ML20069F203

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

ML20069F203
Person / Time
Site:	Oyster Creek
Issue date:	08/17/1982
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20069F168	List: ML20069F192 ML20069F203
References
PROC-820817-01, NUDOCS 8209270500
Download: ML20069F203 (96)

Text

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8/17/82 Page 1 of 3

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EMERGENCY PLAN IMPLEMENTING / ADMINISTRATIVE PROCEDURES INDEX DATE i

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

8209270500 820916 PDR ADOCK 05000219 F PDR

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Page-2 of 3 EPIP AND EPAP TITLE LISTING EMERGENCY PLAN IMPLEMENTING PROCEDURES LAST LAST TITLE REV. NO. REV. DATE PROCEDURE f EP IP - 01 Classification of Emergency Conditions 3 __ 7/20/82 EPIP - 02 Unusual Event 3 7/20/82 3 7/21/82 EPIP - 03 Alert EPIP - 04 Site Emergency 3 7/21/82 EP IP - 05 General Emergency 3 7/21/82 EPIP - 06 Not Is sued Personnel Injury 1 2/23/82 EPIP - 07 2/10/82 EPIP - 08 Fire 1 2/23/82 1

EP IP - 09 Offsite Dose Assessment Emergency Radiological Survey - Onsite 0 2/19/81 EPIP - 10 3/04/82 EPIP - 11 Emergency Radiological Survey - Offsite 1 Personnel Accountability 2 1/27/82 EPIP - 12 EPIP - 13 Site Evacuation and Personnel Accountability 'Af;:er Site 1 2/17/82 Evacuation 3/04/82 EPIP - 14 Damags Control 1 1 2/10/82 EPIP - 15 Toxic / Flammable Gas Release Radioactive Liquid Release 0 2/23/81 EPIP - 16 EPIP - 17 Activation of the Parsippany 0 2/26/82 Technical Punctions Center 2/23/81 Activation of' the Remote Assembly Area 0 j EPIP - 18 2/17/82 1

EPIP - 19 Energency Dosimetry Tornado /rigli Winds De le te 2/19/82 EP IP - 20 2/19/82 1

EPIP - 21 Personnel Decontamination 2/24/81 Search and Rescue Operations 0 EP IP - 22

• 2/19/82 EPIP - 23 Thyroid Blocking 1 EPIP - 24 Emergency Respiratory 2/19/82 0

Equipment EPIP - 25 Activation of the Nearsite Emergency 0 2/24/31 Operat. ions Facility 2/24/81 EPIP - 26 Activation of the Technical Support Center 0 Activation of the Operations Support Center 0 2/24/81 EPIP - 27 EPIP - 28 Activation of the Farsite Bsergency 0 2/24/81 Operations Facility 3/04/82 1

EPIP - 29 Recovery Operations l

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EMEDGENCY PLAN IMPLEMENTING PROCEDURES LAST LAST TITLE REV. NO. REY. DATE PROCEDURE #

ADMINISTRATIVE PROCEDURES EPAP - 01 Baergency Plan Implementing Procedure Format Delet e--

EPAP - 02 No t Issued EPAP - 03 Not Issued EPAP - 04 Not Issued 05 Baergency Equipment Inventory 0 2/27/81 EPAP - 2/24/81 Baergency Preparedness Training 0 EPAP - 06 07 Radiological Survey Team Training 0 2/24/81 EPAP - 2/24/81 Pire Brigade Training 0 EPAP - 08 09 Of fiste Fire Department Training 0 2/24/81 EPAP - 0 2/24/81 EPAP - 10 First Aid Training 11 Of faite Medical Personnel Training 0 2/24/81 EPAP -

EPAP - 12 Not Issued -

EPAP - 13 Bnergency Plan Implementing Procedure /

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

Mainistrative Procedure Review /

Revision Procedure 0 2/24/81 EPAP - 15 - Baergency Response Mobilization (Proposal) 16 Maintaining Baergency Preparedness 0 2/24/81 EPAP -

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• Jersey Central 2/19 81 5 mr/hr 250 mr/hr l Gaseous Iodine Limits Limits for 1/2 hr Whole Body ~or Exceeded Exceeded by a Whole body g 7250 mr/hr Particulate 725 mr/hr child Thyroid factor of 10 Child Thyroid Liquid 10CFR20 Appendix B, Column 2 -

Limits exceeded in discharge canal Projected Offsite Doses

>10 mrem 7 50nRem >100 mrem Whole Body

> 50nRem 7250nRem 7500 mrem Child Thyroid

).1110 PSIG 71239 PSIG 21373 PSIG Reactor Pressure f

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MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY l EPIP-2 EPIP-3 EPIP-4 EPIP-5 RCS laakage (Into Primary Containment)

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Unidentified >10 gpa -

leak rate To ta] leak > 15 gpa >50 gpm Known Loss of coolant rate or reactor accident with Causes or coolant centainment requires system failure affect-the Reactor leak ing the long to be scrammed exceeds term success of available make- the ECCS. Core up capacity degradation or

. melt in several hrs without con-tainment boundar, RCS Total Iodine . >8.0 uC1/cc >300 uC1/cc Indication of Ac tivity degraded core with possible loss of coolable geometry Of f-Cas Monitor Increase of >10,000 mr/hr Reading and 666 mr/hr Fuel cladding Fuel Status in 30 min. failure and/or

>3,330 mr/hr Safety / Safety / relief Main Steam Steam Line Relief Valve Valve does not Line Break Break outside g close following with MSIV Containment l Main Steam Isolation reduction of Malfunction w/o isolation Valve Status applicable causing pressure leakage into Turbine Building 4., ,

I Classification of Emergency Conditions E*-1" , M, 3 .,, 7

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ATTACHMENT 1 (co'nt'd)

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY EPIP-2 EPIP-3 EPIP-4 EPIP-5 Reactor Reactor SCRAM Failure of Transient req- 1. Loss- o f Protection followed by a reactor pro- uiring opera- coolant accident Systems unplanned taction system tion of shut- with failure automatic to initiate & down systems of ECCS to ECCS initiation complete a with a failure perform lead-and discharge SCRAM which to SCRAM, no ing to core into Reactor brings the core damage melt degrada-Ve ssel reactor sub- evident tion in minutes critical when to hours. I4ss called for of containment may be imminent.

2. Transient occurs & failure of requisite core shutdown systems could lead to core melt in several hours with containment failure likely e

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~ l ATTACHMENT 1 (cont'd) f MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION I

1 PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY i EPIP-2 EPIP-3 EPIP-4 EPIP-5 Loss of Shutdown Co ntainment required by - -

Integrity other than .

normal methods Loss of 1. Requiring 1. Loss of 1. Loss of 1. Shutdown Engineered shutdown by functicas functions need- occurs but decay Safety Features Technical necessary to ed for plant heat rewoval Specifications bring the hot shutdown capability and shutdown is plant to cold when hot shut- is lost. Core required other shutdown down is req'd degradation or than in a when cold 2. Sustain loss melt could normal manner. shutdown is of all or most occur in 10

2. Un- required. annunciEors hours with sub-anticipated, 2. Sustain in Control sequent contain-confirmed, loss of all Room coupled ment failure.

alarm on any o_r, r most annun- with Plant 2. Ioss of 2 of two area ciators in transient 3 fission radiation Control Room 3. Control product barriers monitors 3. Evacuation at local sea- with a potential simultaneously of Control tions not loss of the which cannot Room, Control established third.

be corrected established within 15 mins.

or any Process at local af ter Control

' Radiation stations with- Roon evacuation.

Monitor. in 15 minutes. 4. Major damage

4. Fuel hand- to spent fuel ling accident resulting in or other uncontrolled Eent resulting release of radio-in unexpected active material increase of or uncontrollable inplant radio- decrease in fuel activity levels pool water below top by a factor of of spent icel 1000 i

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Classification of Emergency Conditions

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MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY CLASSIFICATION INITIATING CONDITIONS GENERAL UNUSUAL SITE ,

EMERGENCY EMERGENCY EVENT ~ ALERT EPIP-3 EPIP-4 EPIP-5 EPIP-2 Which could Which enters Enters Vital Toxic or Area and flammaHe gas affeet habita- plant and release - near bility required affects safe affects opera Fon for normal operation of or onsite the plant of safe plant operation shutdown equipment, plant not in cold shutdown Imminent loss Loss of Security Security threat Ongoing physical compromise. of physical Compromise . g attempted control of control of entry og plant coupled plant occurs attempted sabotage with intrusion. with intrusion in progress.

Sustain loss of Offsite'and Offsite and Loss of Power offsite power onsite power Onsite E

' or loss of both or vital D.C. Vital D.C.

diesel generator power for exceeds 15 min.

capabilities <15 min.

during power operations.

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Rension No. 3 Care 7/20'/82 ATTACHMENT 1 (cont'd)

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGENCY cf ASSIFICATION INITIATING CONDITIONS UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY EPIP-2 EPIP-3 EPIP-4 EPIP-5 Natural 1. Sustain 1. Sustain Plant not in Phenomena windspeed >75 .windspeed. cold shutdown:

Being sph >100 mph 1. Sustain Experienced 2. Flood level 2. Flood ol windspeed >125 or Projected with probable low water level sph flooding of potentially 2. Flood E i evacuation affecting low water level routes. operation of affecting safe shutdown operation of safe equipment shutdown equipment when required when required to to operate. operate.

