Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-1 Re Classification of Emergency conditions,EPIP-2 Re Unusual Event & EPIP-3 Re Alert
	ML20039A722
Person / Time
Site:	Oyster Creek
Issue date:	11/24/1981
From:	; JERSEY CENTRAL POWER & LIGHT CO.
To:	;
Shared Package
ML20039A716	List: ML20039A719; ML20039A722;
References
	PROC-811124, NUDOCS 8112210203
	Download: ML20039A722 (97)
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l EMERGENCY PLAN IMPLEMENTING / ADMINISTRATIVE PROCEDUFIS INDEX PAGE DATE 1 11/24/81 2 ( 11/18/81 1

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11/24/81 l Page 3 of 3 i EMERGENCY PLAN IMPLEMENTING PROCEDURES _

LAST LAST TITLE REV. NO. REV. DATE PROCEDURE #

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 EP AP - 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 Of fsite Medical Personnel Training 0 2/24/81 EPAP - 12 No t Issued EPAP - 13 Emergency Plan Implementing Procedure /

( Mainistrative Procedure Comment, Feedback and Evaluation Procedure 0 2/24/81 EP AP - 14 Emergency Plan Implementing Procedure /

Mainistrative Procedure Review /

., . Revision Procedure. ,

0 2/24/81 EPAP - 15 Emergency Response Mobilization (Proposal) 2/24/81 EP AP - 16 Maintaining Emergency Preparedness 0 l

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11/18/81 Page 1 of 3 EMERGENCY PLAN IMPLEMENTING /ADMINI.3TRATIVE PROCEDURES INDEX 3

PAGE DATE 1 11/18/81 2 11/18/81 3 i. 11/18/81 l

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I 11/18/81 Page 2 of 3 EPIP AND EPAP TITLE LISTING EMERGENCY PLAN IMPLEMENTING PROCEDURES LAST LAST PROCEDURE # TITLE REV. NO. REV. DATE EP IP ' - 01 Classification of Emergency Conditions 1 11/3/81 EPIP - 02 Unusual Event 1 11/3/81 EPIP - 03 Alert 1 11/3/81 EPIP - 04 Site Baergency 1 11/3/81 EPIP - 05 General Baergency 1 11/3/81 EPIP - 06 Not Issued EPIP - 07 Personnel Injury 0 2/19/81 EPIP - 08 Fire 0 2/19/81 EPIP - 09 offs'ite Dose Assessment 0 2/23/81 EPIP - 10_ Baergency Radiological Survey - Onsite ,0 2/19/81 EPlP - 11 Baergency Radiological Survey - Offsite 0 2/19/81 EPIP - 12- Personnel Accountability 1 4/28/81 EP IP - 13 Site Evacuation 0 2/23/81 Personnel Accountability Af ter Site 1 Evacuation 0 2/23/81 EPIP - 14 Damage Control .

0 2/23/81 EPIP - 15 Toxic / Flammable Gas Release 0 2/23/81 EPIP - 16 Radioactive Liquid Release 0 2/23/81 EPIP - 17 Not Issued 2/23/81

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^ EP IP - 18 Activation of the Remote ' Assembly Area .0 EPIP - 19 Baergency Dosimetry 0 2/23/81 20 . Tornado /High Winds EPIP - 0 2/23/81 EPIP - 21 Personnel- Decentamination 0 2/23/81 EP IP - 22 Search and Rescue Operations 0 2/24/81 EPIP - 23 Thyroid Blocking 0 2/24/81 EP IP . - 24 Not -Issued EPIP - 25- Activation of the Nearsite Daergency Operations Facility ,

0 , 2/24/81 EPIP - 26 Activation of the Technical Support Center 0 2/24/81

.EPIP . 27 Activation of the Operations Support Center 0 2/24/81 EPIP - 28 Activation of the Farsite Energency

,0perations Facility 0* 2/24/81 EPIP - 29 Recovery Operations 0 2/24/81 k/

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11/18/81 Page 3 of 3 EMERGENCY PLAN IMPLEMENTING PROCEDURES LAST LAST PROCEDURE # TITLE REV. NO. REV. DATE ADMINISTRATIVE PROCEDURES EPAP - 01 anergency Plan laplementing Procedure Format 0 2/24/81 EPAP - 02 Not Issued EPAP - 03 Not Issued EPAP - 04 Not Issued EPAP - 05 Energency Equipment Inventory 0 2/27/81 EP AP - 06 Energency 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 Offiste Fire Department Training 0 2/24/81 EPAP'- 10 First Aid Training 0 2/24/81 EPAP - 11 Offsite Medical' Personnel Training C 2/24/81 EP AP - 12 Not Issued EPAP - 13 Energency Plan Implementing Procedure /

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

Administrative Procedure Review /

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

EP AP - 16 Maintaining Energency Preparedness 'O 2/24/81 l

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,s c c " PrOCeCure NO.

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Oate issued Jersey Centra.g , , , , , , , l Effec'ive

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Power & Light Co.n;_any aevision No. li oato 11/3/81 1

Subject:

Classification of Emergency Authorized By Conditions _

Director-Ovster Creek Ooerations Approvd/Cycurre a Yl ${/ .

Profect:

f / Oyster Creek Nuch[ep/ r Generating Station , _

List of Effective Pages Date Revision Number 1 11/3/81 1 2 11/3/81 1 3 11/3/81 1 1

4 11/3/81 5 11/3/81 1 Attachments 1 (5 pages) 11/3/81 1 s

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Sub ct; Proc: dure No.

EPIP-1 Page2 c: 5 Pa,c- ,

1 Classification of Emergency Conditions Revision No. Date 1 11/3/81 __

1.0 PURPOSE 1.1 The purpose of this procedure is to define those conditions which shall be regarded as emergency conditions at Oyster Creek Nuclear Generating Station and to provide guidance in classifying such conditions.

1.2 The initial classification is made as soon as possible after the occurrence of an event or confirmation of events to ensure that q proper protective and corrective actions are taken and that !

appropriate offsite authorities are promptly notified (within 15 minutes) . Reclassification of an existing emergency condi. tion may occur as the result of continued surveillance and assessment of plant conditions and projected radiological releases.

1.3 Emergency conditions can be classified into one of four 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 the plant, including contaminated injuries of plant personnel which require offsite emergency

' treatment.

1.3.2 A_ert - Tha occurrence of an event or series of events' that indicate and allow recognitition of an actuals or potential substantial degradation of the level of' safety in the plant.

1.3.3 Site' Emergency ' Accidents in which actual or likely major failures of plant functions needed for protection of.the public have occurred. T'his. emergency class

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includes accidents which h' ave a"significant radiation release potential.

1.3.4 General Emercency - Accidents which involve actual or imminent substantial core degradation or melting with potential for loss of Reactor Building (containment) g integrity, and other accidents that have large radio-active release potential such as fuel handling and waste gas system accidents.

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Subject:

Procedure No.

EPIP-1 Page 3 5 Classification of Emergency Conditions Revision No. Date 1 11/3/81 1.4 Definitions 1.4.1 Emergency Action Levels - Define specific limits, parameters or equivalent status for establishing each emergency classifi-cation. Specific instrument readings, alarm points and/or indications are also included for easy recognition of the

, i,' emergency condition. There is a natural progression of imple-mentation criteria to be used by the Emergency Director as a

the initiating event escalates in severity, specific character-istics of the event are defined in order for the Emergency Director to implement the proper protective and corrective actions.

1.4.2 Emergency Actions are procedural guides for use by the Emerg'ency ' Director . These actions are specified-in Section

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4.0 of the Emergency Plan Impleme'nting Procedures. The Emergency Director may omit specific actions that are not necessary for the emergency condition and actions need not necessarily be performed in the order listed but all should be completed with 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 other EPIP's -

which may need to be- implemented for specific situations.

2.0 ATTACHMENTS 2.1 Attachment 1, Matrix of Emergency Action _ Levels for Emergency Classification.

3.0 ' EMERGE CY' ACTION LEVELS 3.1 As stated in Attachment 1

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Subject:

Procedure No.

EPIP-1 Page 4 or 5 Pa."

CLASSIFICATION OF EMERGENCY CONDITIONS Revision No. Date 1 11/3/81 4.0 EMERGENCY ACTIONS Time / Initials 4.1 The Group Shift Supervisor on duty shall:

4.1 1 Evaluate initiating conditions requiring the implementation of the Oyster Creek Nuclear Generating St.ition Emergency Plan and Emergency Plan Implementing Procedures /

4.1.2 . Classify the emergency, condition upon recognition that emergency action levels have been exceeded /

(' Note: Attachment I offers a matrix of initiating conditions for rapid initial classification.

For detailed descriptions of emergency action levels ~ refer to-Section 3.0 of EPIP-2, EPIP-3, EP.IP-4.or EPIP-5, as appropriate

'4.1.3 Assume.the duties of the Emerge'ncy Director until properly relieved /

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CLASSIFICATION OF EMERGENCY CONDITIONS 1 11/3/81 Time / Initials 4.2 The Emergency Director shall refer to the appropriate procedure listed below to find actions required.for each classified event:

4.2.1 EPIP-2, Unusual Event l 4.2.2 EPIP-3, Alert 4.2.3 EPIP-4, Site Emergency i

4.2.4 EPIP-5, General Emergency i

5.0 FINAL CONDITIONS l

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l Subject- Prec . .' No. I EPIP-1 Page1 of 5 Pages CLASSIFICATION OF EMERGENCY CONDITIONS Revmi:- No. Dato 1 11/3/81 MATRIX OF EMERGENCY ACTION LEVELS FOR EMERGENCY CLASSIFICATION I ATTACHMENT 1 EPIP-1 PARAMETER INITIATING CONDITION UNUSUAL JITE GENERAL EVENT ALERT EMERGENCY EMERGENCY

EPIP-2 EPIP-3 EPIP-4 EPIP-5 'e Radiological !

Effluent Release Rate

. Gaseous Tech Spec. Tech Spec. . > SmRem/hr > 50 mrem /hr Limits Limits for 1/2 hr Whole Body -

Exceeded Exceeded by a Whole Body > 250 mrem /hr factor of 10- ' > 25 mrem /hr Child Thyroid Child Thyroid Liquid 10CFR20

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Appendix B, Column 2 ---------

limits exceeded j in discharge canal l I ' l

.0ffsitet00ses

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Whole ----------- > 10mR em - > 50 mrem > 100 mrem-

, Body Ch il.d -----------

> 50mR~em > 2 50rnR em > 500 mRa:.

Thyroid RCS Pressure >ll10.PSIG >l239 PSIG >l375 PSIG ----------

4 RCS , .

Leakage. (Into '

Primary Con- '

tainment) ,

i Unidenti- >5 gpm >

fled leak' rate ' !.

i Total J m >25 gpm >50 gpm >100 gpm :

rate 1 CR0 pump ----------

capacity is l

(,i exceeded

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. EPIP-1 CLASSY '/ICATION OF EMERGENCY CONDITIONS Re m:- No. Date ' '

i 11/3/81 I

i MATRIX OF INITIATI'NG CONDITIONS FOR EMERGENC'Y CLASSIFICATION ATTACHMENT-1 EPIP-1 i

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PARAMETER INITIATING CONDITION EPIP-2 EPIP-3 EPIP-4 EPIP-5 UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY RCS Il31 > 8.0 uCi/cc >300 uCi/cc Indication of Activity fuel cladding i degradation. ----------i Loss of g coolable ,

geometry !

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,' Off-Gas Monitor > 0.5 Ci/sec > l.49 Ci/sec Reading and and/or an Fuel cladding Fuel Status increase of failure ----------- ---------

0.1 C1/sec in 30 min

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le RCS Safety / Valve does not Main Steam Lne Main Steam l Relief Valve close ' Break inside Line Break

Status Containment outside g

>.10 gpm leak Containment .

w/o isolation I Reactor ^ Valid safety Failure'to- 1. LOC w/ i Protection circuit trip or initiate and ----------

failure of '

Systems Manual complete a ECCS to per--

Initiation " scram". Reactor form leadingi resulting in ECCS Activation r,emains critical to core melti down or decra-dation ~l

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2. Transient plus failure of requisitel core shutdows systems could N

lead to melty down with '!

containment'j failure ,

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EPIP-1 CLASSIFICATION OF EMERGENCY CONDITIONS Revt ;cn No. Date .

, 11/3/81 i.

