ensure that Expansion Interface dutton off (dutton in "out" position)

2. Turn Line Filter on ;

3. Turn Line Printer on

4. Turn Expansion Interface Button on (Button in "in" postton)

Screen will display 'MEM SIZE'?

5. Press ' Enter' key on keyooard, Screen will display 'a/5 1.2 BASIC' ' REA,DY '

6. Inse rt Offsite Dose Calculation Program into Cassette ensuring that tape is previously rewound on left spool

7. Press " Play" on cassette

8. Ensure that Volume is on level "8"

9. Enter ' CLOAD "D"'

10. Press ' Enter' (Flashing asterick in top rignt siae or screen indicates that tape is loaking. Tape loads in approximately 4 minutes.)

11. Screen displays ' Ready'

12. Enter 'RUN' Press ' Ente r ' key

13. Instructions for general operation of program will oe displayed

14. To exit program at any time, press ' BREAK' key

15. To restart program enter 'RUN' Press 'ENTEd' Key i

Attacnment 9

*- t --

Procedure No.

ENE MEO EPIP-ll Page i Of 10

Date issuec Effective Date Jersey Central 2n9/el 2nus2 - 2m/s2

,. Power & Light Company ' Revision No. . Cate Suoject: Emergency Radiological Surveys Offsite 6

Director - Station Operations

/ /Mdgf/$

Projep(p: /

Creek

[

Nuclear Gener ing Station Oyft v

LIST OF EFFECTIVE PAGE DATE REVISION NUMBER i

1 3/4/82 1 2 3/4/82 1 3 3/4/82 l 4 3/4/82 1 5 3/4/82 1 6 3/4/82 1 7 3/4/82 L 8 3/4/82 1 9 3/4/82, i 10 3/4/82 L ATTACHMENTS Attachment 1 (23 pages) 3/4/82 1 Of fsite Monitoring Points Attachment 2 (2 pages) 3/4/82 L Of fsite Monitoring Checklist Attachment 3 (1 page) 3/4/82 L Dose Rate Survey and Air Sample Log Attachment 4 (1 page) 3/4/82 i Contamination and Biotic Media Survey Log NON-CONTROLLED s

This Document Will Not Be Kept Up To Date

Sustect: Pric x uro %

Emergency Radiological EPIP-11 40 2 2f 10 Nges Survays Offsite 4,

/

1.0 PURPOSE The purpose of tnis procedure is to provide guidance to ortsite radiation monitoring teams during declared emergencies. The orfsite Monitoring Teams are responsible for implementing tnis procedure.

2.0 ATTACHMENTS 2.1 Attachment #1, Offsite Monitoring Points 2.2 Attachment #2, Of fsite Monitoring Checklist 2.3 Attachment #3, Dose Rate Survey and Air Sample Log 2.4 Attachment #4, Contamination and Biotic Media Survey Log 3.0 EMERGENCY ACTION LEVELS 3.1 This procedure is to be initiated upon any of tne following conditions:

, 3.1.1 Alert (as determined by Procedure EPIP-3) 3.1.2 Site Emergency (as determined by Procedure EPIP-4) 3.1.3 General Emergency (as determined oy Procedure c. PIP-5) 3.1.4 Upon direction of the Emergency Director 4.0 EMERGENCY ACTI0riS 4.1 Proceed to the Environmental Assessment Command Ce nter at Building #12, Forked River Site to obtain' the key to a monitoring vehicle and radiation detection instruments.

4.2 Obtain a copy of EPIP-ll from the Environmental As ses sme nt Command Ce nte r. Utilize Attachment 2 to document procedural actions referencing the section listed for guidance. Record time and initials after complet' ion of eacn step. Proceed to emergency monitoring vehicle.

O 3 7* t ==

Suotect:

Protaturs No.

Emirgency Radiological 6 PIP-11 NO 3 af to %qos l

l . Surveys Offsite q ,,, ,, a n yg 7,,,

l 1 s / -* / o l l

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/ 1 i

NOTE: Obtain TLD and self-reading dosimeter from sit anc initiate dose card. Rezero dosimeter at 3/4 rull scale reading, updating dose card.

4.3 Verify that emergency monitoring nit is Locned. (ciaf oe sealed). If monitoring kit is not locked (sealed), completely inventory the kit per Procedure 108.2 using tne inventory Checklist for " Emergency Monitoring Kit" wnicn is included in tne kit. Note any deficiencies and transmit to EAC wnen radio cnec4 is performed.

4.4 Operationally check radiation detection instruments.

4.4.1 Visually inspect instruments for pnysical damage.

4.4.2 If applicable, verify battery condition of turning instrument switch ,to " battery" position. Re place batteries if necessary.

4.4.3 Verify radiation response by placing detectors of count rate meter and' dose rate meter per instructions on source template. Turn range scale to appropriate range of check reading marked on source template.

,4.4.4 Take a 1-minute reading with scaler and verify tnat check reading falls within ene range marked on ene instrument.

4.4.5 If instrument source checks are outside range, repeat twice. If one out of three checks fall within range, instrument is satisfactory.

4.4.6 On Attachment 2, Circle " SAT" or "LINSAT." for eacn respective instrument in Section 6. It "UNSAf" is circled, state the reason in the space provided.

3 p. 2 -.

Sootect: Peseccuro No.

Em2rgsney Radiological EPIP-ll ISO 4 3f 10 Ecqos Surveys Offsite q ,, ,,,n y ,, 7,,, l 1 J / 4 / o.! j l

r .

4.4.7 Notify EAC of radiation detection instrumentation

' status upon radio eneck.

4.5 Operationally check air sample and power supply.

4.5.1 Start gasoline-driven gensrator per instructions labeled on generator nousing. When " power" lignt illuminates, plug in air sampler to test operaoility.

4.5.2 If installed, check operability of DC/AC inverter by operating air sampler.

4.5.3 On Attachment 2, Circle " SAT" or "UNSAT" in Section 7.

If "UNSAT" is circled, state tne reason in tne space provided.

4.5.4 Notify EAC of air sampler and power supply status upon radio check.

4.6 Upon completion of equipment checks, conduct a radio cnecx witn the Environmental Assessment Coo rdinator (EAC) using Channe l 2.

Inform the EAC of emergency monitoring Kit status, ractation detection instrument status and air sampler power supply status.

Await futher instructions from the EAC.

NOTE: Ensure that dose rate meter is operating continuously.

4.7 Upon direction of the EAC, proceed to tne specified offsite monitoring locations. Refer to Attachment 1 for directions.

4.8 Upon arrival at the offsite monitoring location, notify tne cAC by radio. Perform radiological surveys as directed by tne dAC.

Record Model, Serial No., Date Calibrated, and Initials for Instruments at the bottom of Attachment 3 and 4.

s

9-t=

Suotect: Proc :Iurs No.

Emargency Radiological EPIP-il NO 5 d L0 M es I Surveys Offsite q ,,, ,,, n y o, 7,,,

1 3/4/o2

( '

l To obtain dose rate, exit venicle and taxe a reading at 4.8.1 waist level; starting at ene nignest scale or tne ,

l instrument and working to lower scales. decord ,

1 Monitoring location Number from Attacament 1, j l

designated "EMER.#," Time of Survey, dose rate and l intials on Attachment 3. Transmit all data to tne caC.

4.8.2 Comple te air samples and counting as follows: Record data on Attacnment 3.

4.8.2.1 Obtain AC Power for air sampler by use of tne gasoline generators (or DC/AC inverter is installed).

! 4.8.2.2 Place a particulate filter (rougn side out) and a silver zeolite cartridge in ;ne sample l

holder of tne air sampler. Place tne air sampler outside the venicle. Plug tne AC cord of tne air sampler into tne 110 Volt outlet of the power supply. Note time and turn sampler, to "0N". Run sample tor ten minutes. Turn .tir sampler and generator "0FF' . Record Time on Attacnment 3.

NOTE: Total flow = 6.0 E+05 (cc) = 60 L X 10 din X 1000 cc tiin L 4.8.2.3 Remove particulate filter from air sample

[

l holder. with tweezers and place in sample envelope. Record monitoring location and date and time of sample on sample envelope.

\

Return for submittal to EAC for analysis.

l .

l : ,- i ..

j l

. _ _ _ _ _ . _ _ _ _ J

Sootect: Pnexura No.

Emerg:ency Radiological EPIP-il ISO e 3f 10 3cqos Surveys Offsite q,,g an y, 3,,,

1 3/4/o2 1 1

s i 1 NOTE: If count rate meter indicates tnat 1

background radiation is greater l l

than 300 cpm, notify tne EAC and proceed to an area less than 300 cpm to count the air sample.

4.8.2.4 To count the air sample, place an unused silver zeolite cartridge in ene sample holder. Place ene detector on tne sample holder.

4.8.2.5 Place function switen or scaler to "10-minute" position and initiate counting cycle. Divide Scaler display by 10 to ootain

/ background counts per minute (BCPM). Record on Attachment 3. Remove unused silver zeolite cartridge.

4.8.2.6 Place air sample silver zeolite cartridge in sample holder with upstream (side facing out of air sampler sample nolder) beneatn ene detector. Count sample on scaler for ten minutes. Divide final scaler display of 10 to obtain gross counts per minute. Record on Attachment 3.

4.8.2.7 Remove silver zeolite cartridge from sample holder and place in sample envelope. Record monitoring location, and date and time of sample. Retain for submittal to EAC for

(

analysis.

e 1

]

17- 2.-

)

Suotect:

Petr.0 cura No.

Emargsncy Radiological EPIP-11 NO 7 af 10 ages

. Surveys Offsite Revision N o. Care l J/4/o4 A

l 4.8.2.8 Calculate net counts per minute oy i l

subtracting background counts per minute tros gross counts per minute (GCPM - BCDM = NCPM).

Record on Attachment 3.

4.8.2.9 Transmit monitoring location, time, net counts per minute (NCPM) ana /. scaler efficiency to the EAC.

4.8.3 Perform a contamination survey as directed of tne c AG.

Record on Attachment 4. Obtain smear discs and sample envelopes from tne monitroing kit and laoel witn cate, time, and monitoring location. Wipe tne smear disc 2

over a smooth surfaced 4" x 4" (100 cm ) area.

$ Determine tne background counts per minute NCPet) witn the count rate meter. If BCPM are greater enan 300 cpm, notify the EAC and proceed to an area less enan

. 300 cpm to count the smear. Obatin gross counts per minute (GCPM) by ecanting the smear on ene count rate meter. Subtract BCPM from GCPM to obtain net counts

~

per minute (NCPM). (GCPM-BCPM = NCPM). Calculate 100cm2 2

disintegrations per minute / 100 cm by multiplying NCPM by an efficiency factor of ten. (NCPM/100cm x 2 A 10 = dpm/100cm ). Record GCPM, BCPM NCPM/100cm and DPM/100cm on Attachment 4. Iransmit donttoring 2

location, time and dpm/100cm to EAC. detain smear in sample envelope for later analysis as directed oy )

\ I the EAC. l l

4

,. g.

l l

Sootect: Porcwe No. l i

Emergtncy Radiological EPIP-11 ISS) d 3f 10 8cqos Surveys Offsite ,,,,g, g

/ .

4.8.4 Pe rform soil samples as directed oy tne dAC, record on

' 1 Attachment 4. Obtain a plastic sample container ano )

I trowel from the monitoring kit. Choose a sample area free from leaves, grass or vegetation. Using tne trowel, scrape up and place in ene container tne top 2" of soil until container is full. Pe rf o rm a contact radiation survey with the Dose date Meter. Laoel tne container with time, date, dose rate and monitoring location. Record all data on Attachment 4. Transmit dose rate of soil sample to dAC. detain sample tor later analysis as directed by the EAC.

4.8.5 Obtain water samples as directed by tne BAC. Ootain

[ plastic s c rew-top water sample bottle from monitoring kit. Remove top, submerge bottle in water (tasting care not to disturb sediment) and fill bottle trom tne surface of the water. Recap bottle. Perform a contact radiation survey with the dose rate meter. Label bottle with time, date, dose rate and monitoring location. Record all data on ' Attacnment 4. Iransmit dose rate of water sample to dAC. Retain sample ror later analysis as directed by the BAC.

4.8.6 Obtain vegetation samples as directed of tne dae.

Obtain clippers and medium plastic cags from tne monitoring kit. Choose green (living) vegetation ror sampling. Clip off vegetation and place in sample oag,

(

. P = 2 ==

Svetect: p,ocrura No.

N43 Of Nq:e Emerginey Radiological EPIP-11 9 to Surveys Offsite Revision N o. Oate 1 3/4/o2 f

taking care not to include soil, large brancnes or roots. Take as large a sample as can ce fitted in tne bag. Tape the bag closed. Perform a contact radiation survey witn ene dose rate meter. Laoe l witn time, date, dose rate and monitoring location. Record all data on Attachment 4. Transmit dose rate of vegetation sample to EAC. Retain sample for later analysis as directed by the EAC.

NOTE: Use the radio (Channel 2) to communicate witn the EAC. If the radio is inoperative, call tne EAC by telepnone: (609) 971-4033/4029/4001 4.9 Minimize personnel exposure by moving out of areas of exposure I when performing calculations or awaiting furtner instructions.

Record all personnel exposures form dosimeter reading on Daily Exposure and Access Cards and return enem to dosimetry after completion of surveys.

4.10 Maintain all completed Attacnments 2, 3 and 4 anc Inventory l

Checklists for permanent records as directed by EAC. j 1

5.0 FINAL CONDITIONS 5.1 offsite monitoring is no longer required wnen releases of radioactive material to the environment have terminated and the Emergency Director has advised the EAC recall the survey team (s).

l 5.2 Upon direction of the EAC, return tne vehicle to Forked diver Site. 01eck vehicle Fue l Level, Generator Fuel Level (if s

e

S = 2 **

l helecf* Proc: cur 3 No.

193 3f 2cqe2 Emergency Radiological EPIP-11 to to Surveys Offsite 9,,, ,, a n y o, 7,,,

1 3/4/o2

/ .'

applicable) and perform a complete inventory of tne emerdency j 1

l monitoring kit per Procedure 108.2. Record ruel levels on :

Attachment 2, Section 11.

5.3 Submit vehicle key, Inventory Cnecklists and Attacnments 2, 3, and 4 to EAC for his review.

5.4 Re turn TLD to Dosimetry.

i s

i

\.

1 3 8- t --

I

r 3 OFFSITE HONITORING POINTS T

[ $gh 3 (From OCNGS Hain Gate & Rt.'9) g g g3w ggMg LOCATION DIRECTIONS REASON (;' -

2 N $$ ObbE $

N1 0 * -

0.65/ 0 qy ec rum pa M nq lot Left onto Rt. 9, lef t .just afte -

1045.9 intake canal and proceed to JCp&L Energy Spectrum h

N2 -

7* 1.2/ Intersection of Taylor lieTl onto Rt. 9, left onto Closest 1930.8 300 Lane & Kennebec Rd. at Taylor Lane, proceed 0.2 mi. to Residence g Gordon's Restaurant Kennebec Rd. g r-N2a N-2 2* 1.8/ Lakeside Drive

-1 175 Rt. 9 North to Lakeside Dr. NJ E 2896.2 Left onto Lakeside Dr. to location M Callahan residence, approx. d 3/4 ml. o N3 352* 2.5/

Along curb ad.jacent to 4

550 Left onto Rt. 9 approx. 1.5 $

4022.5 park at intersection of miles to Lakeside Dr., left on- M Lakeside Drive and Deer to Lakeside Dr. to Deer liead Head Lake Drive Lake Dr.