3. Tornado 3. Earthquake causing strikas major damage to equip-

. facility. ment necessary for

4. Earthquak,e shutdown.

affecting plant operation Fire Fire not under Po tentially Affecting function control within affecting of plant safety 10 minutes. Pl ant safety systems systems Explosion Unanticipated With damage t'auses severe near g affacting damage to safe onsite plant opera- snutdown equip-tions ment, plant not in cold shutdown

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ATTACHMENT 1 (cont'd)

MATRIX OF INITIATING CONDITIONS FOR EMERGENCY CLASSIFICATION PARAMETER EMERGEFCY CLASSIFICATION INITIATING CONDITIONS UNUSUAL. SITE GENERAL E7ENT ALERT EMERGENCY EMERGENCY EPIP-2 EPIP-3 EPIP-4 EPIP-5 Contaminated Requires Injury transportation __

offsite for medical treatment Aircraf t Crash Onsite outside Within Affecting or protected area- protected area vital plant Missile Impact no plant structures by s tructure s impact or fire, affected plant not in cold shutdown Turbine Ro tating Resulting Failure component in, casing failure causing penetration a reactor scram Other plant Other plant Other plant Other plant Plant Status-or conditions conditions are conditions conditions are- conditions are are in pro- in progress or in prog ess or as evaluated in progress or by GSS/ Emergency have occurred gress or have have occurred have oceurred which Psy occurred which which may which may in-Director ,

indicate a may involve an involve actual volve actual or potential de- actual or or likely major imminent sub-gradation of potential sub- failures of stantial core the level of stantial plant functions degradation or safety of the degradation of needed for melting, with plant. the level of protection of potential for safety of the the public. loss of con-plant tainment integ-rity, or may make release of significant amounts of radioactivity in a short time possible.

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Jersey Central *** 'MW81 5",'*7s*2 e 3 s 23/82 l~

f Power & Light Company Revision No. l Cate 3

I Suciect: Unusual Event Autnosusc Sy Director-Station Operations I

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Oyster Creek Nuclear Gener g Station L/ . j LIST OF EFFECTIVE PACE DATE REVISION NUMBER

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-2 7/20/82 3 3 7/20/82 3 i

ATTACHMENTS

, Attachment 1 (4 pages) 7/20/82 3 l .

Fom EPIP-2-1 (4 pages) 7/20/82 3 Fom EPIP-2-2 (2 pages) 7/20/82 3 Fom EPIP-2-3 (1 page) 7/20/82 3 i

Fom EPIP-2-4 (1 page) 7/20/82 3 Fom EPIP-2-5 (2 pages) 7/20/82 3 l Fom EPIP-2-6 (3 pages) 7/20/82 3 i

l NON-CONTROLLED This Document WiH Not Be Kept

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. . 1 Suoteen ' heceaure Na Unusua1 Event EPIP-2 %2 sf 3 ' 5 Amason - No. Oate 7/20/82

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- 1 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 te:

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

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

1.1.3 Mobilize the appropriate portions of, the emergency. response.

organization to initiate appropriate emergency actions.

2.0 REFERENCES

i 2.1 OCNCS Emergency Plan 2.2 NUREG-0654 Rev. 1, FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

2.3 OCNGS Emergency Plan Implementing Procedures ( EPIP) 2.2.1 EPIP-L Classification of Emergency Conditions 2.2.2 EPIP-3 Alert 2.2.3 EPIP-4 Site Emergency 2.2.4 EPIP-5 General Emergency 3 '. 0 RESPONSIBILITIES 3.1 The Emergency Director is responsible for implementing this procedure.

3.2 Emergency Director responsibilities that may NOT be delegated include:

3.2.1 Decision to notify offsite emergency management agencies.

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

3.2.3 Classification of Emergency Event.

3.2.4 Detennining the necessity for onsite accountability and/or evacuation based upon potential exposure to non-e ssential personnel.

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

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4.nason .N o. Oate 1 3 7/20/82 l l 4.0 PREREQUISITES 4.1 The Site is in a condition that warrants Unusual Event declaration as defined by this procedure as judged by the Group Shift Supervisor / Emergency Director.

5.0 REQUIREMENTS 5.1 Emergency Actions 5.1.1 The Group Shif t Supervisor / Emergency Director shall, upon recognition of inplant or site conditionT that have exceeded only " Unusual Event Emergency Action Levels" EPIP-2 Attachment 1, ensure " Emergency Director Checklist

- Unusual Event" Form EPIP-2-1 is completed.

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' ATTACHMENT 1 UNUSUAL EVENT EMERGENCY ACTION I.EVELS 1.0 INITIATING CONDITION INDICATION 1.1 Reactor SCRAM followed by " Reactor SCRAM Contactor Open", alarm, Display J. Panel SF/6F, Window 3-33

' unplanned automatic ECCS initiation and discharge follawed by into Reactor Vessel " Core Spray System 1 On" Alarm, Displ'ay B, Panel 1F/ 2F, window 5-5 and/or __

" Core Spray System 2 On" Alarm, Display C, Panel IF/2F, Window 1-1 12 Radiological effluent Valid Ri Ri Alarm on stack gas Technical Specifications radiation monitor og; a Hi Alarm on 3.6.A or 3.6.B are exceeded Rad Waste Discharge Monitors as verified by sample and analysis.

1.3 Reactor coolant system activity, As indicated by one or more of the activity > 8 uci/ce, but following alarms:

<300 uci/cc a. " Reactor water Hi-Ri Conductivity" Display D, Panel 3F, Window 4-11

b. " Main Steam Line Hi-Radiation" Display H & J

c. "Hi Radiation Of f-Gas", Panel 10F, Window 5-13 and Confirmed by sample analysis 1.4 Reactor pressure exceeds 1110 PSIC, but < 1239 PSIG 1.5 Primary system leak rate approaching technical specification limits

a. Unidentified leak >10 gpm As indicated by: "Drywell Sump Ri Leak Rate" Alarm, window F Panel 3F and verified by recorder, Panel 3F.

b. Total leakage >25 gpa, but As indicated by: "DWEDT Ri Level"

<50 gpe alarm or "Both Pumps Running" alarm and confirmed by leak rate calculation using integrator readings.

1.6 RCS safety / relief valve Indicated by:

failure to close following 1. " Safety Valve or Relief Valve reduction of applicable Not Closed" alarm, Display B, Panel pre ssure 1F/2F Window 4-34 and

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ATTACHMENT 1 (c~nt'd) o UNUSUAL EVENT EMERGENCY . ION LEVELS INITIATING CONDITION INDICATION

2. Edgemeter display on Panel IF/2F and verified by " Relief Valve Discharge / Relief Valve Downconer Temperature Recorder", Panel 10F or AccousticalIbnitoring System.

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1.7 A sustained loss of offsite As indicated by a 1oss of of'!-site power or

' A loss of ons e AC power capa- As indicated by " Emergency Diesel bility Generator #1 Disabled", Winlow 4-28, Panel 8F/9F and " Emergency Diesel Generator

1. 2 Disabled alarms on Pane L 9F, Window 1-7 1.8 Ioss of Containment Integrity Any condition whereby Technical required by other than normal Specification Limit 3.5. A.3 is exceeded in me thod s. the judgement of the GSS and shutdown is required other than in a normal manner.

1.9 Ioss of Engineered Safety Loss of the ability to meet any one of features. the conditions requiring shutdown by Technical Specification Limiting Conditions of Operation and shutdown is required other than in a normal manner.

1.10 Fire in a permanent plant Group Shift Supervisor's judgement.

structure which cannot be controlled by the Fire Brigade within 10' minutes of discovery 1.11 Security threat og attempted Group Shif t Supervisor's judgement.

entry or attempted sabotage 1.12 Natural phenomena being As indicated by any one of the following:

experienced g projected a. Tornado or storm warning with probable beyotd usual levels impact on plant.

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ATTACHMENT 1 (cont'd)

UNUSUAL EVENT EMERGENCY ACTION LEVELS INITIATING CONDITION INDICATION l b. Sustain winds greater than 75 mph as indicated by wind speed recorder, Panel 13R.

c. Flood warning, probable impact on plant,

, closure of evacuation routes.

l d. Earthquake felt in plant 1.13 Other hazards being experienced As indicated by any~ine of the following:

or projected a. Onsite aircraft crash outside protected area not impacting permanent plant structures.

b. Unanticipated explosion detected near ot; onsite.

c. Near or onsite toxic g flanssable gas og liquid release which could affect habitability required for normal plant operation.

d. Turbine rotating component failure causing a reactor SCRAM 1.14 Other plant conditions are Group Shif t Supervisor judges that:

in progress or have occurred a. Plant shutdown is other than normal, which may indicate a potential controlled shutdown degradation of the level of b. Plant is in other than normal condition safety of the plant. during operation and the abnormal condition is of such a nature as to warrant notification (e.g. , cracking is found in reactor coolant piping during operation)

c. Any other condition exists which has the potential for escalation into a higher level of emergency, and, therefore, i warrants notification.

NOTE: In exercising the judgement as to the need for declaring an Unusual Event, uncertainty concerning safety status of the plant, the length of time the uncertainty exists, and the prospects for early resolution of ambiguities should be considered; i.e.,

uncertainty about the level of safety of the plant extending beyond a reasonable time period is a sufficient basis for

(, declaring an Unusual Event.

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Unusual Event EPIP-2 %4 :f 4 Nges Aemsson No. 3 lOate7/20/82  !

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UNUSUAL EVENT EMERGENCY ACTION LEVELS INITIATING CONDITION INDICATION 1.15 Transporation of any contam- As judged by the Group Shif t Supervisor insted or potentially contam-insted injured person of fsite for medical treatment.

1.16 Unanticipated confirmed alarm Group Shift Supervisor judgement based on any two Area Radiation on cause of initiating event and evalua-Monitors simultaneously which tion of plant condition resulting .from cannot be corrected g any initiating event Process Radiation Monitor l

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Form EPIP-2-1 EMERGENCY DIRECTOR CHECKLIST - UNUSUAL EVENT INITIALS 10 EMERGENCY ACTIONS 1.1 The Group Shift Supervisor / Emergency Director is responsible to complete this checklist, initial each action completed or mark N/ A (No t applicable). .

1.2 Upon recognition. that any of the Unusual Event Emergency Action Levels have been exceeded, the Group Shift Supervisor shall assume the duties of Emergency Director.

Da te/ Time /

1.2.1 Announce to Control Room personnel that has assumed the duties of Emergency Director.

1.3 Assign a Conimunicator to make notifications to persons and agencies listed in Form EPIP-2-2 " Notification Checklist -

Unusu'al Event". -

i.4 Announce (or instruct a connounicator to announce) the following message over the Plant Page System:

Sound thu " STATION ALERT ' ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL AN UNUSUAL EVENT HAS BEEN DECLARED.