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION ATTACHMENT 1 EPIP-1 j i

PARAMETER INITIATING CONDITION i i

EPIP-2 EPIP-3 EPIP-4 EPIo-5 I i

UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERCENCY f Loss of Tech. Spec. 1. Loss of 1.Uncontroll- 1. Shutdown Containment requires functions able occurs but-Integrity or shutdown necessary to' decrease in decav beat Engineered bring the fuel pool removal capa-Safety. Features plant to cold water to . ~bility is lost.

shutdown- below' level- Core dearada-

2. Loss of of fuel tion or melt' Annunciators 2. Damage to could occur.

in Control spent fuel

( Room for during 2. Transient [

i < 15 min. refueling occurs in I

3. Evacuation 3. Loss of coniunction i of Control functions with failure Room, Control necessary to of core shutd at local . -

achieve hot .down. systems.

station'within stendby. Core meltdown 15 minutes 4. Loss of and contain-

- Annunciators ment failure' in Control likely.

Room > l5 min.

5. Control at local ., ,

stations not established !

within 15 min. -

Toxic or No habitability. Habitability En'te rs ' Vital-flammable gas problems- problems but no ' Area and i release - near vital area restricts ---------

or onsite effects or , necessary restriction of access '

access .

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Page 4 of 5 Pages .

EPIP-1 CLASSIFICATION OF EMERGENCY CONDITIONS Revisic., No. Date 1 -11/3/81 I

i MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION ATTACHMENT 1 EPIP-1 l PARAMETER INITIATING CONDITION .

EPIP-2 EPIP-3 EPIP-4 EPIP-5 UNUSUAL SIJE GENERAL EVENT ALERT EMERGENCY EMERGENCY

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Security Security threat, Ongoing Imminent loss Loss of Compromise attempted entry compromise. No of physical physical or sabotage imminent loss of control of control of physical control plant olant occurs of clant _ _ , _

Loss of Power Of.fsite Pow'r e or/Offsite and 'Offsite and onsite power but onsite power Onsite or not both or vital D.C. Vital D.C.

power for exceeds 15 min !

k' <l5 min j Natural 1. Windspeed 1. Windspeed 1. Windspeed Phenomena > 75. mph > 100 - mph > 125 mph

2. Flood level 2. Flood level 2. Flood level

- <1desig'n level near design ' > de' s ign level -------- --

with probable level 3. Earthquake l flooding'of. 3. Tornado' > SSE levels "

evacuation strikes vital 0.22 g. ,

routes. olant structures Fire Fire not under Af.fecting plant Affecting safety I' control within safety systems systems required ' -------- '

l' 10 minutes. not required for shutdown No safety .for' shutdown ~

systems affected i Explosion .

.No Damage to.

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~.Affecting Aff3cti.ng within Security facility facility .

sa ety systems Protected Area affecting dperations but required for ----------

operations not safety shutdown systems required l for shutdown -

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Prce: .u a No.

_7 Page , of _ Pages l CLASSIFICATION OF EMERGENCY CONDITIONS Revu -- 4o. ,

Date 11/3/81 MATRIX OF INITIATING 'ONDITIONS FOR EMERGENCY CLASSIFICATION ATTACHMENT 1 EPIP-1 PARAMETER INITIATING CONDITION EPIP-2 EPIP-3 EPIP-4 EPIP-5 ,

UNUSUAL SITE GENERAL EVENT ALERT EHERGENCY EMERGENCY 3 Contaminated Requires h Injury transportation -g to offsite ---------- -----------

1, hosoital !

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-no Airc t Crash Onsite Strikes Station Affecting vital station str.cture- .

structures'by structures No damage to impact or fire affected vital instrument !

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Turbine Rotating Casing l

i component I Failure cenetration failure with ---------- ---------- i no casing .

cenetration !

Plant' Status Requiring -

Warrants . Warrhntsi Any event F or conditions increased _ activation activation of potentially '

as evaluated awareness of' of TSC, 0SC- Emerg.Ctrs, damaging the i by GSS plant operations ' Monitoring plant ,

! Teams, and resulting in 4 -

precautionary core public notice _ degradation .

or loss.of clant control t

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Procecure No.

4 . . . . ..~ [ Date issued Effective Date i

. Jersey Central 2/23/81 n/12/st - u/22/s1 '

Date

Power & Light Company Revision No.

1 11/3/81

Subject:

Authonzed By UNUSUAL EVENT Director Oyster Creek Operations

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j . //OysterCreekNuclearGneratingStation ,

, If Date Revision "t:,har List of Effective Paces 1

1 11/3/81

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2 11/3/81 1

3 11/3/81 11/3/81 1 4

1 1 5 11/3/81 11/3/81 1 6 -

i 1 7 11/3/81 1

8 11/3/81 1

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l 10 11/3/81 1

11 11/3/81 1

11/3/81 i

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14 11/3/81 l

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$ Attachments l

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) Attachment 1 (2 pages) 11/3/81 1

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! Attachnent 2 (1 page) 11/3/81 1

Attachnent 3 (4 pages) 11/3/81 1

Attachmnt 4 (1 page) 11/3/81 i

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EPIP-2 lPage 2 c: 14 ;.

UNUSUAL EVENT ' Revision No. Date 1 11/3/81 1.0 PURPOSE ,

1.1 The purpose of this procedure is to define the conditions that shall be regarded as an Unusual Event for Oyster Creek Nuclear Station and to:

1.1.1 Ensur's 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 to initiate appropriate emergency actions.

l.2' The' Emergency Director is responsible'for im'plementing this procedure. .

(- 1.3 Emergency Director responsibilities that may NOT.be delegated include:

1,.3.1 Decision to notify offsit'e emergency management agencies.

- l ' .3 . 2.- Making protective action recommendations-as necessary.to offsite emergency management agencies.

1.3.3 Classification o'f Emergency Event.

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1.3.4 Determining the necessity for onsite evacuation based upon potential exposure to non-essential personnel.

1.3.5 Authorization for emergency workers to exceed 10-CFR 20 radiation exposure l'imit's.

2 .' O ATTACHMENTS' 2.1 Attachment 1, Communicator's Checklist 2.2 Attachment 2, Initial Notification Message 2.3 Attachment 3, Additional.Information Message I

2.4 Attachment 4, INPO/ANI Notification Message

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EPIP-2 Paga 3 of 14 Pages UNUSUAL g a Rev:d , No. ,

Date 1 11/3/81 j

3.0 Emercency Pction Invels ;

i PARAMP ml INITIATING COtOITION le2L s c 3.1 RNASE.EYN TEDNIC'AL dm LnCATION LIMIT INDICATIONS OR AUM1S ON PROCESS OR EFFIDENT EPIP 1 KNflORS NCTf EUNCTIONAL IN CONTROL ROOM 'IO AN EPIP-9 -

EXTE27f te.UJ11uNG PIANT SHUIDOWN OR OTHER SIG- EPIP-10 l

NIFICANP IDSS OF ASSESSMENT OR cot +1DNICATIONS EPIP-ll CAPABILITY EPIP-16 .

t RADIOACTIVE EPIP-19 EFFIDENTS o PIANT STACK EFFIDENTS EPIP-21

.The maxinun release rate of gross activity EPIP 29 except iodine and particulates with half lives longer than eight days shall be limi-tad in accordance with the follow 2.ng equa- ,

tion: 0 = 0.21s- where Q is the stack . j release rate (Ci/sec) of gross activity !

I and E is the average gama energy per ,

j disintegration (Mev/ dis) .

r Note: IF THE READING EXCEEDS 10 TIMES THE ABOVE LIMIT, Pfu.22u 'IO THE ALERf a CLASSIFICATION EPIP-3. .

The maximum release rate of io' dine and.

particulates with half lives longer than-

' eight days shall not excee14 tCi/sec. .

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Note: IF THE RELEASE RATE OF IODINES AND t PARTICUIATES EXr'Fm 40 uC/i/sec, PROCEED 'IO THE ALERI CIASSIFICATION i

EPIP-3. !

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EPIP-2 Page 4 of 14 Pages UNUSUAL EVENT Rev v. :7. , Date 1]/3/81 PARAMETER INITIATING CONDITION REFERENCE i Note: Indication of this value is obtained from evaluation of i

filters in stack gas discharge lI system.

i o The release of radioactive liquid effluents shall be limited such that that the concentrations of radionuclides in the discharge canal at the site boundary shall not at any time exceed the concentrations given in Appendix B, Column 2 of 10CFR20 and notes 1-5 i- thereto. .

3.2 EXCEEDS 1110 PSIG A OR IF REACTOR PRESSURE EXCEEDS'1239 PSIG, EPIP 1

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EPIP 29

-PROCEED TO THE ALERT CLASSIFICATION EPIP-3.

3 '. '3 EXCEEDSLCO o Uni ~dentified' leak-in. containment-exceeds .

REACTOR 5 GPM.

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o Total Leakage into containment from un- EPIP 1 COOLANT SYSTEM identified and identified sources exceed EPIP 29-LEAK .

25.GPM.. -

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Note: IF REACTOR COOLANT LEAK RATE EXCEEDS J

50 GPM, PROCEED'TO THE ALERT CLAS'SI'-

FICATION EPIP-3.

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upilct:, Procedure hu.

- . UNUSUAL EVENT EPIP-2 P34e 5 0:

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R; vision No. I D:au -

I 1 l 11/3/81 PARAMETER IN1TIATING CONDITION REFERENCE !

i 3.4 EXCEEDS LCO l

o For 1-131, 8.0 uCi/cc .

REACTOR ,

EPIP -

Note: IF REACTOR COOLANT SYSTEM l-131 EPIP 29 COOLANT '

ACTIVITY EXCEEDS 300 uCi/cc, OR SYSTEM OFF-GAS AIR EJECTORS INDICATE ;

ACTIVITY GREATER THAN 1.49 Ci/Sec CORRES- !

PONDING TO A READING OF 10,000 f mr/hr, PROCEED TO THE ALERT CLASS- {

IFICATION EPIP-3.

I 3.5 FAILURE TO CLOSE RCS SAFETY /

RELIEF EPIP 1 l

( VALVE EPIP 29 i FAILURE

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1 OFF-GAS MONITORS INDICATE GREATER THAN. 500,000 3 .' 6 UCI/SEC-l Corresponding indication cf this value on FUEL any -gas monitor will equate to 3,330 l CLADDING DEGRADA-

"!'* p g TION ,

OFF-GAS MONITOR INCREASE BY GREATER THAN 100,000

'UCI/SEC'WITHIN THIRTY' MINUTES o Corre'spon' ding indication of this'.value on any off-gas monitor will equate to 666 .

' mrem /hr, t

Note: IF OFF-GAS MONITORS INDICATE GREATER

, THAN 1.49 CI/SEC CORRESPONDING TO A j

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UNUSUAL EVENT ' Revision No. Outu l 1

. 11/3/81 '

PARAMETER INITIATING CONDITION REFERENCE _

READING OF 10,000 MR/HR OR l-131 ACTIVITY EXCEEDS 300 UCI/CC, PROCEED TO THE ALERT CLASSIFICA-TION EPIP-3.

3.7 VALID SAFETY CIRCUIT TRIP OR NECESSARY FANUAL INITIATION INITIATION EPIP l-OF ECCS ., EPIP 29 3.8 REQUIRES SHUTDOWN BY TECHNICAL SPECIFICATIONS LOSS OF o Primary containment integrity shall be main- EPIP 1 CONTAINMENT tained at all times when the reactor is crit- EPIP 9 INTEGRITY ical or when temperature is.above 212* F and EPIP 10 fuel is in the reactor, eiccept'wiiile p'e'rform- EPIP'll' ing low power physic's tests at atmospheric EPIP'29

. pressure during or after refueling.at power levels not to exceed 5 MWt.

3 . 9. _ REQUIRING SHUTDOWN BY TECHNICAL SPECIFICATIONS LOSS OF -

-ENGINEERING EPIP 1 SAFETY EPIP 29 FEATURES l ( .

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. UNUSUAL E31ENT Revision No. Uate 1 11/3/81 _

PARAMETER INITIATING CONDITION REFERENCE 3.10 NEAR OR ONSITE TOXIC OR FLAMMABLE GAS RELEASE EPIP 1 TOXIC OR Note: IF TOXIC OR FLAMMABLE GAS ENTERS EPIP 7 FLAMMABLE THE FACILITY kb1D PRESENT HABABIL- fp f7 GAS , ITY PROBLEMS, PROCEED TO THE ALERT EPIP-14

' CLASSIFICATION EPIP-3.

- EPIP 29 3.ll- SECURITY THREAT OR ATTEMPTED ENTRY OR SABOTAGE EPIP 1 SECURITY ' Note: IF THE SECURITY COMPROMISE IS ON- EPIP 12 COMPROMISE '

GOING, PROCEED TO THE ALERT CLASS- EPIP 22 IFICATION EPIP-3. EPIP 29 C

3.12 UPON OCCURRENCE OF LOSS OF OFFSITE POWER LOSS.OF Note: . TEMPORARY LOSS OF'OFFSITE AND EPIP.1 POWER ONSITE POWER SUPPLIES, PROCEED TO- EPIP 29 THE ALERT. CLASSIFICATION EPIP-3.