N4 N-4 Lacey Townshin Munici-

-1 354* 3.2/

5148.8 150 pal Bidq. parkinn lot Left onto Rt. 9 to Rt. 614 (Lacey Rd.), left onto Lacey {

[

g 110 AC Rd., 1.7 mile to Lacey Town- g g ship 11unicipal Bldq. on right. a mg

/

N5 N-5 E 32 North consnuter parkinn

-1 354* 4.21/

6757.8 800 lot at forked River Left onto Rt. 9 to Rt. 614 (Lacey Rd.), left onto Lacey [-

Service Area on G.S. Rd. to G.S. Pkwy. north on Pkwy. 110 AC Pkwv. to forked River Service Area.

O E N6 -

Apnrox. 1/3 mile west E S 356.5* 5.45/ 450 Left onto Rt. 9 to Rt. 614 8769.0 of Central Regional (Lacey Rd.), left onto Lacey ~

g High School along Pine- Rd. to G.S. Pkwy. north on g wald-Keswick Rd. at g g Pkwy. for 2.2 miles at overpass s o function with G.S. Pkwy. of Pinewald-Keswick Rd. mile $ "

Post 77.2 8 4 .

p ^

m 3

OFFSITE HONITORING POINTS '

t aJ . E G OC UR~G (From OCNGS Main Gate & Rt. 9) S

$ y 3

$h LOCATION DIRECTIONS REASON g N 25 b]

N10 -

E E5 O d E, 3e 9.6/ 100 Ocean County Courthouse Left onto Rt. 9 to Rt. 614 (La- h 15.446 (EOC) Toms River, 110 cey Rd), left onto Lacey Rd. to AC, parkinq lot G.S. Pkwv. north to Exit 81, i h east on Wa ter St.. for. a.5 ml. g to Ma in St. , lef t.one block to g Washington St., right on Wash- m ling to 2nd lef t to llorr.er St.

N10a -

359' 8.75/ 700 Lef t side of road before Left onto Rt. 9, continue left~ g 14,078 traffic light at inter- at Rt. 166 junction to G.S. "

section of G.S. Pkwy., Pkwy. Interchange approaching Q Rt. 530 (Oover Rd.) and intersection of Rt. 530 (Dover m Rt. 9. Rd.), left to roadside area be- g fore intersection. .]

Z N20 N-20 2500 Rt. 37, DOT Haintenance

-1 351.5* 10.8/ Left onto Rt. 9 to Rt. 614 (La-17,377 Yard, W. Toms River cey Rd.) to G.S. Pkwy, north to Exit it # , 1.9 mi. west to 00T Haintendace Yard on left. y

.m 1 1

5. 1 a 4

= 8" Gs S'

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-- - - .. - - _ - - - _ - - .- _. = _ . - . - . _ .. - - - - . - - - .

f* %

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"O7 OFFSITE HONITORING POINTS

{

al W E U EUJ" E MI~2 0 (From OCNGS Main Gate & Rt. 9) k LOCATION 5- Ebi

< ~ 6- -.s g;; m m t, DIRECTIONS REASON g -

W $5 0 8 b 5. m E

NNE1 -

19a ~0.45/ 50 Rt. 9 mile marker 80 at Left onto Rt. 9 to intak'e canal 9 724.0 0.C. Intake canal bridge at mile marker 80. Q Intersection of Bis- Left onto Rt. 9, 0.7 mi. to Closest

NEla -

23a :0.h/ ' 0 cayne Dr. & Nantucket traffic light at Beach Blvd. $

1126.3 residence G Rd. (#730 Biscayne Dr. ,right on Beach Blvd. to Bis-

"Kinn" residence) ' cayne Dr. (1st right)to Nan- S lucket Rd. Q F

NNE2 NNE-2 E

-1 23.Sa 1.7/ 200 Forked River State Lef t onto Rt. 9,1.6 mi. to E 2735.3 Marina SW corner of Forked River State Marina 0 parking lot, 110 AC "

NNE3- - %

24.Sa 2.5/ 500 Intersection of Rt. 9 & Left onto Rt. 9, 2.6 ml. to 0 4022.5 Sunrise Blvd. Sunrise Blvd. ,

M NNE4 - ~

27a 3.7/ 500 Intersection of Rt. 9 & Left onto Rt. 9, 3.9 mi to 5953.3 Laurel Blvd. parking lot Laurel Blvd.

NNES -

26a 4.6/ 500 7401.4 Intersection of Rt. 9 & Left onto Rt. 9, 4.9 mi. to h 40BM access road k WOBH radio station E E access road. "

rn2 NNE6

- 24 / 350

.S 5 0*4 Rt. 9, Pinewald Substa- Left onto Rt. 9, 5.5 miles on tion, opposite Anchor b right, beyond Serpentine Dr.

Boat Sales at large metal utility poles.

NNE6a . 32.Sa 6.8/ 300 g u 10,941 Edge of Bay, Bay Blvd. Left onto Rt. 9, 6.2 mi. to at Holly Park inn Bay Blvd., east on Bay Blvd. g k to end of road. u

\

Q t

NNE7 NNE- 23.Sa 6.0/ 2000 Rt. 9. Bayville, 110 7-1 9654.0 AC Lef t onto Rt. 9, approx. 6 NJ U mi. to Bayv111e.

Location "

I

, n n

^

0FFSITE MONITORING POINTS 't g

UO G (From OCNGS Main Gate & Rt. 9) nd b- 2M

{ _

M h$ $ LOCATION DIRECTIONS REASON m -

EEE 08$5 .

E NNE10 - 21.5* 7.55/ 225 Intersection of Rt. 9, Lef t onto Rt. 9, 7.6 mi. to 12,148 Veeder Lane, Ocean Gate multi-point intersection,.fust Dr. & Hill Creek Rd. at past HacDonald's to parking h parkinn lot, Baytown area near intersection on right. Es o

NNE -

Intersection of Chelsea . eft onto Rt. 9, 7.6 mi, go 10a 22.5* 8.65/ 100 k 33,937 Ave & Ocean Gate Dr. past MacDonald's, right on Ocear #

Gate Dr. to Chelsea Ave. (near vi end). !s

~ .

NNE -

16.50 9.9/ 1725 Intersection of Rt. 37 Lef t onto Rt. 9 to Rt. 614 (La- Q

^

10b 15,929 & Vaughn Ave., lot on cey Rd.) to G.S. Pkwy. to Rt.

first .junhandle exit 37 (Exit 82) east approx. 2.9 Q

from Rt. 37 mi. to Vaunhn Ave. intersec-3 tion, right fughandle to sta- M' tion.

NhE20 -

27,5* 10.5/ 1500 Bay Bridge Inn parking Lef t onto Rt. 9 to Rt. 614 (La-lot near Rt. 37 & west cey Rd.) to G.S. Pkwy., Exit 82 16,894 end of Bridqe at west to Rt. 37 east to Bridge, right {

[

o shore of Darneqat Bay into parkinq lot. E 1 S

e

_5 g

e Y

~ L' a

f .

? E E. E m -

PJ g I 'l

~

, m -

OFFSITE HONITORING POINTS E' sak E N3

[ t "C '

g g$ (From OCNGS Main Gate & Rt. 9) k

=

gggg LOCATION DIRECTIONS REASON g "

E c25 Uci E Intersection of Rt. 9 E NE1 -

47 0.3/ 0 Left onto Rt. 9. 0.2 mi. to Q 482.7 & farm road first right at farm road.

NEla - 42a 0.9/ 50 #732 Bermuda Dr. near lef t onto Rt. 9 to first traf- Closest 8 1448.1 Nantucket Rd. fic light, right onto Beach resident 5 Blvd. to Benmida Dr., right -

to end of road. Address #732. h .

Just past Nantucket Rd. m NE2 -

41 146/ Captain's Inn, Lacey left onto Rt. 9 to second traf- Good food 2574.4 100 Rd. Parking lot at fic light, right onto Lacey Rd. h m

rear. to Captain's Inn (near end of g road). g "a

NE3 -

42.5* 2.4/ 200 Game Farm Ocean Left onto Rt. 9, beyond second

3861.6 Residential Group traffic light, right onto Game Center Farm Rd. (between concrete pillars). 0.8 mi. to parking lot near bidos. y y n

NE4 -

51* 500 End of Sail Dr. near 3.1/ left onto Rt. 9, north 2.6 mi. o E 4987.9 intersection with to Sunrise Blvd., turn right, q< "

m3 Sunrise Blvd. approx. 1.4 mi to Sail Dr. (at 5 3x bend in road), left into Sail 7.

Dr. ~

Z NES NE- 47a 4.8/ 400 Laurel Blvd. at first Left onto Rt. 9, 1.9 mi. (past 5-1 7723.2 bend. Address #1063. second traffic light) to Laurel Blvd., right onto Laurel Blvd. g u (NJ Location #1068). r+ o to #1063 at curve (at street n light).

R S

. t 3 m

tJ O

v6

, m '

m OFFSITE HONITORING POINTS

.= -

= = > , E, bG

@ '3R~G (rrom OCNGS Main Gate & Rt. 9) 4 W E t3" 5Sb5 LOCATION k E. 2;$

t<;i t-"Ob DIRECTIONS REASON g -

m W gg" e eggs m gj NE10 -

44* 9.5/ 125 Intersection of Central Left onto Rt. 9, left at second 15,285 Ave. & 14th St., traffic light onto Rt. 614 (La- 6 Seaside Park cey Rd.) to G.S. Pkwy., North to Exit 82E, East onto Rt. 37 !

over bridge to Rt. 35 South 8 e (Central Ave.), right onto Cen- G tral Ave. to intersection of R Central and 14th St. r Q

NE20 - 37" 11:8/

E

18,986 Near intersection of Lef t onto Rt. 9, hf t at second 2500 Rt. 37 access road & E I traffic light onto Rt. 614 (La- Q

} 'Rt. 35 North (Central cey Rd.) to G.S. Pkwy., North "

Ave.) to Exit 82, east on Rt. 37, %

cross bridge to Rt. 35 North, 3 exit. At first traffic light, O turn rioht, "U-Turn" into '

service road area.

< 3

" -e. n

$. 1 8 4 2 "#

98

~ ,'.-

2 2 2 %

o,

, z u

Q 3:

I

- m s a

OFFSITE HONITORING P0lHTS y Li E hd M3

[y (From OCNGS Main Gate & Rt. 9) h

=

' 2 N

ggg LOCATION DIRECTIONS REASON g -

' E E. OEi$5 ENE1 -

70* 0.25/ 0 Yellow NJ Natural Gas left onto Rt. 9 approx. 25 yds. M 402.2 Co. marker approx. 100 south of N. Gate Access Rd. on

yds north of main en- left, g trance P-ENE2a -

67* 1.15/ '50 Intersection Tampa Rd. Lef t onto Rt. 9 to ist traffic Closest 1850.3 & Sandy Hook Dr. (#701 light (Beach Blvd.), right onto Resident .k Tampa Rd. "lononi" g Beach Blvd. to Forked River r-residence) Bridae. Just over bridge turn g right onto Sandy llook Dr. to =

2nd lef t (Tampa Rd.)

h m

ENE2 ENE-59.5* 250 Beach Blvd., lef t side Left onto Rt. 9 to ist traffic %

2-1 1.15/ of road after crossina Itoht (Beach Blvd.), right onto 1850.3 5 Forked River Bridge Beach Blvd. to southeast end of U Forked River Bridge. *

~

ENE3 70* Intersection of Beach 2.3/ 300 Left onto Rt. 9 to 1st traffic 3700.7 Blvd. & Tamiami Rd. light (Beach Blvd.), right onto m y Beach Blvd., over Forked River 7 3 i

Bridqe to next bridge (wooden), 2 9 continue over bridge to rioht E E fork (Tamiami Rd.). '

m3 58*

$ $5 ENE4 -

3.7/ 900 Parkinq lot at Sunrise Left onto Rt. 9 to Sunrise Blvd.

5953.3 Beach Club, - .~ ' '

right on Sunrise to Capstan Dr.

on left. Capstan Dr. straight to Sunrise Beach Club.

?

hi 8 s

~%

5 0

'J O

vm

, -s OFFSITE MONITORING POINTS m a >,

E, UJ '30 7 (From OCNGS Main Gate & Rt. 9) k f

5- 20; y ,

ME ti b JEb h LOCATION DIRECTIONS REASON -

g g $ r. E ENE7 -

67* 6.8/ 100 Island Beach State Park E 10,941 Left onto Rt. 9 to 2nd traffic Q Service Area parking light Rt. 614 (Lacey Rd.), left lot between North and on Lacey Rd. to G.S. Pkwy, South Swiming Area North on Pkwy. to Exit 82E, east h

parkinq lots, 8 on Rt. 37 across bridae to Rt. G 35 south (Central Ave.) to Is- S land Beach State Park, 3.5 mi. Q south of Park entrance gate to r swiming area parking lots. 8 ENE10 -

60* 7,35/ 1500 Island Beach State Park, left onto Rt. 9 to 2nd traffic Q 11,826 2.5 mi. south of Park lioht, Rt. 614 (Lacey Rd.), '

entrance at chained left on Lacey Rd. to G.S. Pkwy.

Q access road, on right. North on Pkwy. to Exit 82E. Q q

East on Rt. 37 across bridge to m Rt. 35 south (Central Ave.) to Island Beach State Park. 2.5 mi. south of Park entrance gate to intersection of chained g' y access road on right. 1 n i 1 8 4

= 8" P 9, .8:

2? E is 8 m

s U

2 e

~s y 0FFSITE HONITORING POINTS gi 585- .E l

- w -

. m WME dbe E (From OCNGS Main Gate & Rt. 9) 3 E $ ~ $d ggMg LOCATION DIRECTIONS REASON g U

' g$

E Mb Q m

E1 -

82* 0.3/ 0 Opposite Main Gate on Exit Main Gate road onto Rt. 9 5 482.7 Rt. 9 "

C S

Ela P

87.So 0.85/ SO Farm llouse, Old Lef t onto Rt. 9. rioht at first 2976.6 Finninger Farm (Eco- farm road (JCPAL) to second g loalcal Analyststs Lab) lef t to farm house r-un E2 -

87* 1.6/ 150 Intersection of lef t onto Rt. 9, right at first E 2574.4 Albatross Ct. A Orlando traffic light, to Forked River O Dr. Bridge, cross bridge to Elks "'

Club, right on Club llouse Dr., ?

4 blocks to Orlando Dr., left 5 on Orlando Dr. to Albatross Z Court (2nd left).