PERSONNEL SHOULD CONTINUE WITH THEIR NORMAL DUTIES UNLESS FUKrHER INSTRUCTION IS GIVEN

. (REPEAT THE ANNOUNCE.M T) 1.5 Immediately initiate Of fsite Dose Assessment, EPIP-9.

1.6 Notification Messages 1.6.1 Complete Form EPIP-2-3, " Initial No tification Message - Unusual Event" and give it to a communicator for transmission.

NOTE: New Jersey State Police are to be notifed within 15 minutes after the recognition that a Emergency Action Level has been

- exceeded.

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Form EPIP-2-1 (cont'd)

EMERCENCY DIRECTOR CHECKLIST - UNUSUAL EVENT INITIALS 1.6.1.1 Ensure initial notification is received by:

New Jersey State Police (division headquarters, communication center) and Nuclear Regulator Commission Operations Center.

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1.6.2 Complete Form EPIP-2-4 "Institue of Nuclear Power Operations and American Nuclear Insurers, No tification Message - Unusual Event" and give it to a communicator for transmission.

1.6.2.1 Ensure initial notification is received by:

Institute of Nuclear Power Operations (INPO) and American Nuclear Insurers (ANI)

, 1.7 Followup Messages k

1.7.1 Assign personnel to gather information for update message Forms EPIP-2-6 " Additional Information Message - Unusual Event" and EPIP-2-5 "3ureau of Radiation Protection Station Status Checklist -

Unusual Evsnt" 1.7.1.1 Ensure additional information messages are j received by the Nucl, ear Regulatory 1 Commission Operations Center at regular intervals.

1.7.1.2 Ensure Bureau of Radiation Protection Station Status Checklist messages are received (when requested) by the Bureau of Radiation Protection.

1.7.1.3 Provide the facility- contacts from INFO and ANI with information requested when available and/or request assistanece deemed appropriate.

1.7.2 Ensure appropriate follow up actions are initiated in accordance with administrative Procedures 106.1 Reportable Occurrence and/or 126 Procedure for

,- Notification of Station Events.

1.8 As required, initiate (if not previously implemented) the following procedures and ensure all appropriate notifications are completed in a timely manner by a communicator:

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For2 EPIP-2-1 (cont 'd)

EMERGENCY DIRECTOR CHECKLIST - UNUSUAL EVENT INITIAT.S 1.8.1 Personnel Injury EPIP-7. Ensure notifications in 1.8.5.1 thru 1.8.5.5 are completed as appropriate.

1.8.2 Fire EPIP-6. Ensure notifications in 1.8.5.5 thru 1.8.5.7 see completed as appropriate.

1.8.3 Toxic /Flamable Gas Release EPIP-15. Ensure notifications in 1.8.5 are completed as appropriate.

1.E.4 Search and Rescue EPIP-22. Ensure notifications in 1.8.5.1 thru 1.8.5.6 are completed as appropriace.

1.8.5 Notifications and request for offsite assistance (as required).

1.8.5.1 Onsite Medical Department Telephone _

1.8.5.2 tacey First Aid Souad/ Fire Department I Telephone , W 1.8.5.3 Community Memorial- Hospital Telephone , .

Radiation Management Corporation 1.8.5.4 Te lephone

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1.8.5.5 OCNGS Security Department '

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1.8.5.6 Lacey Fire Department f First Aid Squad Telephons ;"'_ ^.2-1.8.5.7 Fire Protection Manager Telephone Primary Of fic-Alternate Beeper n v 1.9 If required, initiate Damage Control Procedure EPIP-14.

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Date / Time 1.10 If radiation levels onsite E of fsite are expected above routinely observed levels initiate the following procedures:

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Form EPIP-2-1 (cont'd)

EbERGENCY DIRECTOR CHECKLIST - UNUSUAL EVENT INITIALS 1.10.2 Emergency Radiological Survey-Onsite, EPIP-10.

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Date Time 1.10.3 Emergency Radiological Survey-Of fsite , EPIP-11.

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Date Time

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1.10.4 Environmental Assesament Command -Center, EPIP-31.

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i Date Time 1.11 E Unusual Event emergency action levels have been exceeded, escalate to the appropriate emergency classification:

Date/ Time of reclassification / -

1.11.1 Alert, EPIP-3.

or 1.11.2 Site Emergency, EPIP-4 or 1.11.3 GeneTa'l Emergency, EPIP-5.

1.12 H recovery requirements have been met, initiate Recovery Phase Procedure EPIP-29. /

Date/ Time 1.13 E no further emergency actions are required terminate the Unusual Event. /

Dat e/ Time 1.13.1 Ensure all 'offsite agencies and CPU Nuclear personnel that were notified of the Unusual Event receive termination notification.

mE

-, -- - _ e *_ _ _ - - __ -- %M -

• Suaiec:: 7-scaourc No.

Unusual Event EPIP-2 Nce I =f 2  %,;,,

b sson No. 3 care 7/20/82

/~

\

FORM EPIP-2-2' NOTIFICATION CHECKLIST - UNUSUAL EVENT l

INITIALS Initial each item upon completion 1

1. With Emergency Directors approval announce the following message over the Plant Page System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATTENTION. ALL_I'ERSONNEL AN UNUSUAL EVENT HAS BEEN DECLARED.

PERSONNEL SHOULD CONTINUE WITH THEIR NORMAL DUTIES UNLESS PURTHER INSTRUCTION IS CIVEN (REPEAT THE ANNOUNCEMENT)

2. No tify the On-Du r.y Shif t Technical . Advisor Primary: , f Alternate: Beeper ,

3. Notify the On-Duty Emergency Director. /

Tean(1) Office * /~ Team (2) Office / Team (3) Office Be epe r / Beeper ,

, / Beeper ,~

~. 1

4. Notify the On-Duty Emergency Advisor NOTE: Ihe Emergency Advisor shall ensure the VP-Nuclear Assurance, the GPU-Nuclear Board of Directors and the 1 GPU-Reading Dispatch Control Center are notified.

Team (l) Offic- Team (2) Office- ~ bea(3) Office -

Be eper -. j Be eperL.- Beeper *

5. Notify the senior Radiological Controls representative on shift.

Primaryi / Al ternate:' /

6. Notify the New Jersey State Police witnin 15 minutes of classification., Transmit " Initial No tification Message - Unusual Even t" EPIP-2-3 with Dnergency Director approval.

Primary: State Hot Line (No tification Line) Cray Phone Alternate: s <

N _

- / (If Primary Is Out of Service)

NorE: IF State Police Verification Call is not received within one minute, re establish contact via State Hot Line and request verification call on the State Police Verification Line immediately.

IF Alternate Verification means is required instruct

, State, Policeg verify by dialing {~ ~ for

} WJ l

. ,- i 4

Lovect: -

Precaoure No.

Unusual Event EPIP-2 714e 2 of 2  %;ee Aension No. 3

• 7/20I82 l

[. -

FORM EPIP-2-2 (cont'd) ,

l NOTIFICATION CHECKLIST - UNUSUAL EVENT INITIALS

7. Notify the OCNGS Manager-Communication Services .

Primary: Beeper , Alternate: Office '

8. Notify the following agencies: Transmit " Institute of Nuclear Power Operations and American Nuclear Insurers Notification Message -

Unusual Event" EPIP-2-4

~

A. Institute of Nuclear Power Operations Tel:

, B. American Nuclear Insurers Tel:

9. Notify the United States Nuclear Regulatory Coc: mission Operations Ce nter Transmit " Initial No tification Message-Unusual Event" EPIP-2-3 Primary: NRC-ENS Line (Lift receiver from cradle) Red Phone Al ternate: (1) Commercial via Bethesda s ., _

(2) Commercial via Silver Spring (3) NRC-HPN Line - Dial 22 or_*22. (ToucitWone]' '

(4) Commercial via Bethesda

- . . .s NorE: Open-line communication with NRC is to be maintanined on ENS Line throughout the emergency situation.

10. When requested, by the Bureau of Radiation Pro tection (BRP) transmit " Bureau of Radiation Protection Station Status Checklist -

Unusual Event" EPIP-2-4 via, the BRP Inf ormation Line located in the Emergency Command Center (Group Shif t Supervisors Office)

11. Transmit addition information messages to the Nuclear Regulatory Commission and other agencies as directed by the Emergency Director using " Additional Information Message - Unusual Event"

• EPIP-2-6.

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EPIP-2 gg, 1 ,, i gg,,

' 4.nsion No. ste

- 3 7/20/82

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FORM EPIP-2-3 INITIAL NOTIFICATION MESSAGE - UNUSUAL EVENT MESSAGE WILL BEGIN ANT EUD WITH:

s'

! (Cirele One) THIS IS NM AN EXERCISE - I REPEAT - THIS IS NOT AN EXERCISE I

OR J rdIS IS A DRILL 7 THIS IS A DRILL 5 THIS IS - - -

(Name) (Title) .

AT OYSTER CREEK NUCLEAR GENERATING STATION

THIS IS A NOTIFICATION OF AN UNUSUAL EVENT CLASSIFICATION ON

THIS EVENT WAS CLASSIFIED AT ( Date)

(Time - 24 hr. clock) ,

{l _ _ _ _ _ _ _

! [ ] THERE IS NO RELEASE IN PROGRESS f

i [ ] WE HAVE A CONTROLLED RELEASE IN PROGRESS

-[ ] WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS

[ ] NO PROTECTIVE ACTION 3 ARE RECOMMENDED i

. [ ] WE RECOMMEND SHELTERING FOR THE FOLLOWING DIRECTIONAL I SECTOR (S )

f

[ ] WE RECOMMEND EVACUATION FOR THE FOLLOWING DI.IECTIONAL SECTOR (S)

APPROVED

• EMERGENCY DIRECTOR DATE TIME-24 HR l - - - -

TIME NOTIFIED / VERIFIED

' THIS MESSAGE HAS BEEN TRANSMITTED TO:

/ NEW JERSEY STATE POLICE via State Hot Line (Gray Phone)

/ UNITED STATES NUCLEAR REGULATORY COMMISSION via NRC-ENS Line (Red Phone)

(DATE) (COMMUNICATOR) k NOTE: VERIFICATION OF MESSAGE IS COMPLETE ONLY AFTER RECEIVING AGENCY H RESTATED MESSAGE CORRECTLY IN ITS ENTIRETY BACK TO THE OYSTER COMMUNICAIOR l-4,- ~ ...

m_. m . . . __ __

e - . , ,

Susper: Nesows No.