LOSS OF ONSITE POWER CAPABILITY Note: TEMPORARY LOSS ~~OF OFFSITE AND

,ONSITE POWER, SUPPLIES, PROCEED:

.TO. ALERT CLASSIFICATION EPIP-3 -

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- . bicc8: 8G 14 i EPIP-2 (P"'B r

Revision No. Cate UNUSUAL EVENT . 11/3/81 , meea PARAMETER INITIATING CONDITION REFERENCE _,

3.13 TORNADO / STORM EPIP 1 o Warning, probable impact on plant EPIP 7 EPIP 12 o e: Warning will be. received from JCP&L EPIP 14 NATURAL

. System Dispatcher, Morristown, N. J. EPIP PHENOMENA EPIP 21 EPIP 22 o Winds in excess of 75 mph pp Note: IF WIND-3 PEED EXCEEDS 125 MPH, PROCEED TO THE ALERT CLASSIFICATION EPIP-3.

FLdOD

~o Warning,. probable-impact, closure of evacuation routes.

- Note: IF WATER LEVEL IS NEAR DESIGN LEVEL, PROCEED TO THE ALERT CLASSIFICATION EPIP-3 3.14 FIRE NOT UNDER CONTROL IN 10 MINUTES EPIP 1 EPIP 7' Note: FIRE POTENTIALLY AFFECTING SAFETY EPIP 8 SYSTEMS, PROCEED TO THE ALERT EPIP 12 FIRE CLASSIFICATION EPIP-3. EPIP 14 EPIP 21 s

EPIP 22 EPIP 29 -

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I Procedure .40. )

3cajrct:

""'I' 9 "' 14 ' '

EPIP-2 -

UNUSUAL EVENT Revision No. l U.itu 1 11/3/81 PARAMETER INITIATING CONDITION REFERENCE i

3.15 WITHIN SECURITY PROTECTED AREA, NO SIGNI- EPIP 1 !

FICANT EFFECT - E .

EXPLOSION EPIP 12 E

Note: KNOWN DAMAGE TO FACILITY AFFECT- EI ING OPERATION, PROCEED TO ALERT EPIP 22 EPIP 29

~

CLASSIFICATION EPIP-3. ,

t 3.16 TRANSPORTATION OF INJURED CONTAMINATED EPIP 1 '!

INDIVIDUAL (S) TO OFFSITE HOSPITAL ff8 EPIP 12 ,

CONTAMIN- -

EPIP 14 i ATED INJURY EPIP 21 EPIP 22 EPIP 29 3.17 AIRCRAFT CRASH ONSITE EPIP 1 ;

EPIP 7 ;

EPIP 8 AIRCRAFT ' o't e :

N IF AN AIRCRAFT OR' MIS'SILE STRIKES EPIP 12 CRASH

^ '

EI 21 j.-

ALERT CLASSIFICATION EPIP-3 EPIP 22 ,

EPIP 29 .

1 T

4 3.18 TURBINE ROTATING COMPONENT FAILURE CAUSING RAPID' PLANT SHUTDOWN EPIP-1 TURBINE EPIP 29 FAILURE Note: TURBINE FAILURE CAUSING CASING PENETRATION, PROCEED WITH ALERT ,

CLASSIFICATION EPIP-3. i I

\-

m

Subj:ct: Procedure No.

EPIP-2 Page 100f 14 P"'"

UNUSUAL EVENT Revision No. Date 1 11/3/81 l

PARAMETER INITIATING CONDITION REFERENCE 3.19 OTHER PLANT CONDITIONS EXIST THAT WARRANT INCREASED AWARENESS ON THE PART OF STATE EPIP 1 AND/OR LOCAL OFFSITE AUTHORITIES OR REQUIRE EPIP 29 p

~

STATUS OR CONDITIONS OR IWOM OTHER M MN CM-OW.

AS EVALU-ATED BY GSS 1

e h

8 S

. Subjscus Procedure No.

Page 11 of 14 Pag.

EPIP--2 ~

UNUSUAL EVEtTT Revision No. Date 1 11/3/81 4.0 EMERGENCY ACTIONS Note: Record time and initials or N/A (not applicable) after completing each task. . TIME / INITIALS 4 4.1 Upon recognition that any of the, emergency action levels have been exceeded the Gt' cup Shift Super-visor shall assume the duties of the Emergency Director. /

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

- i 4 c3 Announce (or have announced) the following [

message over the public address system:

ATTENTION ALL PERSONNEL,. ATTENTION ALL

( PERSONNEL:

EVENT CONDITION.

THE PLANT'IS IN AN UNUSUAL PERSONNEL SHOULD CONTINUE WITH THEIR NORMAL DUTIES UNLESS FURTHER INSTRUCTION IS GIVEN /

(Repeat the~ announcement) 4.4 - Announce to Con' trol Room personnel t' hat has as'sumed.the duties of (name)

Emergency Director. /

4 . 5- Assign"a- Commtinicator to make ' notifications to' -

p'e'rs.ons and' agencies' li'sted"in ' Attachment l . /

(.

qPE .

1 .

i~*

Subject:

Procadura No.

EPIP-2 Page 12 of 14 Pag ..

UNUSUAL EVENT Revision No. Date 1 11/3/81 4.6 Complete Attachment 2 " Initial Notification Message" and give it to the Communicator for

transmission. /

l.

'4. 7 If changes in onsite or offsite radiation *

] levels are, expected:

1 i .

i

'4.7.1 Initiate and continue offsite dose i

projections in accordance with EPIP-9 / ;

1 4.7.2 Initiate onsite and.offsite radio- l i logical surveys in accordance with '

i . .

EPIP-10'and EPIP-ll. '

/

I 4.8 :If. fire.is involved initiate'EPIP-8 <

/- !

i 4.9 Complete Attachment 3 " Additional Information

.{ Message" and give it to the Communicator for transmission to the following agencies: 1,

.! Nuclear Regulatory Commission

<New Jersey: State ~ Police-i ,

e i

t 4

-- , . ~

}

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QP .

, - . _ y _ __.y- _,

__9%_ -_

i .

Procedura No.

Jubjtet EPIP-2 Page 13 of 14 Pagu gggggAL g Revision No. Date 1 11/3/81

/

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

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

4.12 Complete Attachment 4 "INPO 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 i" no further emergency actions are required.

,(Instruct Communicator to notify all agencies originally notified and notify

~

- pla'nt personnel via the Public' Address System). /

4.13.2 If recovery conditions have been met, initiate the Recovery Phase in accord- .

ance with EPIP-29. / ,

.- s. .

. 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),. Site

! Emergency (EPIP-4), or General Emer-gency -(EPIP-5).

/..

'5.0 FINAL CONDITIONS ,

5.1 The Unusual Event has been' terminated since no further actions are required. /

5.2 Recovery operations have been initiated per EPIP-29. /

_ 'QP e

,. Prcsr /..a No. i i ct EPIP-2 Pag 2 14 of 14 Pages '

UNUSUAL EVENT Rev:s . No. ,

Date ,

l 1 11/3/81 .

I 5.3 A higher class of event has been declared in accordance with: j i

5.3.1 Alert EPIP-3 / .'

5.3.2 Site Emergency EPIP-4 / !

5.3.3 General Emergency EPIP-5 /

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Subj ct: Procedure No.

EPIP-2 Page 1 or 2 Nb""

UNUSUAL EVENT Revision No. lDate ]

1 11/3/81 l 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 /

5. Notify the New Jersey State Police within 15 minutes of classification Use Attachment 2 Format Primary: State Hot Line Alternate: (609) 882-4200 /

6. Notify the United States Nuclear Regulatory Commission Operations Center

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

Alternate: (1) Commercial vir. Bethesda (301)-492-8111 (2), Commercial via Silver Spring (301) 427-4056 (3) NRC-HPN Line - Dial 22 or *22 (Touch-tone)

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

Note: Open-line communication with NRC is to be maintained on ENS Line throughout the emergency situation.

ATTACHMENT 1

. I

Prc: ; . , - No.

' L " J "J ' I ' Pages i

EPIP-2 Page 2 of 2 j UNUSUAL EVENT Re- .~ to. Date i

1 11/3/81 --_

e

7. Notify the agencies directed by the Emergency Director using Attachment 3 Format. /

8, Notify the following agencies using Attachment I 4 Format t

Institute of Nuclear Power Operations !

Tel:- (404) 953-0904 - /

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

( l i

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( i

. ATTACHMENT 1 .,

e

'Subj;ct:

Proc 3duro No.

E P T P ,, Page of , % es Unusual Event 3 Revision No. Date i l 11/3/81 l 1

I INITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERCISE, THE MESSAGE WILL BEGIN AND END WITH THE PHRASE, "THIS IS A "

. EXAMPLES:

"THIS 15 -A ORILL." "

THIS IS A COMMUNICATIONS TEST." "THIS IS AN EXERCISE." "THIS 'IS NOT AN EXERCISE -. I REPEAT _- THIS IS NOT AN EXERCISE."

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATION THIS IS A NOTIFICATION OF AN UNUSUAL EVENT EMERGENCY CLASSIFICATION.

THE EVENT OCCURRED AT. , ON (Time - 24 hr. Clock) (Date)

O THERE IS NO RELEASE.IN PROGRESS.

O WE HAVE A CONTROLLED RELEASE IN PROGRESS.

WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS.

{ ____ O _________________________________________________________________________

O NO Piu.au;nVE ACTIONS ARE RECOMMENDED.

~

_/__7 WE RECOMMEND SHELTERING FOR THE FOLLOWING DIRECTIONAL' SECTOR (S)

O WE RECOMMENO EVACUATION FOR.THE FOLLOWING OI'RECTIONAL SECTOR (S)

APPROVED EMERGENCY DIRECTOR DATE (Time _24 hr)

THIS MESSAGE HAS BEEN TRANSMITTED.TO:

TIME COMPLETED C NEW -JERSEY . STATE POLICE ,

O

~

I UNITED STATES NUCLEAR. REGULATORY COMMISSION DATE COMMUNICATOR l l

ATTACHMENT 2 l l

k 4

Subj:ct: Procidura No.

Page of ea r .

Unusual Event co7" ? '

Revision No. Date 1 11/3/81 ADDITIONAL INFORMATION MESSAGE Check ( ) all appropriate information DATE TIME

1. This is acting under the' Direction of the Emergency

, (Emergency Director)

Director at Oyster Creek Nuclear Generating Station. The fol' lowing is pr'ovided as additional information for the initial notification of the (circle one) Unusual event; Alert; Site Emeroency; General Emeroency.

(

-2. DATE/ TIME OF CLASSIFICATION

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

Month- ' Day Year

'b. Date:

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

4. Plant Status

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

l k- ATTACHMENT 3 1

l

i Subj ct: Procrdura No.

Page2 0' P " b '"'

Unusual Event EPIP-2 A Revision No. Date 1 11/3/81 ,

l

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.

'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 estim'ated duration of release:

8. Liquid Radiological Date

a. Release concentration uCi/cc

b. Release rate UCi/sec

c. ' Release (' circle one) h a s /h a d ' n ot t'e rmin a t ed

~

. d. Actua'l or estimated duration o'f r'elease

e. ' Estimated ~ total' release ~ uCi ATTACHMENT 3

(

L .

Proc:duro No.

Subirct: '

Unusual Event coto

9"' "

Revision No. Date 1 11/3/81

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

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

( d. 10 miles UCi/cc mrem

11. Estimate of surface contamination dom /100

.cm2 (catain 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- ,

f. First aid teams onsite

g. Ambulance service

h. Medical support

1. Environmental surveys offsite

(. J. Other, specify

^ TidC;-;W ;;T 3

Procedura No.

' Subj:ct: I #'"

Unusual Event __

EPIP-2 9"4 &

Revision No. Date 1 11/3/81

13. Additional support required (specify)

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

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

, i f

16. The following changes in protective measures are recommended

'forthe!populationin:these. sectors'

a. None

b. Notify (projected offsite dose )

[

c. Take shelter (projected offsite dose )

d. Evacuate (projected offsite dose )

17; Approved (Emergency Director / Emergency Support Director)

(Date) (Time)

18. Transmitted

a. New Jersey State Police

b. . United States Nuclear Regulatory Commission (Communicator)

(Date) (Time)

ATTACHMENT 3 L

5

Subjsct: Procedura No.

EPIP-2 P 8" l f 1 Pay

~~'

UNUSUAL N Revision No. Date l i

, 1 _11/3/81 l l

NOTIFICATION TO: INSTITUTE OF NUCLEAR POWER OP.CPFIOtIS & AMERICAN NUCLEAR INSURERS MESSAGE FORMAT 1.~ This is at (Name/ Title)

Oyster Creek Nuclear Generating Station. We have declared a/an condition at (Event Classification) (Time) ,

2. Description of Emergency: l 1

~

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

(Date) (Time)

~

4. Transmitted:

(Communicator)

(Date) (Time) 1

(- *

< . ATTACHMENT 4

.QP

s O "p'roce::ure No.