E7 -

94.5* 5.9/ 800 Old Coast Guard Station 9493.1 lef t onto Rt. 9. left at 2nd Watch Tower, Island traffic lioht onto Rt. 614 (La- n u Beach State Park, 110 cey Rd.) to G.S. Pkwy., North 7 3 AC to Exit 82E, east on Rt. 37 to 2 S Rt. 3S South (Central Ave.) to 8 E Island Beach State Park, to 7 "

mS mi. south of entrance gate to 5 32 station on left. ??

m em H

LM 8 8

D u

J

r %

OFFSITE HONITORING POINTS E ce >,

E, Uy UO7 (from OCNGS Main Gate & Rt. 9) )T f _ LOCATION DIRECTIONS REASON -

b* 2m N E5 Obb5 2

ESE1 -

111* 0.3/ o Yellow Marker (N.J. Right onto Rt. 9, approx. 0.1 482,7 O Natural Gas Co.) 0.1 mile south of 0.C. Main Gate g mile south of 0.C. Main a Gate y

8 ESEla ESE- 177* 0.8/ 200 Fork Area formed at Rinht onto Rt. 9, 0.5 mi.,

1-1 1287.2 intersection Bay Park- left on Bay Pkwy. to inter- y r-way & Dock Ave. Willow section with Willow & Dock Ave. v, also intersects here. E ESE2 -

End of Bay Parkway at Q

109.5* 1.85/ 150 Right onto Rt. 9, 0.5 mi., "

2976.6 Barnegat Bay left on Bay Pkwy. to end of street at Barnegat Day. z vi ESE7 -

109 6.3/ 450 Island Beach State Park left onto Rt. 9 to 2nd traffic 10,136 southern end of paved light, Rt. 614 (Lacey Rd.),

Park Rd. left on Lacey Rd. to G.S. Pkwy.

florth on Pkwy. to Exit 82E, m i east on Rt. 37 across bridge 7 3 to Rt. 35 South (Central Ave.) 2 2 to Island Beach State Park, go ET E 8.2 mi. south of Park entrance m2 to southern end of naved road. ~5 }g G9 2 %

5 t .,

I ji e !

8

f a T OFFSITE MONITORING POINTS E iis oc i E UsG UO7

@ (from OCNGS Main Gate & Rt. 9) S g E b* 25

{

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$5 0%$E

{ LOCATION' DIRECTIONS REASON g U S

SE1 -

126' O.36/ 50 Rt. 9, South of South Right onto Rt. 9, over dis-579.2 Access Rd., south of charge canal bridge, just 6

discharge canal bridge past South Access Road.

g,

~

o SEla -

140* 1.5/ 125 Southeast corner of Right onto Rt. 9, left on 2413.5 Bay Parkway, along Rt. Day Parkway. 5

9. next to residence y at 2 Bay Parkway i E SE2~ 300 130* 1.7/ South end of Shore Dr.

and on Barnegat Bay, Right onto Rt. 9. 0.75 mi.,

left onto Main St., 0.4 mi.

k 2735.3 O!

Waretown , to intersection of Lighthouse o Dr., right to end of Shore Dr. l u,i SE- ~4 SE7 127* 6.3/ 1500 Across the street from Right onto Rt. 9, to inter- I' m 7-1 10,136 the Coast Guard Station section of Rt. 72, left onto on Bayview Ave., Ware- Rt. 72 to Long Beach Blvd.,

town Harbor left onto long Beach Blvd., to 6th St. (Near end of Island & , y y Barnegat Light Tower), left i n onto 6th St. to Bayview Ave., $. 1 right onto Bayview Ave, and 8 %

across the street from the Q*

Coast Guard Station. qg e '

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[ UU (from OCNGS Main Gate & Rt. 9) g g _ gggg LOCATION DIRECTIONS REASON g -

5- n u sE ens l SSE1 -

152' O.75/ McGeorge's Restaurant 75 Right onto Rt. 9 to McGeorge's Closest h 1206.7 Restaurant. Individual E

o SSE2a 164a 1.6/ Waretown, Ocean Twp. Rinht onto Rt. 9, 1.6 mi.,

150 2574.4 Hunicipal Bldg. right onto Rt. 532, I block h g

bidq. on right. ;q

?

SSE2 SSE- 154* 1.55/ 300 Area east side of Main Right onto Rt. 9, 0.75 mi.,

2-1 2493.9 St. & south of Skip- E l

left onto Main St., 0.75 mi., 5 pers Blvd. to just past intersection with Skippers Blvd. Q n

SSE3 -

164a 2.65/ 450 Lagoon (BBCA Recrea- Right onto Rt. 9, 2.2 mi.,

4263.8 ton Area) near Bonita left onto Barnegat Beach Dr., $

Blvd. 0.6 mi., right on 1.agoon View g

Rd., lh blocks, to area on left next to lagoon.

SSE10 -

153o 8.3/ 1100 Intersection south Rinht onto Rt. 9, to inter- 0" 3" 13,354 Anchor St. with Harvey section of Rt. 72, lef t onto 2 S Cedars Water Stand Pipe Rt. 72 to intersection of Long I E Beach Blvd., left onto long "

rn2 Beach Blvd. to intersection of 5 32 West 80th St., left onto W. # 7-l 80th St. to intersection with C S. Anchor St. & Harvey Cedars i

Water Stand Pipe,

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3 (From OCNGS Main Gate & Rt. 9) g g g gggg LOCATION, DIRECTIONS REASON g -

! b' E N $5 OEiN S2 184* 1.6/

200 0.7 mi. west of Rt. 9 Right onto Rt. 9, right onto Closest 2574.4 on Rt. 532 Rt. 532 0.7 mi. Just beyond h resident y resident #172 and dirt lane, g

~

o S3 5-3 178* 2.3/ Haretown Substation

-1.

125 Rinht onto Rt. 9, 2.5 mi., E 3700.7 10 yards in from Rt. 9, pole p; No. R 144 Z, JC 83. Residence #

13 (Harman). v, "n

S3a -

Along Rt. 9 Waretown 182.5* 2.6/ 175 Right onto Rt. 9, 2.9 miles, h 4183.4 Junction pole fBT 1545 and 4 in. x 4 in "

timber with qas ofpeline leak- %

age tester attached.

Q

~

S4 176*

-e 3.2/ 350 Pebble Beach Water Right onto Rt. 9, 3.2 mi., "

5148.8 Tower left onto Senaca Blvd. to in-tersection of Eighth St. and Water Tower.

N N SS S5 187* 4.45/ 825 Roadside area, Barnegat_

Rinht onto Rt. 9, two traffic

< o

-l 7160.0 Service Pole #27 on 1 S lights to Rt. 554 (East Bay & E East Bay Ave. Ave.), left 0.5 mi. to Water "

m3 St. on rinht. ,8 }g S7 -

183* 6.3/ 500 End of Taylor Lane, liqhtontoRt.9,6.2mi., " ..

~

10,136 a t Ga te left onto Taylor La. (Dirt Rd.)

1.6 mi. to end of road at gate.

a y S10 -

186* 9.65/ Intersection of Bay 15,526 1450 Rinht onto Rt. 9 to Rt. 72, ;;; g Ave. & Rt. 180 access left on Rt. 72 for 2.5 mi., -

road turn left, go 0.2 mi. to in- "

tersection of Rt.180 g o,,

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UNE y (from OCNGS Main Gate & Rt. 9) 5- am W

$6 MEE wmbW h LOCATION DIRECTIONS REASON g U o~ uoo- 9 o

SSW2 -

210* 1,7/ 350 Intersection of Rt. Right onto Rt. 9 to right on 2735.5 532 & Laurelwyck Rd. Rt. 532 (Wells Mills Rd.), h 1.3 mi to entrance of devel- h opment on south side of road. g SSW4 -

205.Sa 3.45/ 325 End of Rose 11111 Blvd. Rinht onto Rt. 9, 4.4 mi. to 5551.0 at Cemetary rinht on Rose Hill Blvd., 1 9 mi, to cemetary. '~

e SSW5a -

210.5* 4.5/ 1150 Opposite G.S. Pkwy. Right onto Rt. 9, to 2nd traf-

o 7240.5 Maintenance Area on M

Rt. 554, east of G.S.

fic light. Right on Rt. d

' 554/534 (Bay Ave.) to Pkwy. o Pkwy. entrance area.

}

SSW5 -

193.5 4.35/ 1050 Union Township Hunici- Rinht onto Rt. 9, 4.8 mi., m 6999.1 pal Building right on Rt. 554/534 (Bay Ave.), 50 yds on right.

SSW7 -

925 Rt. 9 & Taylor Lane 397o 5.8/ Right onto Rt. 9, 6.2 mi., %' y 9332.2 left onto entrance of Taylor g Lane. }.

. a SSW10 S 5 199a 7.5/ 700 Southern Regional liiqh Right onto Rt. 9, 8.2 mi., g 32 12,067 Sc.hool riqht onto Parkino Lot north -

??

of buildings. ~

SSW -

10a 200* 9.0/ 600 Entrance to Atlantic Riqht onto Rt. 9, 10 mi. to 34*4g; City Electric Co. sub- paved entrance of substation station on Rt. 9 on left side of road. li? 8 i o <o SSW20 -

201 11.0/ -

175 Dinner Point Dr. Rinht onto Rt. 9, 11.9 mi. to w '"

17,699 Staffordville Staffordville, left onto U o Dinner Point Dr., 25 yds on S

lef t side of road "

3 2

O '

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m 0FFSITE MONITORING POINTS y g

[

g h.. $$ (from OCNGS Main Gate & Rt. 9) g gggp LOCATION DIRECTIONS REASON g -

5~ au u nE nas SW2 -

221* .1.8/

2896.2 o Ocean County Cemetary on Rt. 532 Right onto Rt'. 9 (to first traffic light), right onto Rt.

Covers closest l(

532 (Wells Hills Rd.), 1.75 resident [ ,

miles to cemetary. g

___ - r-o SW3 -

227.5 2.15/ 450 Intersection of Rt. 532 Rinht onto Rt. 9, right onto 3459.3 & G.S. Pkwy. Rt. 53? (Wells Hills Rd.) to kp intersection with G.S. Pkwy. ,

SW4 SW-4-1 219* 3.45/

5551.0 650 Barnegat Toll Booth on G.S. Pkwy. 110 AC Right onto Rt. 9, right onto Rt. 532 (Wells Hills Rd.) to (m

G.S. Pkwy. south. Right side q of road just beyond toll hooth. .]

m SW5 -

217* 4.5/ 1350 Parking area between Right onto Rt. 9, to 2nd 7240.5 First A Second Sts. traffic liqht. Right onto west of G.S. Pkwy. Rt. 554 to first right after exit ramn, 110 AC G.S. Pkwy. exit (First St.)

{ j SW7 InterseItlonofKeadow 8 Riqht onto Rt. 9, right onto 228.5* 7.2/ 85o g @

. -11.584 Rd. A Rt. 72 at Fawn Rt. 532 (Wells Hills Rd.) to 3 mg Lakes. G.S. Pkwy. south, South to Exit 63N, take Rt. 72N for s .3 2 2.4 ml. to Meadow Road

?.

C SW10 -

229' 8.9/ 1025 Intersection of llay Rd. Riqht onto Rt. 9. right onto 14,320 & Hicaja's Rd. Rt. 532 to G.S. Pkwy., south NOTE: unimproved dirt to Rt. 72 exit 63N, north on f 8 road Rt. 72, 100 yds, to Recovery E S Rd. Left 5.1 mi. on Recovery -

Rd. , hearing right at landfill to intersection. m 7*

t N E$

0 3

f R OFFSITE MONITORING P0ltal'. p z cr A. ~~

E I UsG 30 7 (Frnm OCNGS Main Gate & Rt. 9)

S o! W E EUE EUUU LOCATION DIRECTIONS REASON g N W ,5 M Mdy M"CU

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SW20 -

214.5* 13.2/ 3650 Intert,ection of Rt. Right onto Rt. 9 right onto 0

21,238 539 & G.S. Pkwy.

O Rt. 532 to G.S. Pkwy. Take Pkwy. south to Exit #58 g o

(Tuckerton) and make right ont o a Rt. 539. Park along right sidt G of road. S o

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[ 5 hd h h (From OCNGS Main Gate & Rt. 9) g h

$ $ g3w gggg LOCATION OIRECTIONS REASON g -

E- Eu W $Eh o-wwbW uoo-gc, WSW1 -

249* 0.3/

482.7 0 Southwest corner of 0.C. Substation, 110 Right onto Rt. 9, over dis-charge canal bridge, right on k-<

AC South Access Road to Substa- @

tion o 8

WSW2 -

247.5* 1.55/ 75 G.S. Pkwy. Picnic Area left onto Rt. 9, left on Rt. $

2493.9 614 (Lacey Rd.) to G.S. Pkwy. Q Take Pkwy north to Forked River r-service area on left. Make U- g Turn and go south into picnic 3 area on lef t at mile marker Q 71.5 "

o WSW3 -

240 2.5/ 425 Ocean County Vocational South on Rt. 9, rioht on Rt. 3 4022.5 School 532, 0.6 mi. beyond G.S. Pkwy.

on left. ]

WSW4 WSW- 251.5* 3.75/ 400 Intersection of Rt. 532 South on Rt. 9 right onto Rt.

4-1 6033.7 & Bryant Rd. 532. continue 4.4 mi. to dirt u u r'oad on right (Bryant Rd.) 7 S

.just before steel quard rail d>

k c

WSW5 -

255* 4.35/ 1000 Intersection of Rt. 532 Riqht on Rt. 9. right onto .. Q

6999.1 & dirt road Rt. 532, continue 4.85 mi. to 3 dirt rnad on right. ~

WSW6 -

254* 5.3/ 1200 Junction Rt. 532 & Rt. Riqht on Rt. 9, rinht onto Rt.

8527.7 611 (Brookville Rd.) 532, 6 mi. to junction of Rt.

opposite Southern Ocean 611 (Brookville Rd.) on left g u Landfill entrance opposite Landfill entrance. g g g To WSW10 -

252* 7.5/ 750 Intersection of Rt. 532 Riqht onto Rt. 9. right onto t

& Rt. 72 9' 12.067 Rt. 532 to intersection of Rt. 0 72 (Darneoat Rd.) (j U

^ x f-.

OFFSliE HONITORING P0lHI$ p c m -

gnr 585-g t; p

. i

. m (From ocur.S Main Gate & Rt. 9) p g 5 $ ;sujw wggy LOCATION DIRECTIONS REASON d -

5- au e SEh o~

EmbW voo- 8 ti WSW20 -

243' 11.45/ 1300 End of Rt. 608 (Sim Right onto Rt. 9, right onto 18,423 Place Rd.) at gate Rt. 532. At inter.section of g Rt. 532 A Rt. 72 and Rt. 610 ,b go straight on Rt. 610 to 0 intersection of Rt. 539, turn h left, 1 mi. to Rt. 608, stop M at end of road (Mr. Simm's) @

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OFFSITE HONITORING POINTS y

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] s $[ [] (From OCNGS Main Gate & Rt. 9) k g y $ p_

gggg LOCATION DIRECTIONS REASON g -

-- au u EE edE R W2 -

270* 1.25/ G.S. Pkwy. left side 2011.2 75 Lef t on Rt. 9 to 2nd traffic Covers y grass area at mile light, left on Rt. 614 (Lacey closest ,

marker 71.8 Rd.) to G.S. Pkwy. north to resident at >

service area, turn south on 2.9 mi (no 3 Pkwy. to mile marker 71.8. trespassfaq) h o i W2a W-2 269* 1.3/ 75 G.S. Pkwy.. picnic area Rt. 9 south to Rt. 532 west NJ O

-1 2091.7 at mile Marker 71.2 to C.S. Pkwy. North. Go about Location "

1.5 mi. to picnic area on left E E

m W7 -

259* 6.7/ 1900 0.6 mi. north of Rt. Right on Rt. 9, to ist traffic *5 10.780 532 on Jones Rd. light (Rt. 532), right on Rt. 'o 532 through intersection with 7 Rt. 611 (Brookville Rd.) 1.2 U mi. to dirt access road on M rinht (Jones Rd.), continue 0.6 mi. to fork.