Unusual Event EPIP-2 h48 1 :f i %s Monsson ***

No. 3 7/20/82 s.

FORM EPIP-2-4 l

INSTITUTE OF NUCLEAR POWER OPERATIONS & AMERICAN NUCLEAR INSURERS NOTIFICATION MESSAGE - UNUSUAL EVENT

1. This is at Oyster Creek (Name/Ti tle)

Nuclear Generating Station. An Unusual Event was declared in

~~

accordance with nur Emergency Plan at /

(Time) / (Date)

2. Description of Emergency:

3. Assistatee requested:

4. Approved  ;

(Dnergency Director)

(Date) (Time)

Time

5. Transmitted To: Insitute of Nuclear Power Operations , 7' To: American Nuclear Insurers

.,' '/'

~ ./

(Communicator) (Date)

/

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Suaess:: Wecseurs No.

Unusual Event EPIP-2 8 sge 1 af 2 se:se 1

Monmon MA Oa:s 3 7/20/82

( %. -

FORM EPIP-2-5 ,

BUREAU OF RADIATION PROTECTION STATION STATUS CHECKLIST - UNUSUAL EVENT

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

' 2. Accident Classification: UNUSUAL EVENT

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

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

5. Is Re: Actor Shutdown: (circle one) Yes No

6. Gaseous Release Information (a) Release Tenninated: (circle one) Yes No (b) Estimated Duration of Release: Hours

(

(c) Type of Gaseous Release (circle one) Elevated Ground (d) Windspeed sph m/sec From: (0) Toward (0)

(e) Wind Direction: (Compass Point)

Affected Sector:

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

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

7. Liquid Release Information Ye s No (a) Release Terminated (circle one)

(b) Estimated Duration of Release: Hours (c) Estimated Release Concentration uC1/cc gpm (d) Release Rate d

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hm*8K Noesews s Unusual Event EPIP-2 Ne 2 ' :f 2  %**

4ension No. 2 cts 3 7/20/82

\

FORM EPIP-2-5 (cont'd)

8. Projected Of fsite Doses (a) Whole Body Di s cance (Miles) Dose Rate mrem /hr Time to Reach PAG (hrs.)

1.

2.

3.

4.

S.

~

(b) Child Thyroid Distance kilos) Dose Rate Rem /hr Time to Reach PAG (hrs.)

1.'

2.

3.

4.

S. -

9. Recommended Protective Actions:

(

10. Status checklist approved for ' transmission to NJBRP by Emergency

. Director / Emergency Support Director:

/

(Signature) ( Date/ Time)

11. Status Checklist transmitted to NJBRP:

Transmitted to:

( Name)

/

(OCNGS Conununicator) (Location) ( Dat e/ Time) l t

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W* '

Poosewe No, l Unusual Event EPIP-2 3, I g3  %

Amason No. Oate i f- 3 7/20/82 l

\

FORM EPIP-2-6 i

ADDITIONAL INFORMATION MESSAGE - UNUSUAL EVENT  !

Check ([) all appropriate statements to be transmitted as information is available.

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

Director at Oyster Creek Nuclear Generating Station. The following is provided as additional information for the initial notification of Unusual Event.

^

2. DATE/ TIME OF CLASSIFICATION

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

b. Date: Month Day Year

3. Plant Status

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

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.

4. Type of release (circle one) airborne; liquid; surface soil.

5. Meteorological Data

a. Wind speed MPH '

b. Wind direction ( from) (toward)

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

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

6. Caseous Radiological Data

a. Noble gas release rate uCi/sec

b. Iodine 131 release rate uCi/see

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

d. Actual or estimated duration of release:

(

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

%esesr. Poesewe Na Unusua1 Event EPIP-2 *tta 2:f3 sages Revision NS 2ste 1 3 7/20/82 I

(

FORM EPIP-2-6 (cont'd)

7. Liquid Radiological Data

a. Release concentration uCi/cc

b. Release rate uCi/sec

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

d. Actual or estimated duration of release

e. Es timated total release uCi

8. Projected dose rates and integrated dose (Based on_ actual or --- -- - -

projected duration of release) --

Whole Body

a. Site Boundary ar/hr mrem

b. 2 miles ar/hr mrem

c. 5 miles ar/hr mrem

d. 10 miles mr/hr mrem

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

TRYROID

a. Site Boundary uCi/cc __ mrem

b. 2 miles uCi/cc mrem

c. 5 miles uCi/cc mrem

d. 10 miles uCi/cc mRam

10. Estimate of Surface contamination dpm/100 cm2 (obtain from field date) mrem /hr

11. Emergency Actions in progess:

a. Radiological survey teams onsite 1

t b. Radiological survey teams offsite

c. Onsite fire brigade

d. Of fsite fire department

e. Damage Control

f. Firs t aid teams onsite

g. Ambulance service

h. Medical support

i. Environmental surveys offsite

j. Othe r, specify

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EPIP-2 %4ee Unusual Event

% sson No. :ste I 3 7/20/82 l

, r' i

i FORM EPIP-2-6 (cont'd)

12. Additional support required (specify) i

13. The condition may change to an (circ le one) Alert; Site Emergency; General Emergency

- 14. Of fsite population sector (s) (refer to Emergency Planning Zone

)

Sector map) affected are ,

I ,

e s

! 15. Ihe following changes in protective measures are recommended for

! the population in these sectors.

! a. None Notify (projected offsite dose )

b.

Take shelter (projected offsite dose )

c.

Evacuate (projected offsite dose )

! d.

16. Approved (Emergency Director) l 1

(Time)

( Date) ]

17. Transmitted To: TIME: NOTIFIED / VERIFIED.

a. United States Nuclear Regulatory

/

Comaisaion.

b. New Jersey Bureau of Radiation

/

Protection.

l /

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d.

(Communicator) ( Date) l

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i-__ i_ _ _ _ _ - __ ,.

4 . .

3 ..

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Procecure No.

EPir-3 Pase i et 3 Cate issued ctfecitve Cate j , Jersey Central 2/23/81 <enus23 e/2us2

'. Power & Light Company Revision No. l Cate  !

Autncnzec Sy Director-Station Operations l i ^""*J"*"f' d' a,caff 0 Oyster Creek Nuclear Generat tation V

]

i LIST OF EFFECTIVE PAGES DATE '

REVISION NUMBER l 1 7/ 21/82 ~ ~3  !

2 7/ 21/ 8 2 3 3 7/21/82 3 i

ATTACHMENTS Attachment 1 (4 pages) 7/21/$ 2 3 i Fom EPIP-3-1 (5 pages) 7/ 21/8 2 3 Fom EPIP-3-2 (2 pages) __. 7 / 21 / 8 2 3 For:n EPIP-3-3 (1 page) 7/ 21/82 3

Form EPIP-3-4 (1 page) 7 / 21 / 8 2 3 Form EPIP-3-5 (2 pager) 7/21/82 3 j Form EPIP-3-6 (3 pages) 7/21/8 2 3 4 .

h i

! 'N O N C O i, i,ot;3,g,,, =; O LL E D

This pocumen i Up To Date

- ~ -

- ' ~ ~

j . .

s .

w P*ocoows No.

Alert EPIP-3 as ge 2 :f 3 setse 4ension No. 3 2ote 7/21/82

)

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

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

i .

?

1.1.2 Ensure necessary actions are taken to notify offsite 1

emergency response organizations.

i

1.1.3 Mobilize the appropriate portions of the e,mergency response o rganization to initiate apprqpyiate emergency actions.

2.0 REFERENCES

s 2.1 OCNGS Emergency Plan i

j 2.2 NUREG-0654 Re v. 1; FEMA-REP-1 " Criteria for Preparation and j Evaluation of Radiological Emergency Response Plans and Preparedness

in support of Nuclear Power Plants".

2.3 OCNGS Emergency Plan Implementing Procedures (EPIP)

F b

2.3.1 EPIP-1 dlassification, of Emergency Conditions t

. 2'.3.2 EPIP-2 Unusual Event 2.3.3 EPIP-4 Site Emergency l

l 2.3.4 EPIP-5 General Emergency I

3.0 RESPONSIBILITIES

( 3.1 The Emerg ency Director is responsible for implenenting this procedure. -

3.2 Emergency Director responsibilities that may NOT be delegated include :

3.2.1 Decision to notify offsite emergency management agencies.

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

j 3.2.3 Classification of Emergency Event.

3.2.4 Determining the necessity for onsite accountability and/or evacuation based upon potential exposure to non-essential personnel.

i

, s. 3.2.5 Authorization for emergency workers to exceed 10 CFR 20

( radiation exposure limits.

? .

l Susper: Noceewe Ne, Alert EPIP-3

% 3 sf 3  %

Monmon No. 3 Oefe 7/21/82 4

4.0 PREREQUISITES l

4.1 The Site is in a condition that warrants Alert declaration as

! defined by this procedure as judged by the Group Shift Supervisor / Emergency Director.

5.0 REQUIREMENTS 5.1 Emergency Actions 5.1.1 The Group Shif t Supervisor / Emergency Director shall, upon recognition of inplant or site conditions that have exceeded " Alert Emergency Action Levels" EPIP-3 Attachment I and no emergency action level of a higher classification, ensure " Emergency Director Checklist -

Alert" Form EPIP-3-1 is completed.