{F39e 1 Of j

r'gi[Cj,. . . . - . . . . . .

) EPIP-3 Cate lesued I

Effective Cate 13 _

Jersey Central :-22-n 11/1: ei - n/:: ,. '.

Power & Light Company sevision no. cate O

1 11/3/81

Subject:

Authorized By

~~

ALERP Director Oyster Creek Operations Approval /Co tre

/ _

Project: / / // l

{

gt,ter Creek Nuclear Gu'f/ fating Station J '

lj I List of Effective Pages Date Revision % rber 1 11/3/81 1 2 11/3/81 1 3 11/3/81 1 4 11/3/81 1 l 11/3/81 1 j 5

6 11/3/81 1 '

l 7 11/3/81 1 l

8 11/3/81 1 9 11/3/81 1 ';

10 11/3/81 1 11 11/3/81 1

'N 12 11/3/81 1

'# 13 11/3/81 1 14 11/3/81 1 15 11/3/81 1 !

Attachments l

ttachment 1 (2 pages) 11/3/81 1 Attachment 2 (1 page) 11/3/81 1 Attachment 3 (4 pages) 11/3/81 1 Attachent 4 (1 page) 11/3/81 1 G

I

s

, e .g , , Prc. n No.

EPIP-3 Page 2 OI 15 Page::

i

. ALERT Re. .o.

Date

1 11/3/81 I

l 1.0 PURPOSE i

I .

j 1.1 The purpose of this procedure is to define the conditions that l

shall be regarded as an Alert for Oyster Creek Nuclear Station

and to

l 1.1.1 Ensure necessary actions are taken to protqct i.

the health I I and safety of the public.

l.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 to initiate appropriate emergency actions.

1.2 The Emergency Director is responsible for implementing this procedure.

Is 1.3 Emergency Director responsibilities that may NOT be delegated l include:

1.3.1 Decisiion to notify offsite emergency -management agencies.

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

1.3.3 Classific'ation of Emergency Event. l 1.3.4 Determining the necessity'for onsite evacuation based upon!

I potential exposure to non-essential personnel. i 1.3.5 Authorization for emergency workers to exceed 10 CFR 20 ;

radiation exposure limits. ,

2.0 ATTACHMENTS.

I 2.1 Attachment 1, Communicator's Checklist 2 . 21 Attachment 2, Initial Notification Message , ,

1 1 2.3 Attachment 3, Additional Information Message j f

Attachment 4, INPO/ANI Notification ^Messaga [

l' 2.4 .

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' Prort.._ : No. '

Suta: ::t: EPIP-3 Page 3 of 15 Par;cs -

M Revism ; No.

Date -

I 1 11/3/91 3.0 EMERGENCY ACTION LEVELS PARAMETER INITIATING CONDITIONS , REFERENfE_,

1 RELEASE EXCEEDS 10 TIMES TECHNICAL SPECIFICA- EPIP 1. l 3.1 1

TIONS. EPIP 9 j EPIP 10 l o PLANT STACK EFFLUENTS EPIP U .

The maximum release rate of gross activity EPIP 16 except iodine and particulates with half EP1F 19 lives longer than eight days shall be EPIP 21 RADIOACTIVE limited in accordance with the following EPIP 25 EFFLUENTS equation: Q.=.10 (0.21) -where Q is. the EPIP 26 stack release rate (Ci/sec) of gross EPIP 27 activity and E is the average gamma energy EPIP 28 per disintegration (Mev/ dis). EPIP 29

[

Th'e' maximum release' rate of iodines and -

particulates with half lives longer than eight days shall not exceed 40 uci/sec.

OFFSITE DOSE DUE TO THE EVENT IS PROJECTED TO I

i EXCEED 50 MREM WHOLE BODY OR 250 MREM CHILD THYROID !

s Note: IF THE'OFFSITE. DOSE DUE TO THE EVENT IS PROJECTED TO EXCEED 50 MREM WHOLE BODY OR ;

250 MREM CHILD THYROID, PROCEED TO THE SITE EMERGENCY CLASSIFICATION EIPI-4.

(.,.

-i-

ProccGura N3.

'I u. :t:

Page 4 of 15 Pages EPIP-3 N Revi:: A No. Date f ,

i 1 11/3/81 r

PARAMETER INITIATING CONDITION REFERENCE _ ,

i I

3.2 FUEL HANDLING ACCIDENT OR OTHER EVENT RESULT- EPIP 1 l

i ING IN UNEXPECTED INCREASE OF INPLANT RADIO- EPIP 9 ,

ACTIVITY LEVELS BY A FACTOR OF 10. EPIP 10 RELEASE OR EPIP 11 I

LOSS OF EPIP 19 Note: IF MAJOR DAMAGE.TO SPENT FUEL IN THE gpyp g CONTROL OF TOR CMM OR SPM Fm POOL EPIP 25 RADIOACTIVE OCCURS, OR THM IS M WCOMROMD thru MATERIAL DECREASE IN FUEL POOL WAE R M m TO EPIP 29 WITHIN THE BELOW THE LEVEL OF FUEL; PROCEED TO pg THE SITE EMERGENCY CLASSIFICATION f EPIP-4.

( '

3.3 EXCEEDS 1239 PSIG EPIP 1 EPIP 25 Note: IF REACTOR PRESSURE EXCEEDS THE thru REAC'OR T SAFETY LIMIT OF 1375 PSIG, PROCEED TO EPIP 29 PRESSURE THE SITE EMERGE'NCY CLASSIFICATION EPIP-4. ;

3.4 EXCEEDS 50 GPM EPIP'l

EPIP 25 o As computed from drywell equipment thru REACTOR drain tank readings plus gallons EPIP 29 COOLANT pumped from drywell sump per elapsed ,

SYSTEM time, i LEAK !l i

Note: -IF REACTOR COOLANT SYSTEM LEAK EXCCEDS 100 GPM, PROCEED TO THE SITE EMERGENCY I

CLASSIFICATION EPIP-4.

a l

l

. , . . . . . PTCY ^ : ND.

~~-

,, t' age 5 c 15 Pa9CS N Rev. No. Date 1 11/3/81 l

l PARAMETER INITIATING CONDITION REFERENCE i 3.5 STEAM LINE BREAK WITH SIGNIFICANT, GREATER 1

THAN 10 GPM LEAK RATE, OR MSIV MALFUNCTION EPIP 1 E 10 LINE BREAK Note: IF THERE IS A MAIN STEAM LINE BREAK EPIP ll E

OUTSIDE OF CONTAINMENT WITHOUT ISO- E 9 ,

LATION, PROCEED TO THE-SITE EMERGENCY EPIP 21 CLASSIFICATION EPIP-4.

EPIP 2')

(

3.6 RCS 1-131 ACTIVITY GREATER THAN 300 uCi/cc i

REACTOR o Determined from plant chemistry samples EPIP 1 COOLANT

( SYSTEM EPIP 25 ACTIVITY OFF-GAS AIR EJECTOR MONITORS INDICATE GREATER thru THAN 1.49 Ci/sec. EPIP 29 FUEL ,

CLADDING .

DEGRADA- o Corresponding indication of this value i TION '~

on any off-gas air ejector monitor will equate to 10,000 mr/hr.

Note: IF DEGRADATIO'.4 OF THE CORE OCCURS , OR THERE.IS POSGIBLE LOSS OF COOLAELE -

GEOMETRY, PROCEED TO THE SITE' EMERGENCY CLASSIFICATION'EPIP-4.

3.7' REACTOR NOT SUBCRITICAL AFTER VALID SCRAM EPIP 1 '

SIGNAL FAILURE EPIP'25 OF A thru REACTOR EPIP 29. ,

g PROTECTION 1 SYSTEM TO ,

I l INITIATE &

COMPLETE A ~

M l

--SCRAM l 1

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Prc r : No.

Page 6 Of 15 Pa p

{~~' EPIP.--3 Date ALERT Re . .. lo.

1* 11/3/81 PARAMETER INITIATING CONDITION REFERENCE i

I 3.8 LOSS OF FUNCTIONS NEEDED TO ACHIEVE PLANT e COLD SHUTDOWN s

i LOSS OF o Cold shutdou.t mode switch in shutdown PLANT mode position, fuel in the reactor CONTROL vessel, all operable control rods are fully inserted, and the reactor cool- EPIP 1 ant system maintained at less than 212 EPIP 25 F and vented. thru EPIP 29 Note: IF LOSS OF FUNCTIONS NEEDED TO ACHIEVE HOT STANDBY OCCUR, PROCEED TO THE SITE EMERGENCY CLASSIFICATION EPIP-4.

e

(.

3.9 LOSS OF ALL CONTROL ROOM ALARMS (ANNUNCIATOR)

LOSS OF 'o Occurs on loss-of 125 VDC EPIP 1 ANNUNCI- EPIP 25 t

~

ATORS OR Note: LOSS OF'ALL CONTROL ROOM ALARMS .thru )

ALARMS (ANNUNCIATORS) GREATER THAN 15 MINUTES EPIP 29 ,

OCCURS WITH PLANT NOT IN COLD SHUTDOWN,

~

PROCEED TO THE SITE EMERGENCY,CLASSI-FICATION EPIP-4.

I f

kt r.' i "5 '

~

Prc _ ' No.

t- u Page 7 of 15 Pages EPIP-3 l ';o.

Reut '

Date 1 11/3/81 REFERENCE PARAMETER INITIATING CONDITION i

EPIP 1 3.10 REQUIRED OR ANTICIPATED WITH CONTROL OF

,4 SHUTDOWN SYSTEMS ESTABLISHED AT LOCAL EPIP 15 STATIONS EPIP 25 ,

CONTROL thru EPIP 29 ROOM Note: IF THE CONTROL '100M IS EVACUATED MD REQUIRED SI4UTDON SYSTEM CON- f EVACUATION TROL AT LOCAL STATIONS IS NOT ESTABLISHED WITHIN 15 MINUTES, PROCEED TO THE SITE EMERGENCY '

CLASSIFICATION EPIP-4.

ENTERS FACILITY, PRESENTS HABITABILITY EPIP 1 3.11 EPIP 7 PROBLEMS EPIP 8 EPIP 12 TOXIC OR ,

FLAMMABLE Note: IF TOXIC OR FLAMMABLE GAS ENTERS fP 5

{ ^ EPIP 22 GAS ACCESS, PROCEED TO THE SITE EMERGENCY EPIP 25 CLASSIFICATION EPIP-4. thru .

EPIP 29

( .

i 3.12 ONGOING SECURITY COMPROMISE EPIP 1 E

Note: IF THERE IS IMMINENT LOSS OF PHYSICAL E P 2 CONTROL OF THE PLANT, PROCEED TO THE E SITE EMERGENCY CLASSIFICATION.EPIP-4.

EPIP 29 COMPROMISE * !

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-- - -_ . _ _ )

,1

Proccc c : No.

L.3 pot: Page 8 of 15 Pages EPIP-3 ALERP Revis;on No. ,

Date 1 11/V81 PARAMETER INITIATING CONDITION REFERENCE

! 3.13 TEMPORARY LOSS OF BOTH I

I f LOSS OF Note: IF TEMPORARY LOSS OF OFFSITE POWER OFFSITE AND ONSITE POWER SUPPLIES EXCEED 15 .EPIP 1 i l' POWER AND MINUTES, PROCEED TO THE SITE EMERGENCY EPIP 25 l LOSS OF CLASSIFICATION EPIP-4. thru ONSITE- EPIP 29 POWER SUPPLIES o

3.14 LOSS OF VITAL DC POWER EPIP'1

(

VITAL DC Note: IF LOSS OF DC POWER FOR MORE THAN 15 EPIP 25 POWER MINUTES OCCURS, PROCEED TO THE SITE thru EMERGENCY CLASSIFICATION EPIP-4. EPIP 29

- EPIP 1 3.15 TORNADO EPIP 7-EPIP 12 i o Strikes. vital plant strt.ctures EPIP 20' STORM- .

EPIP 22 NATURAL -

EPIP 25 PHENOMENA o Winds near design level, greater than EP P 29 100 mph.. '

Note: IF WIND SPEED EXCEEDS 125 MILES PER ,

HOUR, PROCEED TO THE SITE. EMERGENCY f CLASSIFICATION EPIP-4. - '

'A .

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)

Prc;-- No.

^~~

EPIP-3 Page 9 of 15 Pagrts i ALERT Revs- !o.

Date 1 11/3fgi l

INITIATING CONDITION REFERENCE j PARAMETER FLOOD o Near design level l

Note: IF WATER LEVEL EXCEEDS DESIGN LEVEL e' OR DAMAGES VITAL EQUIPMENT, PROCEED l'

j TO THE SITE EMERGENCY CLASSIFICATION ,

EPIP-4.