W10 -

260a 9.15/ Intersection of Rt. 72 14,722 1850 Rinht on Rt. 9 to 2nd traffic E Y (Darnegat Rd.) & Rt. light, right on Rt. 554 (west) i N l

539 (Warren Grove to Rt. 72 west (Rarnegat Rd). I E Whitino Rd.) to intersection with Rt. 539 3 5 (i.'arren Grove Whiting Rd.). g 3[

'O O W20 -

276* 14.0/ 2525 Intersection of Rt. 72 Right on Rt. 9 to 2nd traffic 22,526 C (Darneoat Rd.) & Rt. light, right on Rt. 554/534 532 (west) to Rt. 72 west (Barne-nat Rd.). 7.6 miles to left fork junction with Rt. 532. hf f

.. o

___ ___...____..___- = +

H20a W-20 - - -

Lebanon State Forest _ (Off man) PL1 g

-1 ,

110 AC Location 2 0 2

tJ as a

( *^ h .

OFFSITE MONITORING POINTS g' -

a

- x w - Eod- -7

. m $ WMy durp (Trnm DCNGS Main Gate & Rt. 9) n,

$ Q E ;5 **j ' Wggy LOCATION DIRECTIONS REASON rp -

5. 2M M M o~

E h5mbM uoo- 9, c

WNW1 -

284* 0.6/ 100 Forked River Het Tower Lef t onto Rt. 9, first dirt k*

965.4 road on lef t after end of owner control fencing beyond C intake canal bridge, west on 2 dirt road to first left, curve @

l right, then second left to next 8 l -

left, to met tower. R

<- l HHW2 -

291* 1.35/ 50 G.S. Pkwy., mile Lef t on Rt. 9 to 2nd traffic p 2172.1 marker 72.4 at Emer- light, left on Rt. 614 (Lacey y gency Turnaround Rd.) to G.S. Pkwy. north to Q Service Area, turn south on m Pkwy. to mile marker 72.4 o

- _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ . _ _ _ . 3 WNW10 -

285* 9.7/ 2000 Rt. 539 (Warren Grove Rinht on Rt. 9 to 2nd traffic 7 15,607 Whiting Rd) where it light, right on Rt. 554 (west)

crosses over Chamber- to Rt. 72 (Barnegat Rd) to lain Brook right on Rt. 539 (Warren Grove Whitino Rd), 3.6 mi to Cham-herlain Brook. 4' -"

-- _ -= - - - - __ - - - - _ . . - - - - . - .

1 8 7

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% LOCATION (From OCNGS Main Gate & Rt. 9)

DIRECTIONS REASON k -

5- am u sE ens g= +

In12 -

322.So 1.7/ G.S. Pkwy. mile :

2735.5 300 Left on Rt. 9 to 2nd traffic Q 1

marker 73.0 Itoht, lef t on Tr. 614 (La-cey Rd) to G.S. Pkwy north to k Service Area, turn south on B Pkwv. to mile marker 73.0 5 '

fM6 322* 5.95/ Rt. 614 (Lacey Rd.)

900 Left on Rt. 9 to 2nd traffic h 9573.5 0.1 mi. down dirt Rd., light, lef t on Rt. 614 (La- !

(west of Cranberry cey Rd) to mile marker 7 (3.2 y,

g, !

Boq) mi. west of G.S. Pkwy), dirt .

g l access road on left after if, mile marker 7. ,

4 vs NW10 -

314' 8.7/ 200 Intersection of Rt. 614 Lef t on Rt. 9 to 2nd traffic 13,998 (Lacey Rd) and Good lioht. lef t on Rt. 614 (Lacey h r Luck Rd. Rd.) to mile marker 5. (5.3 mi. west of G.S. Pkwy) at Good Luck Rd. intersection, u u fM10a 7 3 i Fwd 315 7.9/ 75 Bamber Lake Fire Sta- Lef t on Rt. 9 to 2nd traffic

- a ;

NJ 1

EOC 12,711 'a.,

tion on 614 (Whiting Itoht, lef t on Rt. 614 (Lacey location VAN Lacey Rd) location of g y Rd) to Bamber Lake Fire Sta- q 'n IU State RRP Fwd. E0C tion on right (6.1 mi. west _.

Van of G.S. Pkwv. " .6 *;; *g fM20 -

317 13.3/ Town of _Whitino, junc-825 Lef t on Rt. 9 to 2nd traffic 21,399 tion at RR tracks and If aht, lef t on Rt. 614 (Lacey Whitinq-Lacey Rd. Rd), past Bamber Lake to town o u of Whitino (RR tracks). N $

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^ x OFFSITE MONITORING POINTS ,

L

' Aae$. E k UO $3 3

. [ (From OCNGS Main Gate & Rt. 9) g g 3 -

ggg LOCATION DIRECTIONS REASON g -

5 =. 2 I7i E g5 gy$

NfM3 -

340* 2.7N 125 Access road to median, lef t on Rt. 9 to 2nd traffic ili 4424.7 G.S. Pkwy. mile marker light, left on Rt. 614 (Lacey

74.4 Rd) to G.S. Pkwy, north to E service area (h m!.) on left. E enter service area, turn soutt 8 on Pkwy to mile marker 74.4 or 8 :

left side, left into access rd .

NfM4 348* 3.5/. Intersection of Rt. Lef t onto Rt. 9, lef t at 2nd 975 E 5631.5 614 (Lacey Rd) & G.S. traffic light on Rt. 614 (Lacey Pkwy. Q -

Rd) to intersection with G.S. Q I Pkwy. m ,

o NNWS -

331 4.65/ Roadside at Pole ] :

7481.8 850 Lef t onto Rt. 9. lef t at 2nd "'

BT4112 at Rt. 614 traffic light onto Rt. 614 (Lacey Rd) at Deep (Lacey Rd) (1.7 mi. west of M Hollow Creek (inter- G.S. Pkwy) Just past speed mittantstream) limit 50 sian.

NNil10 -

339' 7.9/ Just beqore intersec-g u 400 Lef t onto Rt. 9, lef t at Rt.

12,711 tion of Pinewald-Kes- 618 (Central Pkwy. Opposite 1 8 wick Rd. & Rt. 530 1 R Butler Blvd.) to Rt. 530 g q (Dover Rd) on right (Dover Rd.). gm O -* :4 NNW20 -

342* 12.55/ 2700 Intersection of Rt. 37 Lef t onto Rt. 9, lef t at 2nd 20,192 L'

& Northampton Blvd. traffic lioht onto Rt. 614 "

(Lacey Rd) to G.S. Pkwy.,

north to Exit 82, west on Rt.

37, 3.75 mi. from Pkwy. exit, o u turn right to offstreet park-

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o EPIP-11

. Rev. 1 3/4/82 ATTACHMENT 2 page 1 of 2 OFFSITE MONITORING CHECKLIST DATE / /

?

ACTION Reference Time / Initials

1. Obtain copy of EPIP 11, Initiate '

Attachment 2. 4.2

/

2. Obtain key to vehicle and instrumentation 4.1

, /

3. Verify that monitoring kit is locked (sealed) 4.3 /

4. Don TLD and self-reading dosimeter. 4.3 /

5. Inventory monitoring kit (If applicable) 4.3 /

6. Operationally check survey instruments 4.4 /

6.1 Scaler SAT UNSAT 4.4 6.2 Count Rate Meter SAT UNSAT 4.4 6.3 Dose Rate Meter SAT UNSAT 4.4 i 7. Operationally check air sampler and power supply SAT UNSAT 4.5 /

8. Perform radio check and equipment status l transmission to EAC 4.6 /

9. Ensure that dose rate meter is contin-uously ' operating 4.6 /

10. Proceed to offsite monitoring locations and perform radiological surveys as dir-acted by EAC. 4.7 10.1 Obtain dose rate survey for all lo-cations specified by the EAC and record on Attachment 3. 4.8.1 10.2 Obtain air sample and analyze with

! scalar for all locations specified by the EAC. Retain particulate fil-ter and silver zealite cartridge and record data on Attachment 3. 4.8.2 '

10.3 Obtain smear survey for all lo-cations specified by the EAC and record on Attachment 4. 4.8.3 Retain smears .

ATTACHMENT 2 l .

l \~

1

EPIP-11 Rev. 1 3/4/82 Page 2 of 2 l

ACTION Reference Time / Initials 10.4 Obtain biotic media - samples 4.8.4-6 !

for all locations specified by the EAC and record on Attach-ment 4.

11. Upon direction of the EAC, return Forked River Site, Checking Vehicle Fuel Level, Generator Fuel level and perform a com-plete inventory of the emergency mon-itoring kit.

Vehicle Fuel level 5.2 Generator Fuel level Inventory completed /

12. Submit Vehicle, Inventory Checklists and Attachments 2, 3, and 4 to EAC 5.3 /

13. Return TLD to Dosimetry 5.4 /

Reviewed by EAC / /

Signature Time Date Attachmeitt 2 e

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/

s ATTACHMENT 4 EPIP-Il w3/4/82 CONTAMINATION AND DIOTIs sEDIA SURVEY W Rev. 1 .agg 1 of 1 e

DATE: / /

SURVEY TEAM MEMBERS 1. 2.

1. SMEAR SURVEY ,

Monit. Gross BKG Net DPM Init. Monit. Gross BKG Net DPH Init.

Location Time CPM CPM CPM / LOO CM2 100 CH2 Loct. Lion Time CPM CPM CPM / LOO CM2 IOOCM2

1. . . . _ . __ .

11.

2- - -

12.

3 __ - - .- -

13.

4 . . . .. . - _ _ _ _ _ _ 14,

5. 15.

6. 16.

7. 17.

8. 18. ._ .

9_ 19.

10. 20.

2. BIOTIC MEDIA SURVEY - SOIL, WATER, VEGETATION

. l Monitoring Type of Dose Rate Monitoring Type of Dose Rate Location Sample Time mR/hr Initials Location Sample Time mR/hr Initials

1. 11.

2. 12.

3. 13.

4. 14.

5. 15.

6. 16. -

7. 17.

8, 1 18.

9.. 19.

10. 20.

INSTRUMENT MODEL SERI AL NO. CALIBRATION DATE

1. Count Rate Meter

2. Dose Rate Meter l

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ATTACllMENT 4

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Procecure No.

_It' D R.B JRENE EPIP - 13 Page 1 Of s Date issued Effective Date Jersey Central 2/17es2 3,3,s:_3,19,s:

/ Power & Light Compar1y Revision No. Cate

Subject:

Site Evacuation and Personnel ^

Accoun bility After Site Evacuation D rSu h omn h Appro hl/plyfu p , _ _ . _ _ . . _

n J.j /aJTQ4uu.jf.

Proje c) oyster Cree uclear Generating Station LIST OF EFFECTIVE PAGES DATE REVISION NUMBER 1 2/17/82 1 2 , 2/17/82 1 3 2/17/82 1 4 2/17/82 1 5 2/17/82 1 6 2/17/82 1 7 2/17/82 1 8 2/17/82 1 ATTAC1HENTS

1. Site Evacuation Ordered, Personnel Accountability Not

( Previously Ordered (8 pages) 2/17/82 1

2. Site Evacuation Ordered, Personnel Accountability Previously Ordered, Not Completed (8 pages) 2/17/82 1

3. Site Evacuation Ordered, Personnel Accountability Completed (3 pages) 2/17/82 1

4. Site Evacuation Instruction Sheet / Evacuation Route Maps (2 pages ) 2/17/82 1 NON-CONTROLLED This Document Will Not Be Kept t Up To Date

4 0b Senatect: P*ciscwo Na Sita Evacuttion 4 Parsonnal g.3g 3 2 3f 6 teq:s EPIP-13 Accountability After Site Evacuation ya a ,,3,an : ate

/ 7/62 7

DATE 1.0 PURPOSE This procedure provides instructions for the orderly evacuatien or personnel from the Oyster Creek Nuclear Generating Station protected area to the Remote Emergency Assembly Area (Berkeley Operating heaoquarters).

Additionally, described are the accountability requirements associated with a site evacuation. Site evacuation can occur witn accountability, not previously ordered, in progress, or completed.

2.0 DOCUMENTATION TIME /1hl11ALS 2.1 Emergency Director's Documentation Sheet 2.1.1 Site Evacuation Ordered /

2.1.2 Security Notified of Evacuation and route to Use (North or South) /

2.1.3 Site Evacuation Alarm Sounded; 7

i Personnel in Protected Area

notified /

2.1.4 Remote Assembly Area Activation Order (EPIP-18 ) /

2.1.5 Radiological Controls Technician assigned to Remote Assembly Area /

2.1.6 Main Gate Processing Center Habitability Check Performed /

2.1.7 Emergency Assembly Area Habitability Check Performed /

2.1.8 Initiate Search and Rescue (EPIP-22) (as applicable) /

2.1.9 Site Accountability Complete /

2.1.10 Site Evacuation Complete /

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a+a Suntect: Prococuro No, Site Evacuation & Personnel EPIP-13 page 3 of 8 8cces Accountability Af ter Site Evacuation q ,,,,, an ya Cate 2 /17/8 2 a

e DATE 2.2 Control Room Documentation Sheet TIME / INITIALS 2.2.1 Notify security that site evacuation has been ordered.

Te lephone 6954, 6950. Personnel accountability required. /

2.2.2 Notify personnel in protected area that a site evacuation has been ordered. /

2.2.3 Muster members of the Operating Shif t and members of senior plant management present in the Control Room by Security Badge slot number. /

2.2.4 Muster list (by Security Badge slot number) submitted to Site Protection Sergeant. /

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.D Seiect: Receture No, 8 5488 Site Evacuation & Personnel EPIP-13 *sco 4 sf 8 Accountability Af ter Site Evacuation , , , , , , , , ya 7,,,

2/l7/82

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DATE 2.3 Technical Support Center Documentation Sheet TIME / INITI ALS 2.3.1 Personnel present in Technical Support Center mustered by Security Badge slot number. /

2.3.2 Muster list submitted to Site Protection Sergeant /

2.4' Operations Support Center Documentation Shee t 2.4.1 Personnel present in Operations Support Center mustered by Security Badge slot number. /

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2.4.2 Emergency teams not present in Operations Support Center mustered by Security Badge slot number. /

2.4.3 Muster list submitted to Site Pro-tection Sergeant. /

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Site Evacu: tion & Parsonnal EPIP-13 F198 5 3' R 'SG'8 Accountability Af ter Site Evacuation q,,,,,,, yg ;,,,

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DATE 2.5 Security Department Documentation Sheet TIME / INITIALS 2.5.1 Verify that site evacuation has been ordered and which route to be used.