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Alert epro-1 Nga , of sages 4enman Nm Oate 1 3 7/21/8 2 I f

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(j ATTACHMENT 1 ALERT EMERGENCY ACTION LEVELS I 1.0 EMERGENCY ACTION LEVELS l

INITIATING CONDITION INDICATION 1.1 Fuel cladding degradation As indicated by the following:

(Reactor coolant system Total a. "Off-Gas Hi Radiation Alarm",

1 5

Iodine activity >300 uci/cc) Panel 10F, Window 5-12, and confirmed by sample ar. analysis

b. Of f gas Air Ejector nonitors indicate > 10,000 m /hr 1.2 Reactor Pressure exceeds As indicated by followiag alarms:

1239 PSIG, but 41373 PSIG a. " Safety or Relief Valve not Closed" Display B, lanel IF/2F, j Window 4-34 and verified by

?,

" Steam Flow Steam Pressure Recorder:, Panel 5F/6F.

1.3 Steam Line break with Indicated by:

MSIV malfunction causing a. Alarms on any Turbine Building

, leakage into Turbine radiation monitor h Building b. " Main Steam Valves Of f Normal" f alarm, Window G. Panel 3F, f Window 5-17

[ c. Both " CLOSED" and "0 PEN" indication for MSIV's, Panel 11F.

l l

1.4 Raactor coolant system leak As computed from drywell equipment exceeds 50 GPM but not drain tank readings plus gallons 100 GPM cg; causes or requires pumped from drywell sump per the Reactor to be scrammed elapsed time.

1.5 Increased radiation or Valid area radiation monitoring airborne levels within system indications and confirmed by the plant indicating a sample analysis or, direct severe degradation of monitoring .

control of radioactive ~

l materials (increase by a factor of 1000 or more) l 1.6 Loss of all Of fsite power As indicated by a reactor scram coincident with a loss of caused by a loss of power and a diesel generators for less disabled alarm on both diesel l than 15 minutes. generators, neither of which energizes the IC and ID 4160V busses.

i Alert N3 Swa 2 af 4 sums menmon No. 3 are 7/21/82

(

ATTACHMENT I (con't'd) I ALERT EMERCENCY ACTION LEVELS 1.7 Loss of all Onsite DC power All battery voltmeters read zero for less than 15 minutes in the " Station Battery Position",

Panel 8F/9F, and there is no light or control power available.

1.8 Complete loss of any As indicated by total loss of any of function needed for the following:

plant cold shutdown a. Source and iqtermediate range when cold shutdown nuclear instrumentation.

is required. b. Reactor coolant flow and Shutdown Coolant Pumps coincident with loss of other means of main-taining reactor coolant temperature less than 2120 F.

1.9 Failure of a eactor pro- Any reactor scram setpoint being tection system to initiate exceeded with:

and comp 1.ete a scram which a. No " Scram Sole,noids-De-Energized" brings the reactor suberitical lights on Panel 4F.

when callad for. ,

b. The Neutron Monitoring System indicating the reactor is not su bcritical.

c. See Procedure 506.5 1.10 Release or loss of control Indicated by one of the following of radioactive material valid conditions:

within the plant from fuel a. " Fuel Pool Hi Radiation Alarm",

handling accident. Panel 10F, Window 2-10

b. "Reacto.- Operating Flocr Hi Radiation Alarm", Panel 10F, Window 1-9

c. " Reactor Bldg. Ventilation Hi Radiation Alarm", Panel 10F, window 7-23 or

d. Direct RadiationI readingJ or sample analysis. (increase by a factor of 1000 or more) 1.11 Fire potentially affecting As judged by the Group Shift Supervisor the operability of any based on his assessments.

safety system.

1.12 Sustain loss of all or most As judged by the Group Shift Supervisor annunciators in the Control based on his assessments.

Room.

-w. . ~ .mm

• *em* = s4 m w* -m>venei%p- -geus,m.,a 5 4 , s

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p Nemoure No.

l Alert EPIP-3 %4e 3 :f 4 %ges i

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4enmon Na 3 :ste 7/21/82 l j \

g es _

ATTACHMENT 1 (con't'd)

ALERT EMERGENCY ACTION LEVELS 1.13 Radioactive effluents exceed As indicated by any of the following 10 times Technical Specifi- validated alarms and confirmed by sample l cation 3.6A or 3.6B and analysis:

a. " Stack Gas Hi-Hi Radiation Alarms",

Panel 10F, Window 4-4

b. " Radioactive Waste Discharge Monitor Hi Alarm", Panel 10F, Windov 8-24 or 8-32. __

c. " Service Water Discha.ge Monitor Hi-Hi", Panel IR

d. " Emergency Condenser Vent Hi Radiation Alarm", Panel 10F, Window 7-7 or 7-15

e. " Containment Spray Hi Radiation Alarm",

Panel 10F, Window 8-8 or 8-16

f. Actual or projected integrated doses offsite exceed 10 mrem whole body o_r, r 50 mrem to the child thyroid.

J.14 Ongoing security' compromise As judged by the Group Shif t Supervisor 1.15 Severe natural phenomenon As indicated by any of the following:

being experienced. a. Tornado strikes facility

b. Sustain wind speed greater than 100 mph as indicated by Wicd Speed Recorder, Panel BR

c. Flood or, low water level potentially affecting operation of safe shutdown equipment when required to operate.

d. Earthquake affecting plant opers'. ion.

1.16 Other hazards being experienced As indicated by any of the following:

a. Aircraf t crash or missile impact within the protected area.

b. Known explosion damage affecting

( plant operation.

c. Entry of toxic or, flammable gasses into the plant which, in the judgement of the Group Shif t Supervisor, affects the safe operation of the plant.

d. Turbine failure resulting in casing penetration.

l l

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Suetecr: hecsewe No.

Alert EPlP-3 m4 :y 4  %

Menson NS 3 Oare 7/21/82 -

s ATTACH'fENT 1 '(cont ' d)

ALERT EMERGENCY ACTION LEVELS 1.17 Other plant conditions are As judged by the Group Shift Supervisor /

in progress or have occurred Emergency Director which may involve an actual or potential substantial degradation of the level of safety of the plant.

NOTE: In exercising the judgement as to the need for declaring an Alert, uncertainty concerning safety status of the plant, the length of time the uncertainty exists, and the prospects for early resolution of ambiguities, and the potential for substantial

, degradation of the level of safety of i the plant should be considered; i.e.,

uncertainty as to the existence of substantial degradation of the level of safety of the plant extending beyond a reasonable time period is a sufficient basis for declaring an Alert.

1.18 Evacuation of Control Room As judged by the Group Shift Supervisor i

anticipated or required with control of shutdown systems ,

established from local stations within 15 minutes.

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• Alert DD* 3" 1 1 5

%ges l Hoe :f aweson No. 3 Oate 7/21/82 l

l Form EPIP-3-1 EMERGENCY DIRECTOR CHECKLIST - ALERT INITIALS 1.0 EMERGENCY ACTIONS 1.1 The Group Shift Supervisor /Emerg ency Director is responsible j to complete this checklist, initial each action completed or mark N/A (No t applicable).-

1.2 Upon recognition of site conditions that require declaration of Alert Clas sification, the " Group Shift Supervisor shall assume the duties of Emergency Directcr.

Da te/ Time /

1.2.1 Announce to Control Room personnel that has assumed the duties of Baergency Director.

1.3 Assign a Communicator to make notifications to persons and agencies listed in Form EPIP-3-2 " Notification Checklist -

Ale rt" .

1.3.1 Provide the communicator with the Record-a phone message deemed appropriate.

~

1.4 Announce (or instruct a communicator to announen) appropriate lines of the following message over the Plant Page System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL AN ALERT HAS BEEN DECLARED.

ALL ON-DUTY INITIAL EMERGENCY RESPONSE TEAM PERSONNEL REPoltf TO EMERGENCY CENTERS.

ALL OTHER PERSONNEL AWAIT FURTHER INSTRUCTIONS.

EATING, DRINKING, AND SMOKING IS PROHIBITED UNTIL FURTHER NOTICE.

(REPEAT THE ANNOUNCEMENT) 1.5 Immediately initiate Offsite Dose Assessment, EPIP-9. i w=- m-e sA-e m, a

e 7.oceewe No.

Ale rt EPIP-3 2

% 3 5 m, hesen .N o. 3 ste 7/21/82 {

(- ,

Form EPIP-3-1 (cont 'd)

EMERGENCY DIRECTOR CHECKLIST - ALERT INITIALS 1.6 Emergency Support Centers Activated:

1.6.1 Ensure the pagers of the On-Duty Initial Emergency Response Team have been activated by Security.

1.6.2 Ensure Security has unlocked and open the Emergency Centers.

1.6.3 Technical Support Center, EPIP-26 Time Operational 1.6.4 Operation Support Center, EPIP-27 Time Operational 1.6.5 Environmental Assessment Command Center, EPIP-31 Time Operational 1.7 Notification Messages 1.7.1 Complete Form EPIP-3-3 " Initial No tification Message-Alert" and give it to a communicator for transmission.

NOTE: New Jersey State Police are to be notifed with,in 15 minutes after the recongnition that an Emergency Ac tion Level has been exceeded.

1.7.1.1 Ensure initial notification is received by:

New Jersey State Police (division headquarters, communication center) and Nuclear Regulator Commission Operations Center.

1.7.2 Complete Form EPIP-3-4 "Institue of Nuclear Power Operations and American Nuclear Insurers, No tification Message - Alert" and give it to a communicator for transmission.

1.7.2.1 Ensure initial notification is received by:

Institute of Nuclear Power Operations (INPO) and American Nuclear Insurers (ANI)

\.

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, - 7

+ 6 Susiec . Procacura No. -

Alert gp tp _3 AMe3 :f5 Nc;ss Mensson No. Ocre 3 7/21/82

( '

l Form EPIP-3-1 (cont 'd) t EMERGENCY DIRECTOR CHECKLIST - ALERT INITIALS 1.8 Followup Messages 1.8.1 As sign personnel to gather information for update message Forms EPIP-3-6 " Additional Information Message - Al ert" and EPIP-3-5 " Bureau of Radiation Protection Station Status Checklist - Ale rt" 1.8.1.1 Ensure additional inf2.Unation messages are received by the Nuclear Regulatory Co mmission Operations Ce nter at regular intervals.

1.8.1.2 Ensure Bureau of Radiation Protection Station Status Checklist messages are received (when requested) by the Bureau of Radiation Protection.