I 3.16 POTENTIALLY AFFECTING PLANT SAFETY SYSTEMS EPIP 1 EPIP 7' EPIP 8 Note: FIRE AFFECTING SAFETY SYSTEMS EPIP 12 FIRE REQUIRED FOR SHUTDOWN, PROCEED TO IP.2 k SITE EMERGENCY CLASSIFICATION EPIP-4. EPIP 22 EPIP 25 thru EPIP 29 3.17 KNOWN DAMAGE TO FACILITY AFFECTING OPERATIONS EPIP 1 Note: KNOWN DAMAGE TO THE FACILITY AFFECTING b SAFETY SYSTEMS REQUIRED FOR SHUTDOWN, PROCEED TO THE SITE EMERGEUCY CLASSI-

".,P E ~12 FICATION EPIP-4.

EXPLOSION EPIP 22 EPIP 25-thru '

EPIP 29 I

i I .-

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m.+.:.

Procedure No.

Subject:

Page 10 08 15 Pd4*'

EPIP-3 ALERT Revision No. Date 1 11/3/81 PARAMETER INITIATING CONDITION REFERENCE l 3;18 AIRCRAFT OR MISSILE STRIKES A STATION EPIP 1 EPIP 7 STRUCTURE EPIP 8 EPIP 12 EPIP 14 AIRCRAFT Note: IF AN AIRCRAFT OR MISSILE CRASH EPIP 21 EPIP 2 AFFECTS VITAL INSTRUMENTS BY IMPACT pp2 !

OR. FIRE, PROCEED TO THE SITE EMERGEN- thru EPIP 29 CY CLASSIFICATION EPIP-4.

EPIP 1 3.19 TURBINE FAILURE CAUSING CASING PENETRATION EPIP 7 EPIP 9 EPIP 10 EPIP 11 TURBINE EPIP 14 EPIP 21

(*

EPIP 25 thru EPIP 29

-3.20 OTHER PLANT CONDITIONS EXIST THAT. WARRANT ACTIVATION OF THE TECHNICAL SUPPORT CENTER, THE OPERATIONS SUPPORT CENTER, AND THE EPIP-1.

NEARSITE EMERGENCY OPERATIONS FACILITY.

(_

l 4B

Procedme No. .l

' Subiect: EPIP-3 Page 11 W 15 P399_{

Revis.on No. Date ALERP 1 11/3/81 ,

4.0 EMERGENCY ACTIONS Note: Record time and initials or N/A (not applicable) after completing each task.

I Time / Initials 4.1 Upon recognition that any of the above l

Emergency Action levels have been exceeded f

the Group Shift Supervisor shall assume the duties of the Emergency Director. /

i 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 l PERSONNEL: THE PLANT IS IN AN ALERT CON-1 f DITION. ON Srns EMERGENCY RESPONSE PERSONNEL REPORT TO EMERGENCY STATIONS. ALL I

i OTHER PERSONNEL AWAIT FURTHER INSTRUCTIONS.

l l

Repeat Announcement. /'

4.4 Announce to Control Room personnel that has assumed the (Name) l /

[

duties of Emergency Director.

l 4.5 Notify OCNGS Security, Ext. 6954, 6950 and direct them to activate the pagers of the Onsite Emergency Duty Section currently l

on duty (Group 1, 2 or 3) . If during non-normal duty hours, instruct Security to 1

.\.

l

Proceduru No.

--I

Subject:

EPIP-3 Paue 12 or 15 P u;c Revision No. Date N 1 11/3/81 call the home numbers of all members of the Onsite Emergency Duty Section on duty using the auto-dialing phone. /

4.6 Assign a Communicator to make notification to persons and agencies listed in Attach-ment 1. /

4.7 Complete Attachment 2 " Initial Notification Message" and give it to the Communicator for transmission. /

4.8 -Activate the' Operations Support Center (EPIP-27) and Technical Support Center (EPIP-26). /

{

4.9 Initiate Personnel Accountability in accordance with EPIP-12. /

4.10 Initiate and continue offsite dose pro-jection in accordance with EPIP-9. /

4.11 Initiate onsite and offsite radiological surveys in accordance with EPI 9-10 and

~

EPIP-ll /

'/

4.12 If fire is involved initiate EPIP-8 4.13 Complete Attachment 3 " Additional Message Format" and give it to the Communicator for transmission to the following agencies:

(- .

3

l Prococuro No.

micc:. EPIP-3 l i%;e 13 cl 15 T- -

N Revcion No. l Date 1 l 11/3/81 j I

I Nuclear Reculatory Ccmnission l New Jersey State Police 'f s

I

/

I 4.14 As required, initiate damage control activ-

~

ities in accordance with EPIP-14. /

I 4.15 If r ~_-mnl are injured initiate EPIP-7 / l

/. ~

4.16 Ccmplete Attachnent 4, "INPO/ANI Notification Message". and give it to the Comunicator for mr=4 asion. /

J 4.17 If a report of personnel accountability i i

'~

has not been received within 30 minutes, contact Security (Ext. 6954, 6950) for !

a status report. /

4.18 If personnel are unaccountal for, initiate ,

/

Search and Rescue (EPIP'-22) l 4.19 If site evacuation is necessary, activate the Banote Asscubly Area .(EPIP-18) and implenent Site Evacuation (EPIP-13) after ;

l accountability is ccInplete. / j f.

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-- 1 Procedure No.

Subject:

Page 14 of 15 Pa9es EPIP-3

M Revision No. Date

' 1 11/3/81 4.20 Based on assessment of plant conditions:

4.20.1 Terminate the Alert if no further emergency actions are required (in-struct the Communicator to renotify all agencies originally notified and notify plant personnel via the Public

./

Address System. ._

4.20.2 If recovery conditions have been met, initiate the Recovery Phase in ac-cordance with EPIP-29 /

4.20.3 If recovery conditions have not been met but Alert emergency action levels

(-- are no longer being exceeded, de-escalate to an Unusual Event by per-forming notification required by EPIP-2' /

4.20.4 If. emergency action' levels exceed those for an Alert, escalate to the appropriate class in accordance with Site Emergency (EPIP-4) or General Emergency. (EPIP-5). /

5.0 FINAL CONDITIONS 5.1 The Alert has been terminated since no

/

further actions are required 5.2 Recovery Phase has.been initiated in

/

accordance with EPIP-29 __

k D.

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l

. -n.m Proccoute No.

Subject:

EPIP-3 Page 15 or 15 P a g e'.

AIRE Revision No. Date

' 1 11/3/81 _

5.3 A lower class of emergency has been declared by the Emergency Director and EPIP-2 is being implemented /

5.4 A higher class of emergency has been '

declared by the Emergency Director , 4,

' and the following procedure is being i

implemented:

EPIP-4 Site Emergency /

5.4.1 EPIP-5 General Emergency /

5.4.2

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Subj:;ct: Procedure No.

EPIP-3 Page 1 or 2 PJ-

ALERT Revision No. ;Date 1 i 11/3/81 -

COMMUNICATOR'S CHECKLIST - ALERT Time / Initial

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 /

5. Notify the New Jersey State Police within 15 minutes of classification Use Attachment 2 format Primary: State Hot Line Alternate: (609) 882-4200 /

6. Notify the United States Nuclear Regulatory Commission Operations Center

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

1) Commercial via Bethesda (301) 492-8111

2) Commercial via Silver Spring (301) 427-4056-

3) NRC-HPN'Line.- Dial 22 or *22 (Touch-tone)

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

Note: Open-line communication with NRC is to be maintained on ENS Line throughout the emergency situation.

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ATTACHMENT 1 l <

4

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. cu g.c: P7c ~ . m No.

Page 2 CI 2 Pages EPIP-3 l _

R e' " - :o. Date

.l g 11/3/81

' 1 l

7, Notify the agencies directed by the Emergency Time /Lnitials c

a DLnctor using Attachment 3 fcnnat. /

8, Notify the following agencies using Attachmeett 4 fonnat.

l~ s ,

Institute of Nuclear Power Operations s

/

Tel: (404) 953-0904

)

American Nuclear Insurers g /

Tel: (203) 677-7305 __

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Subject:

Procidura No.

9" ' ' "

mm' '

Alert Revision No. Date 1 11/3/81 INITIAL NOTIFICAT ON MESSAGE ,

i IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERCISE, THE MESSAGE WILL BEGIN AND END WITH THE PHRASE, "THIS IS A ." EXAMPLES:

"TH15 15 A DRILL." " THIS IS A COMMUNICAT10N5 TEST." "THIS IS AN EXERCISE." "THIS IS NOT AN EXERCISE __ I REPEAT _- THIS IS NOT AN EXERCISE."

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATION THIS IS A NOTIFICATION OF AN ALERT EMERGENCY CLASSIFICATION.

i THE EVENT OCCURRED AT , ON (Time - 24 hr. Clock) (Date)

O THERE IS NO RELE.ASE IN PR0bRESS.

~ O WE HAVE A CONTROLLED RELEASE IN PROGRESS.

( O WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS.

O NO tmuuxnVE ACTIONS ARE RECOMMENDED.

~

/7 WE R.ECOMMEND SHELTERING FOR THE FOLLOWING OIRECTIONAL SECTOR (S)

O WE RECOMMEND EVACUATION FOR THE FOLLOWING OIRECTIONAL SECTOR (S)

APPROVED EMERGENCY DIRECTOR DATE (Time-24 hr)

THIS MESSAGE HAS BEEN TRANSMIT.TED.TO:

TIME COMPLETED

_/~ 7 NEW .3ERSEY STATE POLICE O UNITED STATES NUCLEAR REGULATORY COMMISSION DATE COMMUNICATOR ATTACHMENT 2

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Subject:

Procedure No.

Alert EPIP-3 Page 1 of 4 Prj Revision No. Date 1 11/3/81 i

i i

ADDITIONAL INFORMATION MESSAGE l

l Check ( ) all appropriate information ,

1 DATE TIME f'

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

(

2. DATE/ TIME OF CLASSIFICATION !

I

a. Time: _

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

' ~

i

b. Date: ' Month Day Year 'l.

3. There (circle one) is/is not. an Emergency Classification ,

change. The classification is: (circle one) Unusual Event; Alert; Site Emergency; General Emergency. l

4. Plant Status l.

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

5 ATTACHMENT 3

w. e

Subjec?: Procedure No.

Alert EPIP-3 Page 2 of 4 Pa u Revision No. Date r' 1 11/3/81 l

i i

i

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

~

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

5. Type of release (circle one) airborne; liquid; 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 I

(-,

b. Iodine 131 release rate uCi/sec j

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

d. . Actual or , estimated du_rati.on of' release:

-i I

8. Liquid Radiological Date

~

a. R'elease concentration uCi/cc 1

b. Release rate UCi/sec i i

c. Re1~ ease (circle one)'has/has not terminated [

~

d. Actual or estimated duration of ' release

~

e. Estimated tota'l release uCi

-ATTACHMENT 3

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Stoject: Procedure No.

Alert EPIP-3 Page 3 of 4 P r. .,

Revision No.

Date

~g 1 11/3/81 j Projected dose rates and integrated dose (Based on actual or

9. _,

projected duration of release) i 4

WHOLE BODY

a. Site Boundary mr/hr mrem

b. 2 miles mr/hr mrem

c. -5 miles mr/hr mrem ,

{

d. 10 miles mr/hr _ mrem

10. Projected '.odine Concentration and Integrated Dose Commitment (Based on actual ar projected duration of release) .

THYROID

a. Site. Boundary uC1/cc , mrem

b. 2 miles UCi/cc mrem'

c. 5 miles uCi/cc mrem i C- d. 10 miles uCi/cc , mrem ,

11. Estimate of surface contamination dom /100 I t

cm 2 (.obtain._ from field data) mrem /hr ;

t

12. Emergency Actions in progress: ;

l

a. Radiological survey teams onsite

b. Radiological survey teams offsite ;

c. Onsite fire brigade l

. 4-

d. Offsite fire department

e. Damage Control

f. First. aid teams onsite

.g . _ Ambulance serv. ice

h. Medical support

.i. Environmental surveys offsite

\- Other, specify J.

ATTACnMENT 3

~

Subject:

Procidura No.

Alert EPIP-3 Page 4 o' 4 Pay Revision No. Date 1 11/3/81 7 _

i i

~

i

13. Additional support required (specify)

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

, Alert; Site Emeroency; General Emeroency

15. Offsite pd ulation sector ('s) (refer tb Emergency olanning Zone !

Sector map) affected are ,

f

16. The following changes in protective measures are recommended for the populatior; in these ~ sectors

l a. None r b. Notify (projected offsite dose ) !