(Check one) North South . /

2.5.2 Remote Assembly Area Activated

( EP IP-18 ) /

2.5.3 Notify personnel at Oyster Creek Nuclear Generating Station outside the protected area not elsewhere notified that site evacuation ordered /

2.5.4 Notify Oyster Creek Nuclear Generating Station, Training Annex, Telephone 6905, 6906 that ' site evacuation ord ere d . /

2.5.5 Notify Forked River Security Department

/

Telephone (609) 693-7703, (609) 971-4359 that site evacuation ordered. /

2.5.6 . Cates 8 and 18 Open. /

2.5.7 Open door 131-D (if personnel accountability ordered prior to site evacuation). /

2.5.8 North Gate Processing Center, Main Cate Processing Center, and (if reg.' edi Emergency Assembly Area Site Protectic ' Officers instructed to give each person leaving the protected area a departure lastruction sheet and evacuation route map (Attachment 4). /

2.5.9 Site Accountability Status Determined, Emergency Director Notified. /

2.5.10 Adjacent Areas mustered. /

2.5.11 Radiological _ Protection Coordinator Contacted for Disposition of Collected Do simetry . /

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I' Sveiect: Procecure No.

l Site Evacuation & Personnel EP1P-13 714e a :f g acqss Acco,untability After Site Evacuation hvision N o. Ocre , ,

1 ./17/64 J

3.0 ACTION LEVEL REFERENCES 3.1 EPIP-2 Unusual Event 3.2 EPIP-3 Alert 3.3 EPIP-4 Site Emergency 3.4 EPIP-5 Ceneral Emergency 4.0 PRECAUTIONS 4.1 Not applicable to this procedure.

5.0 PROCEDURE 5.1 Initiating Conditions Site evacuation may be initiated in the Unusual Event, Alert or Site Emergency conditions or by any initiating events within these classifications. Site evacuation will be orcered in the event a General Emergency is declared.

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5.2 Responsibility The Emergency Director is responsible to evaluate conditions wnten could require site evacuation and to implement the appropriate Emergency Plan Implementing Procedures.

5.3 Remote Assembly Area Location 5.3.1 Berkeley Operating Headquarters O

Svatect: Procxure No.

Sito Evscustion & Parsonnel EPIP-13 FcG) 7 of 8 ocqes Accountability After Site Evacuation I 1 2/17/82 s

5.4 Emergency Director's Notifications The Emergency Director will ensure that each of the following are notified that a site evacuation is ordered:

5.4.1 Security, Telephone 6954, 6950 5.5.1.1 Oyster Creek Nuclear Generating St atio n Se curi ty De pa rt ment proceed in accordance with paragraphs 5.5 and 5.6 of this procedure.

5.4.2 Personnel in the Protected Area 5.4.2.1 Sound site evacuation alarm, approximately 10 seconds.

5.4.2.2 Announcement -

Make the following annsancement on the Public Address System, as appropriate:

Site Evacuation, Accountability not previously o rd e red .

( ATTENTION ALL PERSONNEL: A SITE EVACUATION IS ORDERED. ALL PERSONNEL WHO DO NOT HAVE SPECIFIC EMERGENCY ASSIGNME NTS SHALL LEAVE THE SITE THROUGH EITHER THE NORTH GATE PROCESSING CENTER, OR THE MAIN GATE PROCES SING CENTER. PROCEED TO THE REMOTE ASSEMBLY AREA AT THE BERKELEY OPERATING HEADQUARTERS.

Site Evacuation, Accountability previously ordered.

ATTENTION ALL PERSONNEL: A SITE EVACUATION IS ORDERED. ALL PERSONNEL WHO DO NOT HAVE SPECIFIC EMERGENCY ASSIGNME NTS SHALL LEAVE THE SITE THROUGH EITHER THE NORTH GATE PROCES SING CENTER OR THE MAIN GATE PROCES SING CENTER. PERSONNEL IN THE EMERGENCY ASSEMBLY AREA DEPART THE SITE AS DIRECTED BY SECURITY PERSONNEL. PROCEED TO THE REMOTE ASSEMBLY AREA AT THE BERKELEY OPERATING HEADQUARTERS.

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Suetect: Proceture No.

8 5G'3 Site Evacuation & Personnel EPIP-13 FS93 8 8f 8 1 Accountability Af ter Site Evacuation q ,,, ,,, n y a, 3,,,

1 2/17/82 1

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1 5.4.2.3 Alarm -

Sound site evacuation alarm, '

approximately 10 seconds.

5.4.2.4 Repeat the announcement.

5.4.2.5 Alarm - Sound site evacuation alarm for approximately 15 minutes. Deact ivate the alarm when ordered by the Emergency Dire c t o r. l 5.5 Site Evacuation / Accountability Methods 5.5.1 Site Evacuation Ordered, PERSONNEL ACCOUNTABILITY NOT ;

PREVIOUSLY ORDERED. 1 5.5.1.1 Detailed method contained in Attachment 1.

5.5.2 Site Evacuation Ordered, PERSONNEL ACCOUNTABILITY PREVIOUSLY ORDERED, NOT COMPLETED.

5.5.2.1 Detailed method contained in Attachment 2.

5.5.3 Site Evacuation Ordered, PERSONNEL ACCOUNTABILITY COMPLETED.

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5.5.3.1 Detailed method contained in Attachment 3. -

5.6 Activation of the Remote Assembly Area l The Site Protection Sergeant will ensure the Berkeley Operating Headquarters is activated in accordance with EPIP-18.

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PMeecure NL Site Evccuttion & Parsonn11 EPIP-13 UO 1 0' a N" Accountability After Site Evacuation Revision N o. Oate 1 2/17/82 J e ATTACHMENI 1 SITE EVACUATION ORDERED, PERSONNEL ACCOUNTABILITY NOT PREVIOUSLY ORDERED 1.0 VERIFICATION The Oyster Creek Nuclear Generating Station Site Protection Sergeant will verify that a site evacuation has been ordered by the Emergency Director and the evacuation route to be used (North or South).

2.0 SITE EVACUATION METHOD After the site evacuation message has been verified, the Oyster Creek Nuclear Generating Station Site Protection Se rgeant will ensure e,ach of the following are notified that a site evacuation is ordered; muster and report required.

2.1 Personnel at Oyster Creek Nuclear Generating Station located outside of the protected area and within the area defined on the north and south by the canal, the east by the security fe'ic e west of Route 9, and on the west by the switch yard security fence. .

( .

?. 2 Oyster Creek Nuclear Generating Station, Training Annex, Building #24. Telephone 6905 6906.

2.2.1 Ihe Supervisor Support Program Training or his designee is responsible to ensure that all persons in the Oyster Creek Nuclear Generating Training Annex area are mustered, and the results of the muster forwarded to the Site Protection Sergeant, Telephone 6954 6950.

2.2.1.1 This activity is occupied during normal work hours (Monday throu gh Friday). If telephone communications cannot be established, the Site Protection Sergeant is responsible to ensure that the Training Annex is not occupied.

2.3 Forked River Construction Site Security Department, Telephone (609) 693-7703, (609; 971-4359.

2.3.1 The Forked River Security Department will request each of the following activities submit a muster list of personnel present to the Forked River Security Department.

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Mpet: Pen cura Na Site Evacuation & Personnel EPIP-13 * '#

Accountability After Site Evacuation 4evision N o. Oofe 1 2/17/82 s

ATTACHMENT 1 2.3.1.1 Forked River Construction Site.

2.3.1.2 The Energy Spectrum, Telephone (609) 971-4931/4932 2.3.1.3 Oyster Creek Nuclear Generating Station Activities located in Building #12 and Building #1 at Forked Rive r.

2.3.2 Upon completion of the muster, notify the Oyster Creek Nuclear Generating Station Security Department that the muster is complete, Telephone 6954, 6950. The muster list should be forwarded to the Oyster Creek Nuclear Generating Station Site Protection Sergeant within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.4 The Site Protection Sergeant will ensure that Gates 8 and 18 are opened immediately af ter site evacuation is ordered.

2.5 Personnel departing the Oyster Creek Nuclear Generating Station protection area will exit through either the Main Gate Processing or the North Gate Processing Center. Each

[

person leaving the are's is responsible to:

2.5.1 Turn-in to the Site Protection Officer assigned to the exit area (s) their dosimeters and TLD's for future collection, processing, and dose assessment.

2.5.2 Turn in Oyster Creek Nuclear Generating Station security badge to the Site Protection Officer assigned to the exit area (s).

2.5.3 Obtain departure instruction sheet / evacuation route map (Attachment 4) from Site Protection Officer assigned to the exit area (s).

2.5.4 Evacuate from ' Oyster Creek Nuclear Generating Station to the Remote Assembly Area in automobiles containing no less than 4 persons.

2.5.5 Follow the prescribed route (North or South) to the Remote Assembly Area.

2.6 The Site Protection Sergeant will ensure that persons departing the Oyster Creek Nuclear Generating Station protected area:

2.6.1 Turn-in their individually issued dosimetry.

5 2.6.2 Turn in their Oyster Creek Nuclear Generating Station security badge.

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, Suotect: Pmeaurs %

Sito Evccu'; tion & Parsonn21 EPIP-13 % 3 3f a I Cs Accountability After Site Evacuation l 7 ATTACHMENT 1 2.6.3 Are issued departure instruction sheet / evacuation route map (Attachment 4) with instruction for tne proper route to use.

I I 2.7 Pe rsonnel who evacuate the site shall proceea directly ano expeditiously to the Remote Assembly Area following the designated route and shall wait there for further processing.

2.8 As personnel arrive at the Remote Assembly Area, they shall be logged in by the Site Protection Of ficer(s) assigneo.

2.9 Personnel shall be surveyed for contamination by a member ot Radiological Controls. Skin contamination levels wnich exceed 100, cpm above background will require decontamination in accordance with EPIP-21. (The vehicle of a contaminateo individual must be surveyed and decontaminated if necessary).

2.10 Further disposition of personnel will depend upon the nature of the emergency and anticipated personnel needs for recovery operations.

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2.11 The Site Protection sergeaht will contact the Radiaological Protection Coordinator for disposition of collected dosimetry.

3.0 SITE ACCOUNTABILITY METHOD .

3.1 The Site Protection Sergeant is responsible to ensure tnat site accountability status is determined within 30 minutes af ter site evacuation is ordered.

3.2 The Site Protection Sergeant will ensure that onsite Oyster Creek Nuclear Ge ne rating Station Security Department personnel are accounted for utilizing a security badge slot number listing.

3.3 The Site Protection Sergeant will ensure that the Main Gate Processing Center and the North Gate Processing Center meet minimum personnel habitability requirements (less than 50 mrem / hour ) . If the Processing Centers do not meet these requirements, the Radiological Controls Coord inator will ensure that a habitable area is designated for use by the Oyster Creek Nuclear Generating Station Security Department.

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Swoiect: P.oc x ura u Sito Evccuttion & Parsonnal EPIP-13 NG) 4 af R Nos Accouatability After Site Evacuation g,, g 3,,

s ATTACHMENT 1 3.4 Security badge storage drawers and collected security badges and dosimetry at the North Gate Processing Cente r will be transferred to the Main Cate Processing Center when directed by the Site Protection Sergeant.

3.4.1 Should the Main Gate Processing Center not meet habitability requirements, collected Oyster Cree k Nuclear Generating Station security badges, Dosimetry and active security badge storage drawers at both locations, will be taken to an area designated by the Radiological Controls Coordinator.

3.5 The Site Protection Sergeant will designate Site Protection Officers (as necessary) to place the collected Oyster Creek Nuclear Generating Station security badges with dosimetry attached into the appropriate slots in the storage drawers.

These officers will inventory each security badge storage drawer and compile a list of the badges not in the storage drawers by security badge slot number. This list will be delivered to the Site Protection Sergeant, when completed.

3.6 Personnel assigned to the following areas Control Room Technical Support Cent e r Operations Support Cente r shall be accounted for in the following manner:

3.6.1 Control Room -

The Group Shift Supervisor shall ensure that all members of the operating shift are mustered by security bedge slot number.

Additionally, members of senior plant management present in the Control Room will be mustered by security badge slot number. A composite listing of the security badge slot numbers shall be submitted to the Site Protection Sergeant within 10 minutes of site evacuation being ordered by the Emergency Director.

3.6.2 Te chnical Support Cente r (if activated) -

The Technical Support Coordinator shall ensure that all personnel present in the Technical Support Center are mustered by security badge slot number. A listing of security badge slot numbers shall be submitted to the Site Protection Sergeant within 10 minutes of site s evacuation being ordered by the Emergency Director.

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Site Evccur. tion G Parsonnel EPIP-13 h43 5 2' R 44" Accountability Af ter Site Evacuation g,,,,n g g, 1 2/17/82 s

ATTACHMENT 1 3.6.3 Operations Support ' Center (if activated) -

The Operations Support Coo rdinator shall ensure that all personnel present in the Operations Support Center are mustered by security badge slot number. Additionally, emergency teams dispatched from the Operations Support Center shall also be mustered by security badge slot number. A composite listing of the security badge slot numbers shall be submitted to tne Site Protection Sergeant within 10 minutes of site evacuation being ordered by the Emergency Director. .

3.7 Ihe Site Protection Sergeant will collate accountability reports from the Control Room, the Technical Support Ce n t e r , the Operations Support Ce n t e r , and Security Department. Ihis collated listing of security badge slot numbers will be compared to the list of security badge slot numbers derived from the security badge storage drawer inventory.

3.8 Results of this comparison, may result in any condition listed below or a combination of Conditions 2 and 3.

3.8.1 Condition 1 - All Personnel Accounted For

( 3.8.1.1 All security badge slot numbers on the security badge storage d rawe .- inventory list correspond with tne security badge slot numbers on the collated listing.

NOTE: Required Action: Site Protection Sergeant - Notify the Emergency Director that all personnel in the protected area have been accounted for, and accountability is completed. -

3.8.2 Condition 2 - Missing Person (s) 3.8.2.1 Securi ty badge slot number (s) appear on the security badge storage drawer inventory list, but not on the collated listing.

NOTE: Required Action: Page the missing person (s) using the Public Address System. Missing persons who do not respond in 2 minutes:

Attempt to contact the person (s) by telephone at home (if the telephone number can

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be obtained).

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Swepen Pucyrura No.

Site Evccustion & Parsonnal EPIP-13 FSO 6 af 8 'S4" Accountability After Site Evacuation Revision N o. ore 1 2/17/82

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AITAClEENT 1 Attempt to contact the person (s) by tele phone-4 t-the -

Remote Emergency Assembly Area at the Jersey Central Power &

Light Berkeley Operating Headquarters, Telephone (201) 244-4728/4726.

If all person (s) listed in Condition 2 above respond to the page or telephone

- calls, the Site Protection Sergeant will notify the Emergency Director that all pe rs'ons are accounted for in the protected area, and accountability is completed.

If any of the person (s) in Condition 2 above do not respond to the page or telephone calls, the Site Protection Sergeant will notify the Emergency Director that accountability is completed, and provide the name(s) and

( security badge slot numbers of mi.ssing person (s).

The Emergency Dire c to r will ,

initiate Search & Rescue Operations (EPIP-22).

3.8.3 Condition 3 - System Error 3.8.3.1 Security 5adge slot numbers appearing on the collated listing, but not on the Emergency Assembly Area list. -

NOTE: Required Action: Determine the sou rce of the error (Examples:

Security badge filed in the wrong slot in storage drawer; incorrect security badge slot number recorded on Emergency Assembly Area list or collated listing).

Discrepancies will be resolved by the Site Protection Sergeant or his designee. Upon resolution, the Site Protection Se rgeant will notify the Emergency Director that all persons are accounted for in

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the protected area, and accountability is completed.

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Se p Proceaura No.