1.8.1.3 Provide the facility contacts from INPO and ANI with information requested when available and/or request assistance deemed appropriate.

1.8.2 Ensure appropriate followup actions are initiated in acco rdance with administrative Procedures 106.1 Re port 91e Occurrence and/or 126 Procedure for Notif* . ion of Station Events.

1.9 As required, initiate (if not previously implemented) the following procedures and ensure all appropriate notifications are completed in a timely manner by a communicator:

l 1.9.1 Personnel Injury EPIP-7. Ensure notifications in 1.9.5.1 thru 1.9.5.5 are complete.d as appropriate.

[ 1.9.2 Fire EPIP-8. Ensure notifications in 1.9.5.5 thru 1.9.5.7 are completed as appropriate.

l l 1.9.3 Toxic / Flammable Gas Release ~ EPIP-15. Ensure notifications in 1.9.5 are completed as appropriate.

1.9.4 Search and Rescue EPIP-22. Ensu re notifications in 1.9.5.1 thru 1.9.5.6 are completed as appropriate.

1.9.5 Notifications and request for offsite assistance (as required).

4. 1.9.5.1 Onsite Medical . Department f i Telephone , ~/

Suaidc::* Ncacuta No.

Ale rt EPIP-3 i%te 4 af 5 %;ss Aemsson No. Cate 3 7/21/82

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Form EPIP-3-1 (cont 'd)

EMERGENCY DIRECTOR CHECKLIST - ALERT INITIALS 1.9.5.2 Lacey First Aid Squad / Fire Department Telephone _

1.9.5.3 Community Memorial Hospital Telephone _

1.9.5.4 Radiaiton Management Corporatio n Telephone _. . . ,

1.9.5.5 OCNCS Security Departmert. '

Telephone , .-

1.9.5.6 Lacey Fire Department /First Aid Squad Telephone g 1.9.5.7 Fire Protection Manager NOTE: Beeper activated with Initial Emergency Response Team beepers.

1.10 Initiate the' following procedures and continually monitor repo rts :

1.10.1 Emergency Radiological Survey - Onsite, EPIP-10.

/

Da te Time 1.10.2 Emergency Radiological Survey - Of fsite, EPIP-ll.

/

Date Time 1.11 Emergency Directors discretion, to f.nitiate the following l

procedures:

1.11.1 Personnel Accountability, EPIP-12. /

Date/ Time 1.11.1.1 Ensure immediate notifications are made to:

l ,

A. OCNGS Security Department via Primary: Darit Green Phone, Dial Code Alternate: Tele ph'one

B. Station Personnel via Plant page system per EPIP-12 1.11.1.2 If no personnel accountability report' is

( received within 30 minutes initiation, contact Station Security for a after status report .

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Alert EPIP-3 Na$ of 5 s ,;

hvision No.

3 7/21/82

(-

i Forn EPIP-3-1 (cont'd)

EMERGENCY DIRECTOR CHECKLIST - ALERT l INITIALS i

1.11.1.3 Report of personnel accountability completion received, personnel unaccounted for.

1.11.2 If personnel are unaccounted for, implement Search and Rescue, EPIP-22. Ensure notifications in 1.9.4 l are completed. Da te/ Time /

1.11.3 Site Evacuation, EPIP-13. Date/ Time /

1.11.4 Damage Control EPIP-14. Da te/ Time /

1.11.5 Emergency Dosimetry, EPIP-19. Date/ Time /

1.11. f. Thyroid Blocking , EPIP-23. Da te/ Time /

f 1.11.7 Emergency Respiratory Equipment, EPIP-24.

Da te/ Time /

1.12 E enorgency action levels exceed those for an Alert, escalate to the appropriate emergency classification: ,

Date/ Time of reclassification /

1.12.1 Site Emergency, EPIP-4.

or 1.12.2 CeneEl Emergency, EPIP-5.

1.13 E recovery conditions have not been met and Alert Emergency Action levels are no longer being exceeded, de-escalate to an Unusual Event emergency classification by performing notifications required by EPIP-2. Date / Time /

1.14 H recovery phase conditions have been met, initiate the Recovery Phase in accordance with EPIP-29.

Date/ Time /

1.15 g no further emergency actions are required, terminate the Ale rt . Date/ Time /

1.15.1 Ensure all offsite agencies and GPU Nuclear personnel notified of the Alert receive temination notification.

\

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a 5%,c:: P.cerurs No.

Alert EPIP-3 pg, 1 g 2 g,

% sion N o. 3 Cars 7/21/82 i

u FORM EPIP-3-2 ^

NOTIFICATION CHECKLIST - ALERT INITIALS Initial each item upon completion

1. With Emergency Directors approval announce appropriate lines of the following message over the Plant Page System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATTENTION A,LL, PERSONNEL AN ALERT RAS BEEN DECLARED. .

ALL ON-DUTY INITIAL EMERGENCY RESPONSE TEAM PERSONNEL REPORT TO EMERGENCY CENTERS.

ALL OTHER PERSONNEL AWAIT FURTHER INSTRUCTIONS.

EAT 7NG, DRINKING, AND SMOKING IS PROHIBITIED UNTIL FURTHER NOTICE.

. (REPEAT THE ANNO.UNCEMENT)

2. Notify OCNGS Se curity, direct them to activate the Record-a phone with the appropriate message,. activate the pagers of the Initial Emergency Response Te am on duty and unlock the TSC, OSC, & EACC.

NOTE: The Emergency Advisor shall ensure the VP-Nuclear Assurance, the CPU-Nuclear Board of Directors and the CPU-Reading Dispatch Control Center are notified.

Primary: Station Security / Accountability Line Dark Green Phone, Dial Code l Alternate: Ext.~

~ .-

~

3. Notify the New Jersey ~ State Police within 15 minutes of classification. Transmit " Initial Notification Message -

Alert" EPIP-3-3 with Emergency Director approval. " ' '

, Primary: State Hot Line (Notification Line) Gray Phone l Alterna te : ~

, ') Primary Is Out of Service)

/ (If NorE: IF State Police Verification Call is not received l

within one minute, re-establish contact via State Hot Line and request verification call'on the State Police Verification Line immediately.

IF Alternate Verification means is reauired instruct

( State,Polgto verify by dialing ' ]>o'r N. j D

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FORM EPIP-3-2 (cont 'd)

NOTIFICATION CHECKLIST - ALERT INITIALS

4. Notify the following agencies: Transmit " Institute of Nuclear Power Operations and Ame rican Nuclear Insurers Notifica tion Message - Alert" EPIP-3-4 A. Institute of Nuclear Power Operations Tel: ,

3. American Nuclear Insurers Tel: _

5. Notify the United States Nuclear Regulatory Commission Operations Center Transmit " Initial No tification Message-Alert" EPIP-3-3 Prima ry: NRC-ENS Line (Lif t receiver from cradle) Red Phone Al terna te: (1) Commercial via Bethesda s

}

(2) Commercial via. Silver Sprinx )

(3) NRC-HPN Line - Dial .. 1 (4) Commercial via Bethesda~ , _

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

6. .When requested, by the Bureau of Radiation Protection (BRP) transmit " Bureau of Radia tion Protection Station Status Checklist - Al ert" EPIP-3-5 via, the BRP Information Line located in the Emergency Command Center (Group Shift Supervisors Office)' ,

7. Transmit additional information messages to the Nuclea r Regulatory Commission and other agencies as directed by the Emerg ency Director using " Additional Inf ormation Message -

Alart" EPIP-3-6.

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Alert re v o _, 4 98 3 af 1 kges

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FORM EPIP-3-3 j INITIAL NOTIFICATION MESSAGE - ALERT MESSAGE WILL BEGIN AND END WITH:

l (CIRCLE ONE) THIS IS NOT AN EXERCISE - I REPEAT - THIS IS NOT AN EXERCISE OR THIS IS A DRILL - THIS IS A DRILL THIS IS (Name) (Titie) ,,

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

THIS EVENT WAS CLASSIFIED AT ON (Time - 24 hr. clock) ( Date)

[ ] THERE IS NO RELEASE IN PROGRESS

( ] WE HAVE A CONTROLLED RELEASE IN PROGRESS ..

[ ] WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS

( ] NO PROTECTIVE ACTIONS ARE RECOMMENDED

() WE RECOMMEND SHELTERING FOR THE FOLLOWING DIRECTIONAL SECTOR (S)

( ) WE RECOMMEND EVACUATION FOR THE FOLIDWING DIRECTIONAL SECTOR (S)

APPROVED EMERGENCY DIRECTOR DAIE TLE-24 HR TIME NOTIFIED / VERIFIED THIS MESSAGE HAS BEEN TRANSMITTED TO:

/ NEW JERSEY STATE POLICE via State Hot Line (Gray Phone)

/ UNITED STATES NUCLEAR REGULATORY COMMISSION via NRC-ENS Line (2ed Phone) r (DATE) (COMMUNICATOR)

\ NOIE: VERIFICATION OF MESSAGE IS COMPLETE ONLY AFTER RECEIVING AGENCY HAS RESTATED MESSAGE CORRECTLY IN ITS ENTIRETY BACK TO THE OYSTER CREEK COMMUNICATOR

~

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Alert EPIP--3 h18 1 3f 1 ht**

Mewsson N o. Oate f -

FORM EFTP-3-4 j

INSTITUTE OF NUCLEAR POWER OPERATIONS & AMERICAN NUCLEAR INSURERS NOTIFICATION MESSAGE - ALERT

1. This is at Oyster Creek (Name/Ti tle)

Nuclear Generating Station. An Alert was declared in accordance with our Emergency Plan at /

(Time) / ( Date)

2. Description of Emergency:

3. Assistance requested:

)

4. Ap proved (Emergency Director / Emergency Support Director)

(Date) (Time) t Time

5. Transmitted To: Insitute of Nuclear Power Operations _ ]/~

l To: American Nuclear Insurers

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(Communicato r) ( Dat e )

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FORM EPIP-3-5 BUREAU OF RADIATION PROTECTION STATION STATUS CHECKLIST - ALERT

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

2. Accident Classification: ALERT

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

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

~~

t 5.. Is Reactor Shutdown: (circle one) Ye s No

6. Gaseous Release Information (a) Release Terminated: (circle one) Yes No (b) Estimated Duriation of Release: Hours (c) Type of Gaseous Release (circle one) Elevated Ground (d) Windspeed sph m/sec (e) Wind Direction: From: (0) Toward (0)

Af fected Sector: (Compass Point)

(f) Stability Class: (circle one) Unstable Neutral Stable (g) Release Rate Noble Gas: C1/Sec.