L. l

c. Take shelter (projected offsite dose ) ,

I I

d. . Evacuate.(projected offsite dose )

8 . t 17.- ' Approved (Emergency Director / Emergency Support Director) l (Date) (Time) ,

18. Transmitted ,

a'. N'ew Jersey 'S' tate ' P'o ' lice -

b. United States Nuclear Regulatory Commission (Communicator)

(Date). (Time) ,

! . l ATTACHMENT 3

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Subject:

Proc; dura No.

l Alert EPIP-3 Page 1 of 1 Pag Revision No. ' Date

r~

l 11/3/81 ;

i !'

NOTIFICATION TO: INSTITUTE OF NUCLEAR POWER OPERATIONS

& AMERICAN NUCLEAR INSURERS .

t P

MESSAGE FORMAT

l. This is ~ at (Name/ Title)

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

! condition at l -(Event Classification) (Time) e f

2. Description of Emergency:

i ;

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(-. .'

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

I i

I (Date)- (Time) -

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4. Transmitted: ;

(Communicator) .,

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. (Date) (Time) e ATTACHMENT 4

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> :- . . . . . . _ . _ . I'so< res w e N o

.--. ;_- ji ^89" l '# 13 EPIP-4

'if._.,,- 1 q tp:// V^ 4'"g) 8 i

.' E!!ective D.H'-

UN' =="O Date ist,ueo Jersey Central 2/23/81 lin:/ei - 11nust Date

'- O Power & Light company' Revision No.

, 11/3/81 l- _

' U '"C Authonzed By i Site Imergency ~

Director, Oyster Creek Ocerations i j ^

' Approval /C ncurrence m l k

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l P'clect' l.

JDyster ll Creek NucleaV Generatino Station

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, List of Effective Paces Date Revision Number a

i a

1 1 11/3/81 1- -

2 11/3/81 1

3 11/3/81 ,

11/3/81 1 i I 4 ,

11/3/81 1 ?

5 1

i : 6 11/3/81 ,

I 1 I 7 11/3/81 !

it 1

!- 8 11/3/81 ;

11/3/81 1 1

9 l 1

'i 10 11/3/81 f 11/3/81 1 !

11 1

12 11/3/81 11/3/81 1 ,

13 ;

I i.

, Attachments

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i Attachment 1 (2 pages) 11/3/81 1 l 1

! Attachment 2 (1 page) 11/3/81 ,

Attachment 3 (4 pages) 1 11/3/81 I~ 1 Attachment 4 (1 page) 11/3/81 I

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1 ubject:

Proccc L. No.

EPIP-4 i P30 2 O! 13 P C- [

Site Emergency Rwasion No. ,

Oate 1 11/3/81 . -

1.0 PURPOSE 1.1 The purpose of this procedure is to define the conditions i that shall be regarded as a Sit *e Emergency for Oyster Creek l Nuclear Generating Station and to: ,

. i 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 GPU Nuclear management and offsite emergency response organizations.

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

112 The Emergency Director-is responsible for implementing this procedure.

1.3 Emergency Director responsibilities that may NOT be

( delegated include:

1.3.1 Decision to 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.

2.0 ATTACHMENTS.

. s 2.1 Attachment 1, Communic,ations Checklist 2.2 AttachIment 2, Initial-Notification Message 2.3 Attachment 3, Additional Information Message 1

2.4 Attachment 4, INPO/ANI Message

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'. i Procedure No.

Subiect: EPIP-4 Page 3 08 13 Pages Revision No. Date

( Site Emergency 11/3/81 i

f.

Emergency Action Levels 1

3.0 f PARAMETER INITIATING CONDITION REFERENCE 3.1 RELEASE CORRESPONDS TO 5 MREM /HR FOR 1/2 HOUR OR GREATER WHOLE BODY OR 25 MREM /HR TO THE CHILD THYROID MAJOR DAMAGE TO SPENT FUEL IN THE REACTOR CAVITY OR SPENT FUEL POOL.

EPIP-1 EPIP 9 RADIOACTIVE - EPIP 10

( EFFLUENTS EPIP 11 EPIP 12 EPIP 13 OFFSITE' DOSE DUE TO-THE EVENT IS EPIP 16 PROJECTED TO EXCEED 50 MREM WHOLE EPIP 18 BODY OR 250 MREM CHILD THYROID EPIP 19 l EPIP 21 NOTE: IF THE OFFSITE DOSE EPIP 22 DUE TO THE EVENT IS EPIP 25-29

, PROJECTED TO EXCEED 100 MREM WHOLE BODY OR. 500 MREM CHILD THY- .

-ROID,. PROCEED TO THE.

GENERAL EMERGENCY CLASS-IFICATION EPIP-5.

N l l

1

i Procedure No.

Subiec:: EPIP-4 P34U 4 "'13 Pa4cs Rovi:. son No. D.stu

/ Site Emergency 1 11/3/81 ,

3.2 UNCONTROLLED DECREASE IN FUEL POOL WATER EPIP 1 t

BELOW LEVEL OF FUEL EPIP 9 EPIP 10 RELEASE OR EPIP 11 LOSS OF CONTROL EPIP 12 OF RADIOACTIVE EPIP 13 MATER %L W: THIN EPIP 18 [

THE PLANT EPIP 19 EPIP 21 MAJOR DAMAGE TO SPENT FUEL IN CONTAINMENT EPIP 22 !

OR FUEL.HANDUING BUILDING EPIP 25-29 1

l 3.3 EXCEEDS THE SAFETY LIMIT OF 1373 PSIG.

REACTOR EPIP 1 i PRESSURE EPIP 12 EPIP 13 EPIP 18 EPIP 22 EPIP 25-29 3.4 EXCEEDS 100 GPM Exceeds CRD pump capacity of 100 GPM. EPIP 1 l REACTOR -

EPIP 12.

COOLANT EPIP 13 SYSTEM LEAK EPIP 18 ,

EPIP 22 l EPIP 25-29 l

i G

. i Procedure No.

ubiu m EPIP-4 P"W 5 "' 13 P"9**

Revision No. Date f Site Emergency IV3/81 4

A 3.5 BREAK OUTSIDE CONTAINMENT WITHOUT ISOLATION EPIP 1 MAIN STEAM EPIP 9 LINE BREAK EPIP 10 EPIP 11 EPIP p2 1

EPIP 13 EPIP 14 i

EPIP 18 I.

EPIP 19

. EPIP 21 EPIP 22 EPIP 25-29 3.6 nynnAnnn conn - pngsTnr.v rngs nv cnnt.Anr.v GEOMETRY EPIP 1 REACTOR COOLANT EPIP 12 SYSTEM ACTIVITY EPIP 13 INDICATING FUEL EPIP 18

~ CLADDING EPIP 22 DEGRADATION .EPIP 25-29 3.7 LOSS OF FUNCTIONS NEEDED TO ACHIEVE HOT.

STANDBY Hot Standby - planned shutdown from 100%

LOSS OF ~

po er o stan % w M reactor pressure PLANT CONTROL I 1020 PSIG and the reactor mode switch in EPIP 13

" Run .

Reactor. critical.at 10.% power, PIP 18 A. turbine tripped and turning on gear.

EPIP 22.

EPIP 25-29 )

~. !I I

'I l

Subject:

Procedure No.

EPIP-4 Page 6 f 13 Pagu Revision No. Data

/ Site Emergency i 1 11/3/81 3.8- LOSS ~OF ALL CONTROL ROCM ALARMS (ANNUNCIATORS) GREATER THAN 15 EPIP 1 LOSS OF MINWES WITH PLAW NOT m COLD EPIP 12 ANNUNCIATORS 'EPIP 13 OR ALARMS EPIP 18 EPIP 22

'EPIP 25-29 >

i 3.9 LOCAL CONTROL OF REQUIRED SHUTDOWN EPIP 1

' SYSTEMS NOT' ESTABLISHED WITHIN 15 EPIP 12 CONTROL ROOM -

MINUTES EVACUATION EPIP 13' EPIP 14 EPIP 15 '

. EPIP 18 EPIP 22

~

EPIP 25-2'9 I

3.10 ENTERS VITAL AREAS AND RESTRICTS

-EPIP 1-NECESSARY ACCESS EPIP 7 EPIP 8 FLAMMABLE GAS EPIP 12

,EPIP 13 EPIP 14 EPIP 15 EPIP 18 EPIP 22 EPIP 25-29 d

i Ge-: .

- Subjtet Procardure No.

EPIP-4 Page 7 of l3 Pag Revision No. Date Site Emergency

/

i 11/3/81 l

3.11 IMMINENT LOSS OF PHYSICAL CONTROL EPIP'1

'OF THE PLANT i

f EPIP 12 SECURITY EPIP 13 COMPROMISE EPIP 38

. EPIP 19 EPIP 22 EPIP 25-29 4

a 3.12 TEMPORARY LOSS OF BOTH EXCEEDS EPIP 1 LOSS OF OFFSITE - EPIP 12 i

POWER AND LOSS EPIP 13- s OF ONSITE POWER' EPIP 18 SUPPLIES EPIP 22 EPIP 25-29

[ :

3.13 LOSS'OF VITAL D;C.' POWER FOR MORE-EPIP 1 THAN 15 MINUTES VITAL D.C. EPIP 12 EPIP 13 EPIP 18 EPIP 22 EPIP~25 .

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Subject:

Procedure No.

EPIP-4 34' 8 f 13 Pa g .

Revision No. Data Site Emergency 1 4

11/3/81 j; I

3.14 AFFECTS SAFETY SYSTEMS REQUIRED EPIP 1 FOR SHUTDOWN EPIP 7 FIRE EPIP 8 EPIP 12 a

EPIP 13 EPIP 14 EPIP 18 7 EPIP 21 EPIP 22 EPIP 25-29 3.15 TORNADO / STORM EPIP 1 o Winds in excess of design EPIP 7 level, greater than 125 MPH EPIP 12 '

NATURAL EARTHQUAKE EPIP 13 PHENOMENA o Greater than SSE levels 0.22g EPIP 14 EPIP 18 o' Greater than design level or EPIP 19 '

damages vital equipment

EPIP 20 EPIP 21-

~

EPIP 22 EPIP 25 3.16 AFFECTS SAFETY SYSTEMS REQUIRED EPIP 1 FOR SHUTDOWN EPIP'7' i

EXPLOSION EP.IP 8 EPIP 12 EPIP 13 EPIP 14 4

EPIP 18 EPIP 21 -

EPIP 22 EPIP 25_29' k .

QP-: .

Subjact: 1 Procedure No.

EPIP-4 Page 9 oi l3 Pag.

' ' ~

Revision No. Data Site Emergency 3.17 CRASH AFFECTS VITAL STRUCTURES EPIP 1 AIRCRAFT Y A OR FIE EPIP 7 EPIP 8 EPIP 12 EPIP 13 EPIP 14

~

EPIP 18 EPIP 21 EPIP 22 EPIP 25-29 9

3'.18 OTHER PLANT CONDITIONS EXISTS THAT WARRANT ACTIVATION OF EMERGENCY I

CENTERS'AND MONITORING TEAMS AND A PRECAUTIONARY PUBLIC NOTIFICATION EPIP 13 EPIP 18 EPIP 22 EPIP 25-29 9

+

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QP-2 .

l

Subject:

Procedure No. {

EPIP-4 Page 10 E 13 P"B" Revision No. Date Site Emergency

/ 1 11/3/81 4.0 EMERGENCY ACTIONS TIME / INITIALS Note: . Record time and initials or N/A (not applicable) after completing each task 4.1 Upon recog'nition that any of the above Emergency Action levels have been exceeded, the Group Shift Supervisor shall assume the duties of the Emergency Director /

4 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 v' PERSONNEL: THE PLANT IS IN A SITE

( EMERGENCY CONDITION. ALL ON-CALL EMER-GENCY RESPONSE PERSONNEL REPORT TO

EMERGENCY STATIONS

. Repeat announcement /

4.4 Announce to Control Room personnel that has assumed the duties (name) of Emergency Director. /

L 4.5 Notify OCNGS Security, Ext. 6954,6950 and direct them~to activate.the pagers of the Onsite- Emergency . Duty: Section.. currently on duty (Group 1,2 or 3) If during non-normal duty hours, instruct Security to call the home numbers of all members of the Onsite Emergency Duty Section on duty using the.

auto-dialing phone Instruct Security to contact one member to fill each position on the Offsite Brau96cy Duty Roster. /

QP-:~.

9

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1

. j-Sabjects Procedure No.