Site Evccustion & Parsonn21 EPIP-13 ISC) 7 8f 8 '54'8 Accountability Atter Site Evacuation q ,,,,, g ;,,,

s ATTAClEiENT 1 3.8.4 Condition 4 - Combination of Conditions 2 and 3 3.8.4.1 Required Action: The Site Protection Sergeant or his designee shall perform the required actions listed in Conditions 2 and 3 of this section.

3.9 Alternate Accountability Method 3.9.1 A DIGITAL Computer System is normally used to account for persons in the protected area at Oyster Creek Nuclear Generating Station. Should site evacuation be ordered and this accountability system be available for use, a listing of all personnel within the protected area can be obtained from the computer system at the Central Alarm Station. .

3.9.2 A muster will be conducted by security badge slot number in each of the following areas:

Control Room

( Technical Support Center

. Operations Support Center .

Oyster Creek Nuclear Generating Station Security Department in accordance with the provisions of paragraphs 3.2 and ;

3.5 of this attachment. I 1

3.9.3 The Site Protection Of ficer(s) assigned to the Remote I Emergency Assembly Area will muster all persons there ;

by security badge slot number. This listing will be conveyed immediately, upon completion, to the Site Protection Sergeant.

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l 3.9.4 The Sito Protection Sergeant is responsible to ensure that the listings of those mustered are compared to the computer listing in order to determine the site personnel accountability status.

3.9.5 All Personnel Accounted For - The Site Protection Sergeant wil1 notify the Emergency Director that all persons in the protected area are accounted for and site accountability is complete.

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14'8 Site Evacuation ' Parsonnal EPIP-13 ES43 A Sf 8 Accountability After Site Evacuation q ,,, , , ,3 y o, 3,,,

e ATTACHMENI 1 3.9.6 All Personnel Not Accounted For - Page the missing person (s) using the Public Address System. Missing persons who do not respond in 2 minutes:

Attempt tc contact the person (s) by telephone at home (if telephone number can be obtained).

Attempt to contact the person (s) by telephone at the Remote Emergency Assembly Area at the Jersey Cent ral Powe r & Light Berkeley Operating Headquarters, Telephone (201) 244-4728/4726 If all personnel are accounted for using the methods described in the paragraph above the Site Protection Sergeant will notify the Emergency Director that all persons are accounted for, and accountability is completed.

If any person (s) do not respond, notify the Emergency Director that accountability is completed, and provide the name(s) and security badge slot numbers of missing persons.

The* Emergency Director will initiate Search &

Rescue Operations (EPIP-22).

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Sue,ect: PereIure No.

Sita Evccustion & Parsonnel EPIP-13 NO 1 '# 8 Accountability After Site Evacuation q ,,, s i o n N o. Oofe 1 2/17/82

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AITACHMENI 2 SITE EVACUATION ORDERED, PERSONNEL ACCOUNTABILITY PREVIOUSLY ORDERED, NOT COMPLETED 1.0 VERIFICATION The Oyster Creek Nuclear Generating Station Site Protection Sergeant will verify that a site evacuation has been ordered by the Eme rgency Director and the evacuation route to be used (North or South).

2.0 SITE EVACUATION METHOD After the site evacuation message has been verified, the Oyster Creek Nuclear Generating Station Site Protection Sergeant will ensure each of the following are notified that a site evacuation is ordered; muster and report required.

2.1 Personnel at Oyster Creek Nuclear Generating Station located outside of the protected area and within the area defined on the north and south by the canal, the east by the security fence west of Route 9, and on the west by the switch yard security fence.

2.2 Oyster Creek Nuclear Generating Station, Training Annex (Bldg.

24), Telephone 6905, 6906.

( 2.2.1 The Supervisor Support Program Training or his designee '

is responsible to ensure that all persons in the Oyster Creek Nuclear Generating Station Training Annex area !

are mustered , and the results of the muster forwarded l

to the Site Protection Sergeant. Telephone 6954, 6950.

o This activity is occupied during normal work hours (Monday through Friday). If telephone communications cannot be established, the Site Protection Sergeant is responsible to ensure that the Training Annex is not occupied.

2.3 Forked River Construction Site Security Department, Telephone Number (609) 693-7703, 609 971-4359.

2.3.1 The Forked River Security Department will request each of the following activities submit a muster list of personnel present to the Forked River Security Department.

2.3.1.1 Forked River Construction Site 2.3.1.2 The Ene rgy Spectrum, Telephone (609) 971-4931/4932 2.3.1.3 Oyster Creek Nuclear Generating Station Activities located in Building #12 and

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Building #1 at Forked River.

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Suotect- Pne m a No.

Site Evccuation & Parsonnel RPIP-13 FSO , of a *cces Accountability After Site Evacuation Rension N o. Oate 1 2/17/82

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ATTACHMENT 2 2.3.2 Upon completion of the muster, notify tne Oyster Creek Nuclear Generating Station Security Department that the muster is complete, Telephone 6954, 6950. The muster

, list should be forwarded to the Oyster Creek Nuclear Generating Station Site Protection Sergeant within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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2.4 The Site Protection Sergeant will ensure that the Secondary Alarm 9tation opens door 130-D.

l 2.5 Personnel departing the Oyster Creek Nuclear Generating Station

, protected area will exit through either the Main Gate Processing Ce nter or the North Gate Processing Center. Personnel in the Emergency Assembly Area will exit the protected area through door i 139-B. Each person leaving the protected area is responsible to:

2.5.1 Turn-in to the Site Protection officer assigned to the

, exit area (s) their dosimeters and TLD's for future collection, processing, and dose assessment.

2.5.2 Turn in Oyster Creek Nuclear Generating Station security badge to the Site Protection Officer assigned to the

( exit area (s).

2.5.3 Obtain departure instruction sheet and evacuation route f map (Attachment 4) from Site Protection Officer assigned

, to the etit area (s).

2.5.4 Evacuate from Oyster Creek Nuclear Generating Station to the Remote Assenb;y Area in automobiles containing no less than 4 per .%.

I 2.5.5 Follow ete y es,,ibed route (North g South) to the Remote Aist % y :a.

2.6 The Site Protection Sergeant vill ensure that persons departing the Oyster Creek Nuclear Generating Station protected area:

2.6.1 Turn-in their individually issued dosimetry.

2.6.2 Turn in their Oyster Creek Nucidsr Generating Station security badge.

2.6.3 Are issued departure instruction sheet / evacuation route map (Attachment 4) with instructions for the proper Route to use.

2.7 Personnel who evacuate the site shall proceed directly and expeditiously to the Remote Assembly Area following the designated

( route and shall wait there for further processing.

e 2.8 As personnel arrive at the Remote Assembly Area, they shall be mt ster'ed by the Site Protection Officer assigned.

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Site Evtcustion & Personnal EPIP-13 N42 8# a 4" Accountability Af ter Site Evacuation Revision N o. ots 1 2 /17/82 i

ATTACHMENT 2 2.9 Personnel shall be surveyed for contamination by a member of Radiological Control. Skin contamination levels which exceed 100 CPM above background will require decontamination in accordance with EP IP-21. (The vehicle of a contaminated individual must be surveyed and decontaminated if necessary).

2.10 Further disposition of personnel will depend upon the nature of the emergency and anticipated personnel needs for recovery operations.

2.11 The Site Protection Se rgeant will contact the Radiological Protection Coordinator for disposition of collected dosimetry.

3.0 SITE ACCOUNTABILITY METHOD 3.1 The Site Protection Sergeant is responsible to ensure that site accountability status is determined within 30 minutes after site evacuation is ordered.

3.2 If not previously accomplished as a result of Site Ac countability

( EPIP-12) , the Site Protection Se rgeant will ensure that onsite Oyster Creek Nuclear Generating Station Security De partment i

personnel are accounted for utilizing a security badge slot number listing. l 3.3 The Site Protection Sergeant will ensure that the Emergency Assembly Area meets the minimum hebitability re q u ireme nt s. (less than 50 mrem /h our) . If the Emerg ency Assembly Area does not meet this requ irement , the Radiological Controls Coordinator will ensure that a habitable area is designated for use by the Oyster Creek Nuclear Generating Station Security Department.

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. Svetect: Pnce:ure No.

Site Evecu: tion & PJrsonnal EPIP-13 I'O 4 'I A 0' Accountability After Site Evacuation Revision N o. ore 1 2/17/82

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l ATTACHMENT 2 3.4 The Site Protection Sergeant will ensure that security badges and dosimetry collected at the North Gate Processing Center and the Main Gate Processing Center are transferred to the Emergency Assembly Area.

3.4.1 Should the Emergency Assembly Area not meet habitability requirements, collected Oyster Creek Nuclear Generating Station security badges, dosimetry and security badge ,

storage drawers will taken to the area designated by the l Radiological Controls Coordinator.

3.5 The Site Protection Sergeant will designate Site Protection Officers l (as necessa ry ) to place the collected Oyster Creek Nuclear l Generating Station security badges with dosimetry attached into the appropriate slots in the storage drawers. These officers will inventory each security badge storage drawer and compile a list of the badges ng in the storage drawers by security badge slot number. This list will be delivered to the Site Protection Sergeant, when completed.

3.6 Personnel assigned to the following areas I

( Control Room l

Technical Support Center

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f Operations Support Center l shall be accounted for in the following manner: j i

3.6.1 Control Room - The Group Shift Supervisor shall ensure that all members of the operating shift are mustered by security badge slot number. Additionally, members of senior plant management present in the Control Room will be mustered by security badge slot number. A composite listing of the security badge slot numbers shall be submitted to the Site Protection Sergeant within 10 minutes of site evacuation being ordered by the Emergency Director.

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Sita Evacuation & Pe rsonne l EPTP-13 ho 5 M , %s Accountability After Site Evacuation q ,,,,, o n N o. Care 1 2 /17/8 2

.c ATTACHMENT 2 s

3.6.2 Te chnical Support Center (if activated) - ne Technical Support Coordina tor shall ensure that all personnel present in the Te ch nical Support Ce nter are mustered by security badge slot number. A listing of security badge slot numbers shall be submitted to the Site Protection Se rgeant within 10 minutes of site evacuation being ordered by the Emergency Director.

3.6.3 Operations Suppo rt Center (if activated) -

The Operations Support Coord inator shall ensure that all personnel present in the Operations Suppo rt Center are mustered by security badge slot number. Additionally, emergency teams dispatched from the Operations Support Center shall also be mustered by security badge slot number. A composite listing of the slot numbers shall be submitted to the Site Protection Sergeant within 10 minutes of site evacuation being ordered by the Faergency Director.

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3.7 The Site Protection Sergeant will collate accountability reports f rom the Control Room, the Technical Support Center, the Operations Support Center, and Security De pa rtment . This collated listing of security badge slot numbers will be compared to the list of security

( badge slot numbers derived from the security badge storage drawer inventory. -

3.8 Results of this comparison, may result in any condition listed below or a combination of Conditions 2 and 3.

3.8.1 Condition 1 - All Personnel Accounted For 3.8.1.1 All security badge slot numbers on the security badge storage drawer inventory list correspond with the security badge slot numbers on the collated listing.

NOTE: Re quired Action: Site Protection Se rgeant -

Notify the Eme rgency Director that all personnel in the protected area have been accounted for, and accountability is completed.

3.8.2 Condition 2 - Missing Person (s) s

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krect: Proc: cura N .

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Sito Evrcustion & Personnal coro i, ,

Accountcbility Af ter Site Evacuation a,wAen ya :,,,

1 2 /17 /A 2 e

ATTACHMENT 2 3.8.2.1 Security badge slot number (s) appear on the security badge storage drawer invent o ry list, but not on the collated listing.

l NOTE: Requ ired Ac tion: Page the missing i

person (s) using the Public Addre s s System. Missing persons who do not respond in 2 minutes:

Attempt to contact the person (s) by telephone at home (if the telephone number can be obtained) .

Attempt to contact the person (s) by telephone at the Remot e l Eme rge ncy As sembly Area at the I Jersey Ce ntral Power & Light Berkeley Operating Headqua rte r s ,

Telephone (201) 244-4728/4726.

If all person (s) listed in Condition 2 above respond to the page or telephone

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call, the Site Protection Se rgea nt will notify the Eme rge ncy Di rec tor that all persons are accounted for in the protected area, and accountability is completed. !

If any of the person (s) in Condition 2 above do not re spond to the page or telephone call, the Site Protection Sergeant will notify the Eme rge nc y Director that accountability is completed , 'and provide the name(s) and slot numbers of missing person (s).

The Eme rgency Director will initiate Search and Re scu e Operations (EPIP-22) .

t 3.8.3 Condition 3 - System Error s

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i l Svetect: Penmure u Site Evccustion & Parsonn21 ISO 7 Of acqos EPIP-13 a Accountebility Af ter Site Evecustion a ,,, ,, an y a, 3,3 l 1 2 /17/82 ATTACHMENT 2 3.8.3.1 Security badge slot numbers appearing on the collated listing, but not on the Eme rge ncy Assembly Area list.

NOTE: Required Action: De termine the source of the error (Examples: Security badge filed in the wrong slot in storage drawer; incorrect security badge slot number reco rde d on Eme rgency Assembly Area list or collated listing).

D!.;erepancies will be resolved by the Site Protection Sergeant or his designee. Upon.

resolution, the Site Pro tec tion Se rgeant will notify the Emergency Director that all persons a re accounted for in the pro tec ted a re a , and accountability is completed.

3.8.4 Condition 4 - Combination of Conditions 2 and 3 3.8.4.1 Required Ac tion: The Site Protection Sergeant

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or his designee shall perform the required actions listed in Conditions 2 and 3 of this-section. '

3.9 Alternate Accountability Method 3.9.I A DIGITAL Computer System is normally used to account for persons in the protected a rea at Oyster Creek Nuc le ar Generating Station. Should site evacuation be ordered and this accountability system be available for use, a listing of all personnel within the protected area can be obtained from the computer system at the Central Alarm Station.

3.9.2 A muster will be conducted by security badge slot number in each of the following areas:

Control Room Technical Support Ce nter Operations Support Center Oyster Creek Nuclear Generating Station Security Department in accord ance with the provisions of paragraphs 3.2 and 3.6 of this attachment.

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. Suotect: NcWa No.

Site Evccuntion & Parsonnal '""D '

Accountability After Site Evacuation Revision N o. Octe 1 2/17/82 r

ATTACHMENT 2 3.9.3 The Site Protection Officer (s) assigned to the Remote Emergency Assembly Area will muster all persons there by security badge slot number. This listing will be conveyed immediately, upon completion, to the Site Protec tion Se rgeant .

3.9.4 The Site Protection Sergeant is responsible to ensure that the listings of those persons mustered are compared to the computer listing in order to determine the site personnel accountability status. -

3.9.5 All Personnel Accounted For - The Site Protection Sergeant will notify the Emergency Director that all persons in the protected area are accounted for and site accountability i is complete.

l l 3.9.6 All Personnel No t Ac counted For - Page the missing person (s) using the Public Ad d res s System. Missing persons who do not respond in 2 minutes:

Attempt to contact the person (s) by telephone at home (if telephone number can be obtained) .

Attempt to contact the person (s) by telephone at the Remote Emergency Assembly Area at the Jersey Central Power & Light Berkeley Operating He a dqua rt e r s ,

Telephone (201) 244-4728/4726. ,

If all personnel are accounted for using the methods described in the paragraph above the Site Protection Se rgeant will notify the Fae rgency Director that all persons are accounted for, and accountability is completed.