(h) Release Rate Iodine (if known) C1/Sec.

7. Liquid Release Information (a) Release Terminated (circle one) Ye s No (b) Estimated Duration of Release: Hours (c) Estimated Release Concentration uC1/cc (d) Release Rate gpm k.

W

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FORM EPIP-3-5 (cont'd)

, 8. Projected Offsite Doses (a) Whole Body i.

Distance Miles) Do se Ra te mrem /h r Time to Reach PAC (hrs.)

1.

2.

3.

4.

5. .

(b) Child Thyroid Distance Miles) Dose Rate Rem /hr Time to Reach PAC (hrs.)

1.

2. -

3.

4.

5.

9. Reconcended Protective Actions:

(

10. Status Checklist ' approved for transmission to NJBRP by Emerg ency Director / Emergency Support Director:

(Signature) ( Date/ Time)

11. Status checklist transmitted to NJBRP:

i Transmitted to:

l

, (Name) t i

(OCNGS Contmunicator) (Location) ( Dat e/ Time) 1 I

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• • oceewe No, Alert EPIP-3 hoe 1 31 3 he;os

'"N 3 :ste 7/21/82 l s t FORM EPIP-3-6 ADDITIONAL INFORMATION MESSAGE - ALERT j Check (/) all appropriate statements to be transmitted j as infomation is available.

4

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

} (Emergency Director) f d

Director at Oyster Creek Nu cles r Gene ra ting Station. The following is provided as additional information for the initial

! notification of Alert.

2. DATE/ TIME OF CLASSIFICATION

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

b. Date: Month Day Yea r 3.. Plant Status

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

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.

4. Type of release (circle one) airborne: liquid; surface soil.

( 5. Meteorological Data

a. Wind speed MP H

b. Wind direction ( from) (towa rd)

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

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

6. Gaseous Radiological Da ta l a.. Noble gas release rate uCi/sec

! b. Iodine 131 release rate uCi/sec

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

d. Actual or estimated duration of release:

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Alert

_EPIP-3 8 vie 2 8f 3 83:ss 3 7 / 21/ 8 2 l

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FORM EPIP-3-6 (cont'd) I

7. Liquid Radiological Data

a. Release concentration uCi/cc

b. Release rate uCi/sec

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

d. Actual or estimated duration of release

e. Estimated total release uCi . .

8. Projected dose rates and integrated dose '- ( Based _ on actual or projected duration of release) -

1/ hole Bedy

a. Site Boundary ar/hr mrem

b. 2 miles ar/hr mrem

c. 5 miles ar/h r. mrem

d. 10 miles ar/hr mrem

9. Projected Iodine Co ncentt c tion and Integrated Dose Co nniement (Based on actual or projectea duration of release).

THYROID

a. Site Boundary uCi/cc mrem

b. 2 miles uCi/cc mrem

c. 5 miles uC1/c c m8 tem

d. 10 miles uCi/cc mrem

10. Es timate of Surface contamination dpm/100 cm (obtain from field date) mrem /h r

11. Emergency Actionc in progess:

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 i

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l FORM EPIP-3-6 (cont'd) {

f

13. Additional support required (specify) l

! 14. The condition may change to an (circle ene) Unusual Event; I

i _'ite Emergency; General Emergency f

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

{ Zone Sector map) affected are ,

l . .

i ,

l

16. Ihe following changes in protective measures are recommende d i

t for the population in 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) i l ,

( Dat e) (Time)

18. Transmitted To: TIME: NOTIFIED / VERIFIED.

a. United States Nuclear Regulatory Commission. /.

b. New Jersey Bureau of Radiation Protection. /

i c. /

i i d. /

(Communicator) ( Dat e) 1

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i Procedure No. 1 EP IP-4 l P3qe IOf 3 Cate issued 7.-

Jersey Central 2/23/81 I' Effecuve Cate carn es23 s/2us2 Power & Light Company sevisief No. l Cate 77 pg

Subject:

Site Faergency I Autnenzec Sy Director-Station Operations 1

M/// I rc Oyster Creek Nuclear Ge ing Station ff I

i l LIST OF EFFECTIVE PAGES DATE REVISIQti NIMBER l 1 7/ 21/8 2 3 1

, 2 7/n/82 3 i

3 7/ 21/82 3 i

ATTACHMENTS l Attachment 1 (5 pages) 7 /21 / 8 2 3 Fom EPIP-4-1 (6 pages)

( 7/ 21 /8 2 3

Fom EPIP-4-2. (2 pages) 7/21 /8 2 3 Fom EPIP-4-3 (1 page) 7/ 21/8 2 3 Fom EPIP-4-4 (1 page) 7 /21 / 8 2 3 Fom EPIP-4-5 (2 pages). 7/ 21/8 2 3 Fom EPIP-4-6 (3 pages) 7 /21 / 8 2 3 NON-CONTROLLED This Document Will Not Be Kept

- ~~

Up To Date n'

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Site Emergency EPIP-4 Nga 2 f 3 8 mise amsson No. Ne

] 3 7 /21/ 8 2 1.0 PURPOSE 1.1 The purpose of this procedure is to defino the conditions that shall be regarded as a Site Emergency for Oyster Creek Nuclear Generating Station and tot 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 of fsite emergency response organizations.

1.1.3 Mobilize the emergency re sponse organizations to initiate appropriate emergency actions.

2.0 REPERENCES 2.1 OCNGS Emergency Plan

{

2.2 NUREG-0654 Rev 1, FDfA-REP-1 " Criteria for Preparation and

+ Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.3 OCNGS Emergency Plan Implementing Procedures (EPIP) 2.3.1 EPIP-1 Classification of Emergency Condition

[ 2.3.2 EPIP-2 Unusual Event i 2.3.3 EPIP-3 Alert

• 2.3.4 EPIP-5 General Emergency 3.0 RESPONSIBILITIES 3.1 The Emergency Director is re sponsible for implementing this procedure.

3.2 Emergency Director responsibilities that may NOT be delegated include:

3.2.1 Decision to notify offsite emergency management agencies.

3.2.2 Making protective action recommendations as necessary to

[ offsite emergency management agencies.

i l

l 3.2.3 Classification of Emergency Event.

l l 3.2.4 De termining the necessity for onsite accountability and/or evacuation based upon potential exposure to s

non-e ssential personnel.

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1 3.2.5 Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

4.0 PREREQUISITES 4.1 The site is in a condition that warrants Site Emergency  ;

declaration as defined by this procedure as judged by the Group '

Shift Supervisor / Emergency Director.

5.0 REQUIREMENTS 5.1 Emergency Ac tions ,,

5.1.1 The Group Shift Supervisor / Emergency Director, shall upon recognition of inplant g site conditions that have exceeded " Site Em erg ency, Emergency Ac tion Levels" EPIP-4 Attachment 1 and no emergency action level of a higher classification, ensure "Eme rg ency Director Checklis t-Site Emergency" Form EPIP-4-1 is completed.

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Sussecc . Nosewe No.

Site Emergency EPIP-4 N4e 1 af 5 seres

, 4ension No. care 3 7/21/ 8 2

~~'ACHMENT 1 SITE EMERGENCY, EMERGENCY ACTION LEVELS 1.0 EMERGENCY XCTION LEVELS INITIATING CONDITION INDICATION 1.1 Known reactor coolant system As indicated by automatic ECCS leak exceeds available makeup initiation due to either high capacity. drywell pressure or low reactor water level 1.2 Degraded core with possible Indicated by any or all of the loss of coolable geometry following alarms:

a. " Main Steam Line Hi-Hi Radiation",

Panel IF/2F, Window 4-16

b. "Off Gas Hi-Ri Radiation", Panel 10F, Window 5-5

c. "Re< ctor Water Hi-Hi Conductivity",

Panes 3F ed As confirmed by sample and analysis 1.3 Steam line break outside As indicated by any or all of the containment without following verified alarms:

isolation a. " Main Steam Valves Off Normal",

Panel 3F, Window 5-17

b. " Main Steam Tunnel High Temperature", Panel 3F, Window 5-29

c. " Ares

• Radiation Monitors", Panel 10F (Verified on 2R as Turbine Building Monitors.)

d. " Stack Gas High Radiation", Panel 10F, window 4-12 1.4 Loss of all offsite power As indicated by reactor scram and by coincident with the loss loss of offsite power and disabled l

of both diesel generators alarms received from both diesel l

for more than 15 minutes, generators neither of which energizes l

I the IC or ID 4160 Volt busses.

1.5 Ioss of all vital DC power As indicated by the following:

j for more than 15 minutes a. All batu ry voltmeters read 0 in the battery voltmeter position, Panel 8F/9F and

b. There is no light or control power available.

l

Suafoer: haceewo se,  !

Site Emergency EPIP-4 hoe 2f 5 asgos l Aensson Na, 3 7/21/82

/

ATTACHMENT 1 (cont'd)

SITE EMERGENCY, EMERGENCY ACTION LEVELS INITIATING CONDITION INDICATION 1.6 Complete loss of any As indicated by a complete loss of any function needed for plant of the following:

hot shutdown when hot a. Ability to insert control rods in shutdown is required. conjunction with failure of standby liquid control system.

b. All meand-~ to control reactor pressure (EPR, MPR, Isolation Condensers & Electromatic Relief Valves).

c. Both normal and emergency makeup water to core.

1.7 Reactor pressure exceeds Indicated by " Safety or Relief Valve 1373 PSIG Not Closed" Alarm, Display B, Panel 1F/2F, Window 4-34 and verified by: " Steam Flow Steam

{- Pressure Reco rder", Panels 5F/ 6F, indicating 1375 PSIC 1.8 Transient requiring operation Group Shif t Supervisor judges that of shutdown systems with a SCRAM setpoint has been exceeded SCRAM failure to SCRAM, no core has not occurred, a transient is in damage evident. progress and the standby liquid control system has failed.