EPIP-4 #E" 11 '13 ^b' Revision No. Date 7

Site Emergency , 1 11/3/81 4.6 Assign a Communicator to make notification i to persons and agencies listed in Attachment 1 / l l

4.7 Complete Attachment 2 " Initial Notification

~

Message" and give it to the Communicator to transmit . /

4 J

t 4.S Activate the Operations Support Center (EPIP-27)-

i the Technical Support Center (EPIP-26) and L the Nearsite Emergency Operations Facility (EPIP-25) / i

4. 9 Initiate Personnel Accountability in accordance k, with EPIP-12 /

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-ll /

4 .12: If fire-is involved, implement EPIP-8 /

4 .13 Complete Attachment 3, " Additional Information Message and give it to the Communicator for Transmission to the:following agencies:

Nuclear Regulatory Commission-

.New Jersey State Police l l

1 i

8

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. . - , 1 Procedure No. -.'Page of .bpsi l

',Suoject:

EPIP-4 12 13 l l SITE DEBGE2CY 7 l

' Revimnn No. 1 ~Date i )

.._.11/3/81 ,,,_ , I j l.

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

4.15 If pm :uual are injured, implement EPIP-7

/

b 4.16 Ccmplete Attachment 4, "INPO/ANI Message" and !

give it to the (h==micator for transatssion / -

l' i ,

4.17 If a report of personnel accountability has rx:t been received within 30 minutes, contact Security (6954, l 6950) for a status report / ;

I 4.18 If personnel are unaccounted for, implenent j Search and Rescue (EPIP-22) /

4.19 Activate the Rettete Assenbly Area (EPIP-18) if Site

k. Evacuation is to be implenented. /

4.20 Implenent Site Evacuation (EPIP-13) upon cx2npletion of pw.:uual accountability /

4.21' Based on assessment of plant conditions:

4.21.1 If recovery conditions have been met, initiate the Recovery Phase in accord-ance with EPIP-29. /

4.21.2 If recovery conditions have not been met but site Emergency Action levels are no: ,

longer being e M M , de-escalate to a lower m m.ymiy class by performing noti-fications in accordance with Alert (EPIP-3)

' or Unusual Event (EPIP-2) as appropriate. /

I k_

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i Sabjset: Procedure No.

EPIP-4 Page 13 f 13 Pag-Site Emergency Revision No. Late 1 11/3/81 4.213. If emergency action levels exceed those j for a Site Emergency,. escalate to a General Emergency (EPIP-5) s /

i i

5.0 Final Conditions I 5.1 Recovery Phase has been initiated in accordance with.EPIP-29 /

5.2 A lower class of emergency has been ,

declared by'the Emergency Director and one of.the following procedures is being~ implemented:

EPIP-2 Unusual Event

(

/

EPIP-3 Alert /

5.3 A General Emergency has been declared by the Emergency Director and EPIP-5 is being implemented /

e e

'Q

QP ' .

Subj:Ict: Procedure No. .

EPIP-4 Page1 cr 2 P a , e .-

Revision No. 'Date ,

SITE EMERGENCY l 11/3/81 l r i h

COMMUNICATOR'S CHECKLIST - SITE EMERGENCY

]

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 /

> 5. Notify the New Jersey State Police within 15 minutes of classification Use Attachment 2 format Primary: State Hot Line Alternate: (609) 882-4200 /

6. Notify the United States Nuclear Regulatory Commission Operations Center

(

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

Alternate: 1) Commercial via Bethesda (301) 492-8111 2 ). Commercial via Silver Spring- (301) 427-4056 3)- NRC-HPN Line . Dial 22 or *22 (Touch-tone)

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

Note: Open-Line Communications with NRC is to be maintained on ENS Line throughout the emergency situation.

7. Notify the agencies directed by the Emergency Director using Attachment 3 format /

\.

ATTACHMENT 1

, a ;c.c. -

Procecuro No.

EPIP-4 ! i'm,e 2, 2 .

SITE N CY l Revision No. ! dan 1 i 11/3/81 j I

I i

Notify the following agencies using Attachnent Time / Initials _ ,

t 4 format.

Institute of Nuclear Power Operations ___

/

Tel: (404) 953-0904 i

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

s i

I i

r 4

~

(

ATDCHMEtE 1

l

'. 1 1

I

Subject:

Procedure No. 1 Site Emergency EPIP-4 Page 1 of 1 Pay Revision No. Date

/ I 11/3/81 .

I r

INITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION . TEST, ORILL OR EXERCISE, THE MESSAGE WILL !

BEGIN AND END WITH THE PHRASE, "THIS IS A . EXAMPLES: ;

"THIS 15 A ORILL." "

THIS IS A COMMUNICATIONS TE5T." "THIS IS AN l EXERCISE." "THIS IS NOT AN EXERCISE -- I REPEAT -- THIS IS NOT AN EXERCISE."

THIS IS '

(Name) (Title)

AT' OYSTER CREEK NUCLEAR GENERATING STATION THIS IS A NOTIFICATION OF A SITE EMERGENCY CLASSIFICATION.

THE EVENT OCCURRED AT , ON (Time - 24 hr. Clock) (Date)

O THERE IS NO RELEA'SE IN PROGRESS.'

O WE HAVE A CONTROLLED RELEASE IN PROGRESS. ,

( ~"

// WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS.

6 NO PIMELTIVE ACTIONS ARE RECOMMENDED. f i

_/7 WE .RECOM. MEND SHEL.TERING FOR THE FOLLOWING DIRECTIONAL SECT I

~~

// WE RECOMMEND EVACU'ATION FOR'THE.FOLLOWING DIRECTIONAL SECTOR (S) j' i-APPROVED .;

EMERGENCY DIRECTOR DATE (Time-24 hr) ,

_____________________________________________________________________________]

THIS. MESSAGE HAS BEEN TRANSMITTED.TO: .. .

' TIME COMPLETED i j NEW' JERSEY STATE POLICE O UNITED STATES NUCLEAR' REGULATORY COMMISSION DATE COMMUNICATOR

~

, ATTACHMENT 2.

\

e

Suoject: Procedure No. j Site Emergency- EPIP-4 l Sage 1 of 4 Pa.; .

Revision No. Date 1 11/3/81 i

l l

ADDITIONAL INFORMATION MESSAGE l

Check ( ) all appropriate information DATE 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 a'dditional'information for the

~

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

( '

Site Emergency; General Emergency.

2. DATE/ TIME OF CLASSIFICATION ,

t

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

~

b. Date: ' Month ' Day ' Year i

3. There (circle.one) is/is not an Emergency Classification j ch'ange. The classi'fication is: (circle one)2 Unusual Everit ;. ;

Alert;. Site' Emergency; General Emeroency. ,

4. . Plant Status -

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

ATTACHMENT 3 pm i

l

Subject:

Procedure No.

Site Emergency EPIP-4 Page 2 of 4 Pmj Revision No. Date r 1 11 /3/81 2

i

I

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

c. Reactor is subcritical, coolant is being maintained over i i

4 tne core, and containment integrity is satisfactory.

E 5. Type'of release (circle one) airborne; liould; surface soill. ,

6. Meteorological Data-

a. Wind speed MPH I

l

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 I i

( b. Iodine 131 release rate uC1/sec j

! i

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

i d. Actual or. estimated duration of release:

~ ' '

j i

I

! 8. Liquid Radiological Date +

I

a. Release concentration uC1/cc ,

a

b. Rel' ease rate' UCi/sec ,

I

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

d. Actual or estimated duration of release

e. ~Est'imated total release uCi ATTACHMENT 3 i.

l

Subject:

Proctdura No.

Site Emergency EPIP-4 Page 3 of 4 Pag-Revision No. Date

! / 1 11/3/81 l 9. Projected dose rates and integrated dose (Based on actual or }

I

I projected duration of release) !

[

! WHOLE BODY !

l

a. Site Boundary mr/hr mrem

b. 2 miles mr/hr mrem

c. 5 miles mr/hr mrem '

l i d. 10 miles mr/hr mrem t

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

THYROID ,

i . .

a. Site Boundary uCi/cc mrem l _

l l b. 2 miles uCi/cc mrem

c. 5 miles uCi/cc mrem i

(_ d. 10 miles uCi/cc mrem '

i

11. Estimate of surface contam'ination dpm/100 I I

cm2 (obtain from field data) -

mrem /hr i

.}

I 12. Emergency Actions in progress:

'a . Radiological survey teams onsite ,

b. Radiological survey teams offsite ;

c'. Onsite fire brigade l

'd.

'Offsita fire' department

~

e. Damage Contro1

f. First aid teams onsite

g. Ambulance service

h. Medical support

.i. Environmental surveys offsite L

j. Other, specify

ATTACHMENT 3-

9

Subject:

Procedure No. .-, .

Site Emergency EPIP-4 Page ; 4 of 4 P a.j -

Revisiort No. Date ~

/ 1 11/3/81 ,

.t ;

I

13. Additional support required (specify) ' '

~

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

j Alert; Site Emergency; General Emergency

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

16. The foliowing changes in' protective measures are recommended <

for the' population in these sectors i

a. None

( b. Notify (projected offsite dose ) !

c. Take. shelter (projected offsite dose ) l

- I

d. Evacuate (projected-offsite. dose )!

I'7 . ' Approved' - i (Emergency Director / Emergency Support Director). l ,

i (Date) (Time) j

18. Transmitted l i .. i

a. 'New Jersey State Police .,

~ ~

b. United. States Nuclear Regulatory Commission s .

(Communicator)

(Date) (Time)

ATTACHMENT 3

(

1

I

%' 4.-

/r_ * ,,

I I .

Procedure No. 1 of 1 Paj EPIP 4 ; Page Saoject: _

I Date e Emergency Revision No. 11/3/81

' f'

, 1 ,

\

r Ie INSTITUTEINSURERS OF NUCLEAR POWER OPERA ;

NOTIFICATION TO:& AMERICAN NUCLEAR s

D', ',

, i t MESSAGE FORMAT #

I'

_. at

1. This is ~ (Name/ Title)

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

condition at - (Time)

(Event Classification) ._-

Description of Emergency:_

2.

i

__l

(', -

i t

~

t 0.irector).

i 3 Approved __ (Emergency Director / Emergency Suppor. .

- - (Time).

i (Date). .

__ i i

i

'.4. . Transmitted: - (Communicator) k 1

~

(Time)

(Date). .

(

ATTACHMENT 4 p dm> -

m 1

+ .

sk Procecure No. i 9

EPIP-5 Page- 1 Of 8 :

b 4 f q.l .),'q --L,

- " Date Issued Effective Cate i Jersey Central 2/22/81 uf uest - u m eat O Power & Light Company Revision No.

1 Date 11/3/81 l

Subject:

ggggn p.ZRGECl Authorized By

- Director Oyster Creek hations

\_ AHdh ,

w Oyster Creek Nucle Generating Station j List of Effective Pages Date Revision Ntrber 1

1 11/3/81 1

2 11/3/81 3 11/3/81 1 4 11/3/81 1 5 1 11/3/81 6 11/3/81 1 7 11/3/81 1 8 1 11/3/81 O .

Attachnents '

Attachment 1 (2 pages) 11/3/81 1 Attachnent 2 (1 page) 11/3/81 1

- Attachment 3 (4 pages) 11/3/81 1 Attachment 4 (1 page) 1 11/3/81 N

~ O. .

I t _-

A s y l

l

. .. . . . _ . 'l l

Procedure No. f

Subject:

Pa9e 2 of 8 Pages l EPIP-5 I GDEFAL D N Revision No. Dato ,

1 11/3/81 h

1.0 PURPOSE i 1.1 The purpose of this procedure is to define the conditions that shall be regarded as a General Emergency for Oyster Creek Nuclear Station and to:

1.1.1 Ensure necessary l'aqtions 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 emergency response organizations to initiate appropriate emergency actions.

1.2 The: Emergency Director is responsible.for implementing this procedure.

l.3 Emergency Director responsibilities that may not be delegated

( include:

1.3.1 Decision to 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, 2.0 ATTACHMENTS 2.1 Attachment 1, Communicators Checklist 2.2 Attachment 2, Initial Notification Message .

2.3 Attachment 3, Additional Information Message k.

2.4 Attachment 4, INPO/ANI Message i

1 Procedure No.

Subjec:: P39" 3 8 P39CS EPIP-5 8 Revision No. Oate N DEM3ENCY 1 11/3/81 g 3.0 EMERGENCY ACTION LEVELS _

REFERENCE PARAMETER INITIATING CONDITION 3.1 RELEASE CORRESPONDS TO GREATER THAN 50 mrem / i hr TO WHOLE BODY OR GREATER THAN 250 mrem /hr EPIP 1 TO CHILD THYROID AT SITE BOUNDARY thru i

RADIOACTIVE EPIP 29 L TS OFFSITE DOSE DUE TO THE EVENT IS PROJECTED TO EXCEED 100 mrem WHOLE BODY OR 500 mrem CHILD THYROID

(

3.2 LOSS OF 2 OF 3 FISSION PRODUCT BARRIERS WITH EPIP 1 A' POTENTIAL LOSS OF THE THIRD BARRIER thru APPLICABLE TO ANY INITIATING EVENT THAT MAY .EPIP 29 LEAD TO THIS CONDITICN OR ANY INITIATING EVENT THAT MAKES RELEASE OF LARGE AMOUNTS OF_

RADIOACTIVITY PROBABLE. FOR EXAMPLE:

o Small or.large LOCA's with failure'of ECCS to: perform leading to core melt or degradation. Loss of containment imminent.

o Small or large'LOCAo'ccurs and contain-ment performance is unsuccessful affect-ing longer term success of the ECCS.