If any person (s) do not re spond , notify the Eme rgency Director that accountability is not completed, and provide name(s) and security badge slot numbers of missing persons.

The Emerg ency Director will initiate Search and Rescue Operations (EPIP-22). {

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. Suotect: P'oistura No.

Sits Evtcuttion & Personnsl EPIP-13 FeG3 1 :f 3 =cqes Accountability After Site Evacuation 4evision N o. Octe 7 2/17/d2

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ATTACHMENT 3 SITE EVACUATION ORDERED, PERSONNEL ACCOUNTABILITY COMPLETED 1.0 VERIFICATION The Oyster Creek Nuclear Generating Station Site Protection Sergeant will verify that a site evacuation has been ordered by the Emergency Director and the evacuation route to be used (dortn or Soutn).

2.0 SITE EVACUATION METHOD After the site evacuation message has been verified, tne Oyster Creek Nuclear Generating Station Site Protection Sergeant will ensure each of the following are notified that a site evacuation is ordered:

2.1 Personnel at Oyster Creek Nuclear Gene rating Station located outside of the protected area and within the area defined on the north and south by the canal, the east by tne security fence west of Route 9, and on the west by tne switen yard security fence.

f 2.2 Oyster Creek Nuclear Generating Station, Training Annex, Building #24 Telephone 6905 6906.

2.2.1 Th-is activity is occupied during normal work nours (Monday through Friday). If telephone communications cannot be established, the Site Protection Sergeant is responsible to ensure that the Training Annex is not occupied.

2.3 Forked River Construction Site Security Department, Telepnone (609) 693-7703, (609) 971-4359.

2.3.1 The Forked River Security Department will request eacn of the following activities submit a muster list of personnel present to the Forked diver Security Depa rtment.

2.3.1.1 Forked River Construction Site.

2.3.1.2 The Energy Spectrum, Tele pnone 609 971-4931/4932 l

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Sootect: Pronzura No.

Sita Evtcustion & Parsonnel EPIP-13 ho 2 :f 3 ers Accountability After Site Evacuation

% sion N o. t Oate 2/174 2 y

ATTACRENT 3 2.3.1.3 Oyster Creek Nuclear Ge ne ra ting Station Activities located in Building #12 and Building #1 at Forked River.

2.3.2 Upon completion of the muster, notify tne Oyster Creen Nuclear Generating Station Security Depa rtment enat tne muster is complete, Telephone 6954, 6950. Ine muster list should be forwarded to the Oyster Creek Nuclear Generating Station Site Protection Sergeant within 24 nours.

2.4 The Site Protection Sergeant will ensure that the Seconda ry Ala rm Station opens door 130-D.

2.5 Personnel in the Emergency Assembly Area will exit tne protected area through door 139-B. Each person leaving the protected area is responsible to:

2.5.1 Turn-in to the Site Protection Officer assigned to tne exit area their dosimeters and TLD's for future collection, processing, and dose assessment.

7 2.5.2 Obtain departure instruction sheet / evacuation route map (Attachment 4) from Site Protection Of ficer(s) assigned to the Emergency Assembly Area.

2.5.3 Evacua te from Oyster Creek Nuclear Generating Station to the Remote Assembly Area in automobiles containing no less than 4 persons.

2.5.4 Follow the prescribed route (North or Soutn) to tne demote Assembly Area. .

2.6 The Site Protection Sergeant will ensure that persons departing tne Oyster Creek Nuclear Generating Station protect'ed area:

2.6.1 Turn-in their individually issued dosimetry.

2.6.2 Are issued departure instruction shee t / evacuation route map (Attachment 4) with instruction for tne proper route to use.

2.7 Personnel who evacuate the site shall proceed directly and expeditiously to the Remote Assembly Area following the designated route and shall wait there for further processing.

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Pnexuro No. i Sootect: i Site Evcc attion & Parsonnel EPIP-l3 Feo 3 :f 3 2cqos Accountability After Site Evacuation Revision N o. t Octe 2/17/d2

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ATTACRENT 3 2.8 As personnel arrive at the Remote Assembly Area, tney snalt oe logged in by the Site Protection Officer (s) assigned.

2.9 Pe rsonnel shall be surveyed for contamination oy a memoer ot Radiological Control . Skin contamination levels whicn exceed 100 CAM above background will require decontamination in accordance witn EPIP-21. (The vehicle of a contaminated individual must be surveyed and decontaminated if necessary).

2.10 Further disposition of personnel will depend upon the nature of tne emergency and anticipated personnel needs for recovery operations.

I 2.11 'Ihe Site Protection Se rgeant 'will contact the Radiological l

Protection Coordinator for disposition of collectea dosimetry.

3.0 SITE ACCOUNTABILITY METHOD 3.1 Personnel Accountability previously completed in accordance witn EPIP-12.

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SUBJECT:

Sito Evscuztlon instruction EPIP-13 ,

sheet /Evacuttion Route Map Rev. 1 Date: 2-f7-P L RT 530 44 N'Z -- - ALD gggWICM ROAD -

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Oyster Creek N k OCNGS W N (CHECK Station Evacuation Routes E) a a* '

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SOUTH ROUTE S l l 4 + -+

"""*"*8""*'"'*"e ma me sopra - l h ROUTE 532 A. en an. n o ..g.s e4 to seeest r..e o,si., c..en me.ien r..e o eto r c een meesen (flDouble back at cross-over) to th. Dee.te Assembly Aree et C.meselleg stell.a 9. anUTN x e e e,e..nes r op...ts.no Ceneseting statt.se g. meep needgees ter s.

.a ete ,t. th. al et et., en no.te o t. th. eusa ilght. Turn plort en 9t.533 stop light. Teen stFT en to the poskesy. Go SOUTN tacey Bd. At Soute 4}S

3. Aetenobiles dele.n to the p.- en yeshway, doubt. b M e tesa DICNT. Turn stFF e.t. As.=63r As.e esa s = w. to the ~mort et fs,et c..e. . eaWho to the~

et leset 4 occupante. ev.e. co poWTW en Peskuey Seekeley cy. set t.ee seed-to e.tvic. E and double geses.se 1.n the left).

C. usadowe end ett wente emot f** back 00Uta to 8 cey DJ.

nele cl.e.4. ce g on tecey ed.

At p.et. 630 toen plcurt.

o. r..n se dis ut.4 at th. o.- T a ter? .a o.ee. lW e.te Ae.ee61y Ar.o. to thlesk. ley cretell.no mesateestere 1.n th. "ef tl.

S. seester eith th. Olt. Fee-tectl.a offices.

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SUBJECT:

Site Evacuation instruction EPIP-13 ,

thast/ Evacuation Route Map Rav. I Dates 2-fl.3L RT 530 A j 'i'~-~ _ _

ND KESWICK ROAg

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//'s[e[ (Double back at service area) g I I glQI s LACEY ROAD $ k)

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Station Evacuation Routes - e*l I '

(CIIECK ONE) W1 >-- E t

._ ___ ___ _ N O R TH R O U T E k

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" " " = = = = '*"'""o" I A e *".'."."o"ne'"i to report n es e . qui ..d r o. oy.t., c.een nucl.e, re- oyste, c...a muel..,

I(ROUTE 532 Double back at cross-over) to the Benote Assembly Asee et Generellag station go SOUTN JCP 4 L Berkeley Oposettone Cenefallag Stellen go poj needquestere.

en poute 9 to the fleet stop on Soute 9 to the second light. Tuse plCNT en St.112 stop light. Turn LEFT on to the Parkuey. Go SOU7tl LaceF 84. At Soute Sig B. Autonobiles driven to tse pe* en Peshuay, double beTIo turn DICHT, Turn LETT note Assembly Asee ellt heee to the es0STN et fleet egoes on Doute $10 to the et least 4 occupante, oueg. co esonTN en Peskuey Besteler operettene need-to service area and double quartese ton the left).

C. Windoue and air eente nuet to- back SOUTM to Lacey Bd.

nela closed. Go RICHT on Lacey Rd.

At Doute 610 tusa alcuT.

D. Desk as directed at the 8** Turn LEFT on SoutelE m te Assembly Area. to the3 akeley Operstlene needquestore ten the lef tl.

5. m.eter with the site Pro-tection officer.

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prp [*1 Page1 Of a Date issuec I Effective Cate 1 Jersey Central 2ne/82 l 3,,,32_3,19,32

- Power & Light Company Revisen No. Cate 0 2/26/82

Subject:

Activation of the Parsippany Technical ,

D r c or Station Operations Approvals ;o t/r ric ,

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O ter Creek Nu ar Generating Station V

LIST OF EFFECTIVE PAGES DATE REVISION NLMBER 1 2/26/82 0 2 2/26/82 0 3 2/26/82 0 4 2/26/82 0 5 2/26/82 0 6 2/26/82 0

( 7 2/26/82 0 8 2/26/82 0

ATTACIMENTS Attachment I (2 pages) 2/26/82 0 Attachment II 2/26/82 0 Attachment III 2/26/82 0 Attachment IV 2/26/82 0

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l NON-CONTROLLED l This Document Will Not Be Kept

' Up To Date .

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. Sootect: P tesiure No.

Activstion of the Parsippany Technical EPIP-17 40 2 Of 6 4cs Funct ons Center ,,,,,,o, N o. ,

0 L/1o/d2

' e 1.0 PURPOSE The purpose of this procedure is to provide guidelines tor tne Group l Leader - Technical Support to activate and maintain the Parsippany Technical Functions Center.

The Emergency Director or the Emergency Support Director is responsible for implementing this procedure.

2.0 ATTACHMENTS 2.1 Attachment I - Data Link Operating Instructions.

2.2 Attachment II - Parsippany Technical Functions Center Arrangement.

2.3 Attachment III - Parsippany Technical Functions Ce nter recnnical Document Invento ry.

2.4 Attachment IV - Retrieval Instructions for OCNGS Document in ene

( DDCC.

3.0 EMERGENCY ACTION LEVELS 3.1 This procedure is to be initiated upon declaration of any o t. tne following: ,

3.1.1 EPIP 4: Site Emergency.

3.1.2 EPIP 5: General Emergency.

3.1.3 At any other time when ene ' Emergency Director or tne Emergency Support Director believes plant conditions warrant the action.

1 4.0 EMERGENCY ACTIONS 4.1 The Group Leader - Technical Support:

Shall be re sponsible for' providing technical analysis, evaluation and i

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, s.og: P*oce ure No.

Activction of ths PIrsippany Technical EPIP-17 NU 3 U 4 W' Functions Center a.,,sion N o. :ote 0 1/20/02 reconsnendations to. the Emergency Support Director and tne On-Site Technical Support Coord inator with respect to plant conditions, reactor core status and plant operations. He shall activate tne appropriate personnel within the Parsippany recnnical Functions Center (PTFC), using PTFC Call-Out Roster, and direct enem to assume and perform their designated responsibilities witnin esca individual's emergency position.

4.1.1 Technical Support - Representative his individual shall be assigned to tne Oyster Creen 100)

Nearsite Emergency Operations Facility (NEOF) and snall De responsible for supporting the activities of tne c'me rge nc y Support Director and coordinating with Te chnica l Support k Cente r and Pa rsippany Tecnnical Functions Ce nte r ac t ivit ie s.

4.1.2 Technical Support - Sec tion Manager This individual shall provide general tecnnical support and management of additional technical resources as tne resources required to support the emergency are identitied by the Group leader - Technical Support.

4.1.3 Technical Support Staff his position shall provide general staf f support to tne Group IAader - Technical Support including organization, planning and scheduling and administrative controls. Inis position also provides for the Data Linn Ope ra to r ,

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. Suotect: Anexurs No.

Activetion of ths Persippany Technical EPIP-17 40 4 af d 4ces Functions Center 9evision N o. :ste 0 LILo/6L

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Communicator and Status Board Keeper functions until otherwise assigned by the Group Leader - Tecnnical Support.

4.1.3.1 Data Link Operator This individual shall activate tne data lins, to the onsite process computer and provide plant data to tne Group Leader for evaluatiot..

I 4.1.3.2 Communicators These individuals shall estaolisn communications f

and maintain phone lines witn:

1). The Nearsite Emergency Operations Facility and the Onsite Technical Support Center via the Technical Functions dedicated line.

-s 2). General Electric Emergency Support Center in San Jose, California via tne Parsippany/ Genera [ Electric dedicated line (future line).

While using both tnese lines, tne communicators shall maintain the Telephone Communication Logs.

4.1.3.3 Status Board Keeper This individual shall maintain tne Pa rs ippany Technical Functions Center Status Board witn information from the Data Link Operator and Communicator and shall maintain the Group Leader Technical Support Log as directed of tne Group Leader - Technical Support.

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, Suetect: P*ocaluro No.

Activation of ths Parsippany Technical EPIP-17 ISC3 5 Of d se ts l

Functions Center q ,, ,, a n ya ; ,,,

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IIME/ INIIIALS 4.2 Upon activation of the Parsippany Technical Functions Center, the following actions shall be taken:

4.2.1 The individuals listed in 4.1 above /

shall be notified and report to the center. Ca ll-out rosters snould be placed in the PTPC.

4.2.2 Communications with the site shall /

be established and the Telephone Communications Log Sheets shall be maintained.

4.2.3 Start the Group Leader - Technical ,

/

Support Log.

4.2.4 Activate the data link per Attacnment I /

and post current conditions on the status board.

4.2.5 Arrange the Support Center in /

accordance with Attachment II.

4.2.6 Inventory Technical Documents per /,

Attachment III.

4.2.7 Establish a watch bill for the /

Parsippany Technical Functions Center.

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- i gg Pue: cure No.

Activation of the Pzrsippany Technical EPIP-17 Pc43 6 :f 8 me ts Functions Center Revision Na

0 2/26/82 l DATE:

TIME / INITIALS 4.2.8 Notify the Emergency Director and/or /

the Emergency Support Director that the duties of the Group Leader - Technical Support have been assumed an'd that tne Parsippany Technical Functions Center is operational.

4.3 Maintenance of the Parsippany Technical Support Center The Group Leader - Technical Support shall execute the following steps as appropriate after receiving the necessary support information from the Emergency Support Director.

( DATE:

TEHE/ INITIALS 4.3.1 Establish communications with the /

General Electric Emergency Support Center on the dedicated Parsippany/

General Electric line by activating the dedicated line as follows:

1. Utilize Coventional Telephone System. *

2. Dial Area Code (408; 925-3207.

3. Request the activation of the General Electric Emergency Support 8

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Suop: P oce:ure No.

Activation of the Parsippany Technical EPIP-17 #cq) 7 sf d :cqes Functions Center Revision % 0 IC' 2/2o/o2 1

DATE:

TIME / INITIALS Center and report emergency condition.

4.3.2 Evaluate what additional personnel /

will be required to support the plant and have them report to tne Parsippany Technical Functions Center. Call-out roster should be placed in PTFC.

4.3.3 Establish frequency of status board /

update appropriate for emergency conditions.

[ 4.3.4 As conditions warrant, the /

number of personnel staffing the Parsippany Technical Functions Center may be reduced by the Group Leader Technical Support.

5.0 FINAL CONDITIONS 5.1 The Emergency Director / Emergency Sup' port /

Director has determined the PTFC is no longer needed due to present plant conditions and has ordered the PTFC de-ac t iva ted .

NOTE: PTFC is not automatically activated during an Unusual Event or Alert Emergency action levels.

n. -

wg: Proc:<ure No.

E'30 8 2f 8 seqes Activation of the Parsippany Technical EPIP-17 Functions Center q,,,,,,, y ,, 7,,,

0 2/26/82

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DATE:

TIME / INITIALS l

1 5.2 The PTFC is de-activated, all materials and /

l equipment have been returned to their 1

emergency storage place and the PTFC is in )

a complete state of readiness.

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.. EPIP - 17 Rsv. 0 2/26/82 l

ATTACHMENT I !

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o /' DATA LINK OPERATING INSTRUCTIONS l At the Tektronics Terminal in Room 116:

1. Turn power on.

2. Set the two band rate indicators to 300 (located on back of Terminal).

3. Set switch number 3 to NP position (located on front console of Terminal).

4. Turn power on to the Acoustic Data Coupler / Modem.

5. Place T-Bar selector switch to TSO/300 position.

6. Dial (609) 693-6759 or 693-6760.

7. When tone signal is received, place telephone handset into the Acoustic Data Coupler / Modem.

8. Execute ene following login procedures:

User Types in: System responds with:

LOGIN GPUSC PRIMOS Version REV. 18.2.2.0YS. ___. . . . _

( ~CPUSC (2) LOCGED IN AT (cur--nt -in ar.4 4:::)

PROJECT - ??? - ~ ^

CPUNUC LOGIN NAME - ???

BLOB ENTER: Your reason for logging in: ???

DATA Welcome to the JCP&L PSMS Computer located at Oyster Creek ** New news on (date)

Type News to receive news.

Ok, DASEDIT Type HLP to get command summary, CR to continue.

(Hit Carriage Return) Select a file to be displayed Answer: CU, CI, OP, AN or QU.

CU Time f rom SIGMA-3 = (date) (time)

(Five pages of output will be displayed for the current data file. Execute the COPY switch on the Terminal and give the data to the Group Leader Technical Support.)

1 i

EPIP - 17 Rev. O 2/26/82 ATTACHMENT I (Cont'd)

/

QU OK, C ALL OK, LOGOUT (session ends)

9. Repeat the above login and data gathering procedures at the time Laterval specified by the Group Leader Technical Support.

10. Ref er to the BWR Hybrid Power Shape Monitoring System User's Manual for more detailed instructions.

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e EPIP - 17 Rev. O ATTACHMENT III 2/26/82

/ PARSIPPANY TECHNICAL SUPPORT CENTER TECHNICAL DOCILLENT INVENTORY (Items contained in Room 115)

1. OC - Emergency plan

2. Emergency Plan Implementing Procedures

3. Logs:

Croup Leader - Technical Support Log Telephone Communications Log Sheets

4. Emergency Duty Rosters:

OC - On-Site OC Offsite Emergency Support Organization S. Technical Documents:

./

\ OC Plant Description Manual 4

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i ATTACitt!E!1T IV RETRIEVAL INSTl;UCTIONS FOR OC DOCUMENTS IN Tile DDCC EPIi) ~ 17

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[IP-24 P3981 Of 4 Date issued =ffective Cate Jersey Central 2/19/82 3/9/82-3/19/62

, Power & Light Company Revision No. Dat 9 82 Emergency Respiratory Equipment Autnonzec Sy

,g g Director Oyster Creek Operations

(&ML N Oyste Creek Nuclear Generating Station LIST OF EFFECTIVE PAGES DATE REVISION NLMBER 1 2/19/81 0 2 2/19/82 0 3 2/19/82 0 4 2/19/82 0

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ATTACINENTS Attachment 1 2/19/82 0 NON-CONTROLLED This Document Will Not Be Kept Up To Date

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1.0 PURPOSE This procedure describes the method used to issue personnel respiratory protective devices during classified eme rgency conditions when the primary respiratory issue facility is not available for use. Other issue of emergency respiratory equipment is performed in accordance with Oyster Creak Nuclear Ge ne ra t ir.g Station Procedures.

2.0 ATTACHMENTS 2.1 Attachment 1- Emergency Respiratory Equipment Issue Location 3.0 EMERGENCY ACTION LEVELS 3.1 EPIP-2 Unusual Event 3.2 EPIP-3 Alert 3.3 EPIP-4 Site Emergency 3.4 EPIP-5 General Emergency

/ 4.0 D4ERGENCY ACTIONS ,

s 4.1 Initiating conditions The issue of emergency respiratory equipment at the Forked River Site, Building 14, will be implemented when any of the following conditions exist:

4.1.1 Normal respiratory equipment is inaccessible due to emergency conditions.

4.1.2 Normal respiratory eqaipment . issue facilities have been damaged or compromised as a result of emergency conditions.

4.1.3 Site evacuation has been implenented. j l

4.1.4 Additional respiratory equipment is required due to !

the emergency condition.

4.2 Forked River Emergency Respiratory Equipment Issue Location l l

4.2.1 Forked River Site, Building #14 (See Attachment 1) l l

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, g Puczure No.

Emergency raspiratory Equipment EPIP-24 h43 3 3f 4 DGI' Revision N o. Octe 0 2/19/82 4.3 NOTIFICATIONS 4.3.1 The Group Leader Radiological Support or his designee is responsible to notify the following when emergency respiratory equipment issue facility is activated.

4.3.1.1 The Radiological Controls Coordinator.

4.3.1.2 The Environmental Assessment Coordinator.

4.4 EMERGENCY RESPIRATORY EQUIPMENT 4.4.1 Respirators for Emergency use will be obtained from the normal respirator issue station. Additional respirators are available in the warehouse.

4.4.2 Forms for respiratory equipment issue and tacord-keeping will be maintained at the Forked River Energency Respiratory Equipment Issue Facility.

4.4.3 Respiratory equipment will be maintained and/or calibrated in acco rdance with applicable station procedures.

/ 4.4.4 Spare parts, tools and other necessary equipment for

\ the repair and cleaning or respiratory protective devices shall be maintained at the Forked River Facility.

4.4.5 Scott air iak cylinders requiring refilling may be refilled at the Fo rked River Facility provided that air samples. taken in the intake area show lower concentrations of isotopes than list in 10 CFR 20 Appendix B Table I column 1.

4.4.6 Air compressor for charging Scott Air Pak cylinders will be maintained in aedordance with station procedures.

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Sveiect: Emergency respiratory Equipment O$N2D ,,, 4, , 4m,9,

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. 4.5 Emergency Respiratory Equipment Use 4.5.1 Emergency respiratory equipment issue and maintenance l records will be maintained in ac co rdanc e with --

l applicable station procedures except as follows:

4.5.1.1 Respiratory equipment will be issued from and returned to the Forked River Emergency Re spirato ry Equipment Issue Facility (Attachment 1).

4.5.1.2 If the in plant RDiS computer is unavailable for use, respiratory qualification inf ormation will be transferred to the corporate computer in Reading, PA. Reports of qualification information will be issued by Reading.

4.5.1.3 If no computerized system is available, a l manual record-keeping system will be l instituted.

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EPIP - 24 a,l'*

SUBJECT:

EMERGENCY RESPIRATORY EQUIPMEi..

Rev. O Date: 2/19/82 ,

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EMERGENCY RESPIRATORY EQUIPMENT ISSUE LOCATION a:

Directions:

From Oyster Creek Nuclear Generating Station Proceed north on Route 9. Turn A left at first road, after canal bridge. .

Continue past JCP&L " Energy Spectrum" t OYSTER CREEK NUCLEAR Forked River Site Security. Park in East GENERATING STATION Parking Lot of Forked River Site. Enter Gate #5 to Bldg. 14.

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i EPI - P3g3 1 Of 4 Ott2 IS$uCC Jersey Central 2f w s1 l Eff;ctivo 2nus2Ca!O

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l Power & Light Company Revision No. l Cate IuDject:Pecovery Operations 4 g Director Station Cperations Approval / Onyfen l 7 h . r.' / /dA Proj ./

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LIST OF EFFECTIVE PAGES DATE REVISION NUMBER 1 3/04/82 1 2 3/04/82 1 3 3/04/d2 L 4 3/04/82 1 ATTACILMENTS Attachment 1 ( 1 page) 3/04/d2 1 Attachment 2 ( 2 o.iaesI 3/04/82 1 l

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NON-CONTROLLED l This Document Will Not Be Kept Up To Date

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8eges RECOVERY OPERATIONS EPIP-29 Dege 2 8f 4 aevision N o. Octe g

i DATE 1.0 DOCUMENTATION TIME / INITIALS 1.1 Recovery Phase classified af ter tne following conditions are met: /

1.1.1 Radiation levels in all in plant areas are stable and decreasing with time. /

1.1.2 Releases of radioactive material to tne environment from the plant are under control or have ceased. /

1.1.3 Containment pressure is at normal levels. /

1.1.4 Reactor plant is stable and in a long-term safe shutdown condition. /

1.1.5 Any fire, flooding, or similar emergency conditions are controlled or hpve ceased. /

1.2 Notifications 1.2.1 Onsite personnel. /

1.2.2 Offsite agencies which were notified of the classified emergency. /

1.2.3 Recovery organization personnel. /

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RECOVERY OPERATIONS EPIP-29 4G3 3 Sf 4 4qes aevision N o. 2ote .

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l' 2.0 ACTION LEVEL REFERENCES 2.1 EPIP-1 Classification of i.mergency Conditions 2.2 EPIP-2 Unusual Event 2.3 EPIP-3 Alert 2.4 EPIP-4 Site Emergency 2.5 EPIP-5 Ceneral Emergency 3.0 PRECAUTIONS Not applicable to this procedure.

4.0 PROCEDURE his procedure provides guidance in tne impleme nta tion of a recovery ef fort subsequent to the declaration of a classified emerdency.

4.1 Initiating Conditions he emergency is considered to be in the decovery Pnase wnen tne following conditions are met:

i 4.1.1 Radiation levels in all in plant areas are stable and decreasing with time.

4.1.2 Releases of radioactive material to tne environment from the plant are under control or have ceased.

4.1.3 Containment pressure is at normal levels.

4.1.4 Reactor plant is stable and in a Lond-term safe shutdown condition.

4.1.5 Any fire, flooding, or similar eme rdency conditions are controlled or nave ceased.

4.2 Responsibility The Emergency Director / Emergency Support Director, as appropriate,is responsible to determino and declare wnen an emergency situation is stable and in ene recovery pnase. I'n e emergency s'ituation will be considered stable when ene criteria of paragraph 4.1 are met.

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, RECOVERY OPERATIONS EPIP-29 *148 4 af 4 8cqes Revistra % :ste 4.3 Notifications The Emergency Director / Emergency Support Director, as appropriate, shall ensure the following personnel / organizations a re notified the emergency situation is staole and tne decovery Phase initiated.

4.3.1 Emergency Director, as applicaole.

4.3.2 Emergency Supervisors 4.3.3 Onsite personnel 4.3.4 Of fsite agencies which . we re notified or ene classtried emergency.

4.3.5 On-call recovery organization personnel.

4.4 Recover Operations The Emergency Director / Emergency Support Director, as applicaote, shall develop recovery plans, as necessary, to restore tne plant to a safe operating condition. Recovery operations are restricted as follows:

4.4.1 The radiation exposure limits of 10CFR20 apply.

4.4.2 Recove ry actions tnat may result in a radioactive release will be evaluated in advance. Suen events and data pertaining to the release will be reported to appropriate offsite emergency response organizations and agencies.

4.4.3 Estimatas of total populations exposure will oe made periodically, as required.

4.5 Recovery Organization The Emergency Director / Emergency Support' Director, as applicaole, will establish the necessary recovery organization based on ene nature of the accident, post accident conditions (i.e., plant conditions, radiation / contamination levels, etc.) or otner factors. The GPU-Nuclear Co rporation Lo ng-Te rm decovery organization (Attachment 1) will be initiated wnen long-term re cove ry operations are anticipated. Responsibilities of tne long-term recovery organizations are described in Attachment 2.

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Attachment 2 l

RESPONSIBILITIES OF THE LONG-TERM RECOVERY ORGANIZATION 1.0 office of the President CPUNC The Office of the President, GPUNC is responsiole for tne overall recovery operation. This includes overseeing tne operations or tne various functional groups; approving all activities, and proposed courses of action af ter proper analysis and coordination; selection or personnel to fill the key positions in ene long-term recovery organization .

2.0 Vice President, Director Ovster Creek The Vice President-Director Oyster Creek is responsiole for: all plant operations and maintenance activities; limiting and controlling personnel exposures; in plant radiological controls management; stabilizing plant conditions; restoring the plant's aoility to function normally; responding to any further emergencies. ne is responsible for safely and effectively managing tne quantities of radioactive gases, liquids, and solids that mignt exist durin6 ene initial phases of recovery. Subsequently, he is responsible for tne development and implementation of snort-term and long-term plans to manage and process contaminated solids, liquids, and gases; and tne establishment of processing priorities based on plant needs.

3.0 he Vice President Technical Functions The Vice President Teshnical Functions is responsiole tor providing engineering support, technical planning and analysis, procedure support, control room tecnnical support, data reduction and management, and sunport relating to licensing requirements. He is responsible for prov. ding engineering, and design support tor defining material and construction requirements necessary to complete required modifications or repairs to plant systems, equipment and structures.

In addition, he provides liaison to the Nuclear Regulatory Commission.

4.0 The Vice President Nuclear Assurance The Vice President Nuclear Assurance is responsiole for implementing the Quality Assurance Plan for all recovery activities. He is responsible for implementing all necessary general employee, tecnnical and recovery management training programs. He provides for ongoing development of the Emergency Plan and Implementing Documents and Attachment 2

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RECOVERY OPERATIONS EPIP-29 Keqes fio 7 :f 7

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,. e ensures that Emergency Preparedness is maintained during potentially hazardous recovery activities. He provides enemistry anc metallurgical analytical services, and provides advice on enemistry requirements and specifications for recovery activities. de monitors, evaluates and assures that all recovery activities have tne potential for compromising nuclear safety are adequately assessed.

5.0 he Vice President Radiological and Environmental Controls he Vice President Radiological and invironmental Co nt rols is responsible for establishing policy, coordinating and implementing radiation and environmental controls at ene station. He is responsible for providing in plant radiological controls management and monitoring, and for quantifying ene degree of contamination of buildings and personnel.

6.0 he Vice President of Maintenance and Construction he Vice President of Maintenance and Cons truc tion nas tne responsibilities for direction of activities associated witn major maintenance tasks and accomplishment of the field worn for major modifications. He also provides corporate oversight for all plant maintenance activities.

7.0 he Vice President Adminis tration he Vice President Administration is responsiDie for providing tne necessary administrative / logistic support (i.e. communications, manpower, transportation, commissa ry arrangements, accommodations, clerical support, and tempora ry office space and equipment.) de coordinates priorities; develops plans and senedules; coordinates and monitors the status of tasks; and reports the work progress of all tne technical groups. In addition, he provides administrattve support to the Nuclear Regulatory Commission.

8.0 he Vice President Communications The Vice President Communications is responsible for coorainating tne exchange of information with public and governmental agencies.

s Attachment 2

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ML20050D369

Contents

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1.0 INTRODUCTION

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