Could lead to core degradation or melt 4

in several hours without containment boundary.

I

Procedure No.

Subject:

Page 4 of g Pages EPIP-5 N MRECl Revision No. Date 11/3/81 INITIATING CONDITION REFERENCE PARAMETER o Shutdown occurs, but requisite decay heat removal systems are rendered unavailable.

Core degradation or melt could occur in about ten hours with subsequent contain-ment failure.

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

.o Any major-internal or external. events which could cause massive common damage to plant systems leading to any of the above

( OR Loss of plant control occurs.

h 60 e

32 ject: ' Procedure No. Page of icyx EPIP-5 _5__ 8 .-

Revision No. 1 DaE/3/81 4.0 EMERGENCY PCfIONS Note: Record time and initiala or N/A (not Applicable) after cciupleting each task. Time / Initials 4.1 Upon recognition that any of the above Dwry Action levels have been exceeced, the Group Shift Supervisor shall assume the duties of the Emergency Director. /

4.2 Sound the appropriate alarm. /

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

ATIENTION ALL PERSONNEL, ATIENTIN AIL PERSWNEL:. THE PIAVf IS IN A GENERAL EN CDNDITION. ALL CN-CEL DERGDCY RESPONSE PERSCNNEL REPORP 'IO DERGECY DUTY SIATICtE.

f

. k.

Repeat announcenent /

4.4 Announce to Control Rocm personnel that has assumed the duties i I

Name of Bnergency Director. /

4.5 Notify CCNGS Security, Ext. 6954, 6950 and direct them to activate the pagers of the Onsite Dim yeucy Duty Section currently on duty (Group 1, 2 or 3) . If during non-normal duty hours, instruct Security to call the hcme nunbers of all' members of the Onsit'e anergency Duty Section on duty using the auto- ,

elialing phone. Instruct Security to contact one msnber to fill each position on the Offsite Emergency Duty Roster.

/ l

'I ,

l I l

c -- -

Prc- No.

~

Page 6 OI 8 Pages

. ..EPIP-5 GE2ERAL N Re; .o. Date j ,

1 11/3/81 __

l 4.6 Assign a' Communicator to make notification to persons and agencies listed in Attachment 1. /

~

l 4.7 Complete Attachment 2 " Initial Notification Message" and give it to the Communicator for

/

transmission.

48 Activate the Operation Support Center (EPIP-27), the Technical Support Center (EPIP-26) and,the Nearsite Emergency Operations Facil-

/

ity (EPIP-25).

4.9 Initiate Personnel Accountability in accord-( /

ance with EPIP-12.

-4.10 Initiate and continue offsite dose projection

' s-in accordance- with EPIP-9. /

Initiate onsite and offsite radiological !

4.11 :

surveys in accordance with EPIP-10 and .

/

EPIP-ll.

~

4.12- If fire is involved, implement EPIP-8 /

4.'13 Complete Attachment 3, " Additional Infor-mation Message" and give to the Communicator for transmission to the following agencies:

Nuclear Regulatory Commission New Jersey State Police ,

Ocean County k Lacey Township i

i -

s _. _ _ -

g k

PrcceeJ 9 No.

Page7 of 8 Pages EPU-5 RevisL' No. Date e ancz 1 11/3/81 __

t i

i e

i f '

i l 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 Attachment 4, "INPO/ANI Message" and.give it to the Communicator for Trans- '

mission. /

4. 17 If a report of personnel accountability has not been received within 30 ttinutes, contact Security.(6954, 6950) for a status report. /

4. 18- If p~ersonnel'are unaccounted for, imple-ment Search and Rescue (EPIP-22) /

4. 19 Activate the Remote Assembly Area '(EPIP-18) /

4. 20 Upon completion of personnel accountability, '

implement Site Evacuation (EPIP-13) /

i

4. 21 Based on assessment of. plant conditions:

4 21 1 If recovery conditions have been met, initiate t.Ne Recovery Phase in accordance with EPIP-29., /

i

.I i i l

-e g

Prt ... r lwo.

ace;,;c: Page a of 8 Page EPIP-5 j

Re 'o. Date l GENERAL NCY .:.

1 11/3/81 4.21 .2 If recovery conditions have not been l lj met but General Emergency Action Levels are no longer being exceeded, f

' de-escalate to a lower emergency class by performing notification in ,

l i accordance with Site Emergency (EPIP-4),

l Klert(EPIP-3) or Unusual Event (EPIP-2) !

/

as appropriate. __

5.0 FINAL CONDITIONS 5.1 Recovery Phase has been initiated in accordance with EPIP-29. /

5.2 A lower class of emergency has been declared by

' the Emergency Director and one of the following l

procedures is being implemented-I i

EPIP-2 Unusual Event /

l EPIP-3 ' Alert' -/

EPIP-4 Site Emergency , /

a e

4 9

l l

l e l l

\

l l

,1, .-

l' 2 ,

~

i Subitct: Procedura No.

EPIP-5 Page 1 of 2 Pau GENERAL EMERGENCY Revision No. Date

,. 1 11/3/81 l <

COMMUNICATOR'S CHECKLIST - GENERAL EMERGENCY '

Time / Initials I

i i 1. Notify the on-duty Shift Technical Advisor / ;

+

l i

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

3. Notify,the on-call Emergency Director /

q

4. Notify the on-call Emergency Advisor /

I

5. Notify the New Jersey. State. Police within l 15 minutes of classification.

Use Attachment 2 format Primary: State Hot Line Alternate: .(609) 882.-4200- /- !

f 6. Notify the United States Nuclear Regulatory l

.; Commission Operations Center Use Attachment 2 format J Primary: NRC-ENS Line (Lift receiver frem cable) l

,I j Alternate: 1) Commercial via Bethesda (301) 492-8111 l

2)-Commercial.via Silver. Spring. (301) 427-4056 l-1 i 3) NRC-HPN Line-Dial 22 or *22 (Touch-tone) l 4') Commercial via Bethesda (301)'492-7000 / l

- i I '

Note: Open-line communications with NRC is i.

i to be maintained on ENS Line throughout ,

j j .

'the emergency' situation. .

I i

~7. Notify the' Ocean County Operations Center Use' Attachment 2 format ~

Primary: Ocean County Hot Line /

i l-

! e k.

ATTACHMENT 1. i l

,uaiec: :

Procucure No.

Pa',e 2 of 2 ' -_ , '

gm en EPIP-3 _ _ _ _

Revision No. Datu ;l 1 11/3/81 !1

'I

.j

8. Notify Lacey Township Use Attadment 2 fonnat !

Primary: (609)~ 693 - 6636 / ,

9. Notify the agencies directed by the Emergency Director using Attachnent 3 femat /

10. Notify the following agencies using Attadunent 4 fonnat

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

I I

American Nuclear Insurers i i

Tel: (203) 677-7305 / I

( i i

i l

i t

f i

l 6

ANTR 1

1 Subjed: Procedure No.

General Emergency EPIP-5 Page 1 of 1 Pay ,

Revision No. Date 1 11/3/81

,l

'NITIAL NOTIFICATION MESSAGE IN THE EVENT OF A COMMUNICATION TEST, DRILL OR EXERCISE, THE MESSAGE WILL !

BEGIN AND END WITH THE PHRASE, "THIS IS A . EXAMPLES: f' "IMIb 15 A DRILL." "

THIS IS A COMMUNICATION 5 TE5T." "THIS IS AN EXERCISE." "THIS IS NOT AN EXERCISE -_ I REPEAT _- THIS IS NOT AN .

EXERCISE." '

THIS IS (Name) (Title)

AT OYSTER CREEK NUCLEAR GENERATING STATION THIS IS A NOTIFICATION OF A GENERAL EMERGENCY CLASSIFICATION.

THE EVENT OCCURRED AT , ON (Time - 24 hr. Clock) (Date) t.

z7 THERE IS NO RELEASE IN PROGRESS.

f 7 WE HAVE A CONTROLLED-RELEASE IN PROGRESS.

_/_7 WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS.

// NO PRDIECTIVE ACTIONS AHE RECOMMENDED.

/[7 WE RECOMMEND SHELTERING FOR THE FOLLOWING DIRECTIONAL SECTOR (S)

/7 WE RECOMMEN'D EVACUATION FOR THE FOLLOWING DIRECTIONAL SECTOR (S)

APPROVED EMERGENCY DIRECTOR DATE (Time _24 hr)

THIS MESSAGE HAS BEEN TRANSMITTED.TO: ,

TIME COMPLETED ,

l.

f7 NEW JERSEY STATE POLICE

/_/ UNITED STATES NUCLEAR REGULATORY COMMISSION f[7 OCEAN COUNTY OPERATIONS CENTER i7 LACEY TOWNSHIP

s. DATE COMMUNICATOR ATTACHMENT i 4

. 1

_ \

Subject:

Procedure No. i General Emergency EPIP-5 Page 1 of 4 Py Revision No. Date I

/ 1 11/3/81 i

I ADDITIONAL INFORMATION MESSAGE l Check ( ) all appropriate information l t

DATE -

i TIME i

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

Director at Oyster Creek Nuclear Generating Station. The e following is~'provid'ed as additional in'formatiori for the initial notification of the (circle one) Unusual event; Alert; ,

( Site Emergency; General Emergency.

I

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) ,

Datei

~

b. M'onth Da Year' !

. I

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

4. Plant Status fl l

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

a.

k ATTACHMENT 3

Subject:

Procedure No.

General Emer,gency EPIP-3 Page 2 or 4Pt Revision No. Date

1 11/3/81 -

i

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

c. Reactor is subcritical, coolant is being maintained over ,

i the core, and containment integrity is satisfactory.

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

6. Meteorological Data-

a. Wind speed MPH

b. Wind direction (toward)

c. Stability cla,ss (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 j

c. Release (circle one) has/has not term'inated

d. Actual or estimated duration of. release:

i

8. Liquid Radiological Date

~

a. Release concentration uCi/cc 1

b. Release rate UCi/sec l

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

d. Actual or estimated duration of release

e. Estimated total release UCi ATTACHMENT 3

~ ~ -

w --

1 l

Proc; dura No.

Subjoct: Page Pm,c-Eoio ; , of s General Emergency Revision No. Date 1 11/3/91 f.

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

WHOLE BODY l

a. Site Boundary mr/hr mrem l

l

b. 2 miles mr/hr mrem

c. 5 miles mr/hr mrem l

l d. 10 miles mr/hr mrem l

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

THYROID

a. Site Boundary uC1/cc mrem

b. 2 miles uC1/cc- mrem

c. 5 miles uC1/cc mrem l d. 10 miles uCi/cc mrem i

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

l

12. Emergency Actions in progress:

a. Radiological survey teams onsite

, b. Radiological survey teams affsite 1

1

c. Onsite fire brigade

d. Offsite fire department

e. Damage Control l f. First aid teams onsite l

g. Ambulance service-

h. Medical support

1. Environmental surveys offsite-J. Other, specify

.-.-3

.a.

Procedure No.

OUbgeet: Page P m;e s gorp_5 f, of 3 General Emergency Revision No. Date

< 1 11/3/81

13. Additional support required (specify)

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

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 )

c. Ta <e shelter (projected offsite dose )

d. e vacsate (projected offsite dose )

17. ' Approved (Erergency Director / Emergency Supoort Director)

(Date) . (Time)

18. Transmitted

a. New Jersey State Police

b. United States Nuclear Regulatory Commission

c. Ocean County

d. Lacey Township (Communicator)

(Date) (Time)

ATTACHMENT 3 1

l .

l e. ,

I e' Proctduro No.

l

Subject:

Page ' of i General Emergency * " ' Pa6c Revision No. Date 1 11/3/81

?

NOTIFICATION TO: INSTITUTE OF NUCLEAR POWER OPERATIONS

& AMERICAN NUCLEAR INSURERS MESSAGE FORMAT

1. This is at (Name/ Title)

Oyster Creek Nuclear Generating Station. We have declared A/AN condition at (Event Classification) . (Time) 1

2. Description of Emergency: _

3. Approved (Emergency Director / Emergency Support Director)

(Date) (Time)

4. Transmitted:

(Communicator)

(Date) (Time) l ATTACHMENT 4 I a j

l l

,

ML20039A722

Contents

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