1.9 Major damage to spent fuel Indicated by any or all of the follow-resulting in uncontrolled ing verified alarms: .

release of radioactive a. " Fuel Pool Iow Level", Panel 5F material g uncontrollable b. " Reactor Building Ventilator Ri d'ecrease in fuel pool water Radiation", Panel 10F, Window below top of spent fuel 7-23

c. " Fuel Pool Area Hi Radia tion",

Panel 10F, Window 2-18

d. " Reactor Operating Floor Hi-Radiation" Panel 10F, Window 1-9 1.10 Fire affecting the As judged by the Group Shift Supervisor function of a safety system 1.11 Sustain loss of most or all As judged by the Group Shift Supervisor annunciators coupled with I

plant transient.

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ATTACEMENT 1 (cont'd) 1, SITE EMERGENCY, EMERGENCY ACTION LEVELS B

I, INITIATING CONDITION INDICATION l 1.12 Actual or projected dose As indicated by offsite radiological 4 rate offsite exceeds 5 monitoring or dese projections.

! ar/hr whole body for 1/2 a. A projected dose rate calculation hour or 25 mr/hr exceeding 5 mr/hr whole body for

-5 to the child thyroid.

' 1/2 hour or 25 mr/hr to the child i oj; thyroid using adverse meterology 4

Actual or projected integrated and calcu1Tred effluent leak f doses offsite exceed 50 mRea rates.

1 whole body oj 250 mRea to the b. Offsite radiological monitoring child thyroid reports of greater than 5 mr/hr whole body for 1/2 hour (gaara) ac any offsite location.

c. A projected integrated dose calculation exceeding 50 mrem

, whole body or,250 mRea to l the child thyroid for the

event.

e . .

1.13 Imminent loss of physical As judged by the Gro'up Shift Supervisor j control of the plant coupled with intrusion e 1.14 Severe natural phenomena Plant is not in cold shutdown and any

being experienced or project- of the following phenomenon are being i ed with plant not in experienced or projected

! cold shutdown a. An earthquake causing major

, damage to equipment necessary i for shutdown.

[ b. Sustained hurricane or tornado

winds greater than 125 MPH

e. Flood or low water level

- affecting operation of safe shut-down equipment when required i to operate.

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L eveen , Roseews No.

Site Emergency EPIP-4 hee 4 :f 5 %ges beson No.  ::ste 3 7 /21 / 8 2 ATTACHMENT 1 (cont d)

SITE EMERGENCY, EMERGENCY ACTION LEVELS INITIATING CONDITION INDICATION 1.15 Other hazards being Plant is not in cold shutdown and any experienced or projected one of the following phenomena are with the plant not in being experienced or projected:

cold shutdown a. Aircraft crash which, in the judgement of the Group Shift Supervisor _ affects vital plant structures by impact or fire.

b. Explosion or missile damare which, in the judgement of the Group Shift Supervisor, cause s severe damage to safe shutdown equipment.

c. Entry of toxic or flammable gases into vital a reas which, in the judgement of the Group Shift Supervisor, affects operation of safe shutdown equipment.

1.16 Other plant conditions are in As judged by the Group Shife --

progress or have occurred which Supervisor / Emergency may involve actual or likely Director.

major failures of plant functions needed for protection of the public. NOTE: In exercising the judgment as to the need for declaring a Site Eme rgency ,

any uncertainty concerning the status of plant functions needed for protection of the public, the length of time the uncertainty exists, the pro spects for early resolution of ambiguities, and the potential degradation of the plant functions needed for protection of the public should be considered; i.e.,

significant uncertainty as to the reliability of plant functions for protecting the public extending beyond a reasonable time period is a sufficient basis for declaring a Site Emergency.

1 se p y = - * - -

g i

hepse Proceews No.

Site Emergency EPIP-4 N9e 5 :1 5 4 488 4evision No. Oefe 3 7 / 21 / 8 2 ATTACHMENT 1 (cont'd)

SITE EMERGENCY, EMERGENCY ACTION LEVELS I

INITIATING CONDITION INDICATION 1.17 Control Room evacuation where Control Room is . evacuated i control of the shutdown systems and control (or verifica-

is not established locally tion of all of the following j

within 15 minutes systems or equipment is not established locally within- 15

, + minutes: _

a. Emergency Condensers l s b. paactor water level l *

c. Reactor pressure

d. Reactor Temperature j

e. Drywell pressure

f. Control rods i

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Site Baergency M'[ Nga 1 sf 6 49ee __

hason No. 3

< l:ste7/21/82 i 1 i Form EPIP-4-1 EMERGENCY DIRECTOR CHECKLIST - SITE EMERGENCY INITIALS 1.0 EMERGENCY ACTIONS 1.1 The Group Shift Supervisor / Emergency Director is responsible to complete this checklist, initial each action completed or mark N/A (Not applicable).

1.2 Upon recognition of site conditions that require declaration of Site Emergency classification, the Group Shif t Supervisor shall assume the duties of Emergency Director.

Date/ Time /

1.2.1 Announce to Control Room personnel that has- assumed the duties of Emergency Director.

1.3 Assign a Communicator to make notifications to persons and sgencies listed in Form EPIP-4-2 " Notification Checklist -

Site Emergency". ,

1.3.1 Provide the communicator with the Re cord-a phone and Adas VI messages deemed appropriate.

1.4 Announce (or instruct a communicator to announce) appropriate lines ol' the following message over the Public Address System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PZRSONNEL, ATTENTION ALL PERSONNEL A SITE EMERGENCY HAS BEEN DECLARED.

l ALL ON-DUTY MEMBERS OF THE EMERGENCY RESPONSE ORGANIZATION REPORT TO EMERGENCY CENTERS. ALL OTHER PERSONNEL AWAIT FURTHER INSIRUCTIONS.

EATING, DRINKING, AND SMOKING ARE PRCHIBITED UNTIL FURTHER NOTICE.

(REPEAT THE ANNOUNCEMENT) 1.5 Immediately initiate Offsite Dose Assessment, EPIP-9.

1.6 Emergency Support Centers Activated:

( 1.6.1 Ensure the pagers of the On-Du ty Initial Emergency Response Team have been activated by Security.

i Sudtes:. Foceews %

( Site Emergency EPIP-4  % 2 *f 6 sages 8ensson % 3 :ste 7/21/82 Form EPIP-4-1 (cont'd)

EMERCENCY DIRECTOR CHECKLIST - SITE EMERCEM:Y INITIALS 1.6.2 Ensure Securi ty has unlocked and open the Emergency

, Cent ers.

l 1.6.3 Technical Support Center, EPIP-26 4

Time Operational 1.6.4 Operation Support Center, EPIP-2f-Time Operational i

1.6.5 Environmental As sessment Command Center, EPIP-3 Time Operational

, 1.6.6 Nearsite Emergency Operations Facility, EPIP-25 Time Operational 1.6.7 Farsite Emergency Operations Facf.11ty, EPIP-28 Time Operational 1.6.8 Parsippany Te chnical Functions Center, EPIP-17 i Time Operational

. 1.7 Notification Messages 1.7.1 Complete Form EPIP-4-3 "In i tial - Notification Message-Site Emergency" and give it to the communicator l for transmission.

, NOTE: New Jersey State Police are to be notified within 15 minutes after the recognition that a Emergency Action Level has been exceeded.

1.7.1.1 Ensure initial notification is received by:

New Jersey State Policy (division headquarters, communication center) and

~

Nuclear Regulat ory Commission Operations Center s

7. v y

4 .

Susect: Roceewo No.

Site Emergency EPIP-4 N4e 3 sf 6 Nges 3 " " 7 / 21 / 8 2 l l ( ~

l I Form EPIP-4-1 (cont'd) i k

EMERGENCY DIRECTOR CHECKLIST - SITE EMERGE!CY INITIALS 1.7.2 Complete Forn EP IP-4-4 "In stitute of Nuclear Power Operations and American Nuclear Insurers. Notification Message-Site Emergency" and give it to a communicator for transmission.

1.7.2.1 Ensure initial notification is received by:

Institute of NuclearPower Operations (INPO) and American Nuclear Insurers (ANI) 1.8 Followup Messages 1.8.1 Assign personnel to gather information for update message Forms EPIP-4-6 " Additional Information Message Site Emergency" and EP IP-4-5 " Bureau of Radiation Protection Station Status Checklist - Site Emergency" 1.8.1.1 Ensure additional information messages are received by the Nuclear Regulatory -

Commission Operations Ce nter at re gular interval s.

1.8.1.2 Ensure Bureau of Radiation Protection Station Status Checklist messages a re received (when requested) by the Bureau of Radiation Protection.

1.8.1.3 Provide the facility contaccc from IMPO and ANI with information requested when available and/or request assistance deemed ap propriat e.

1.8.2 Ensure ' appropriate followup a'etions 4 initiated in accordance with administrative procedure 10 6.1 Reportable Occurrence and/or '126 Procedure for Notification of Station Events.

1.9 As required, initiate (if not pre viou' sly implemented) the following procedures and ensure all appropriate notifications are completed in a timely manner by a communicator:

1.9.1 Personnel Injury, EPIP-7. Ensure notifications in 1.9.5.1 thru 1.9.5.5 are completed as appropriate.

1.9.2 Fire, EPIP-8. Ensure notifications in 1.9.5.5 thru 1.9.5.7 are completed as appropriate.

= - . .

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- _ ---_:------- - _ -- --- 1----_- ----- ------_-----_------- -----_ -_ 1__1 n n- -:_1=----

smotec= . Nessurp si Site Emergency EPIP-4 Ne , :1 , %s Mension N o. ha 3 7/21 / 8 2  ;

l.

Form EPIP-4-1 (cont 'd)

EMERGENCY DIRECER CHECKLIST - SITE EMERCE!CY INITIALS 1.9.3 Toxic / Flammable Gas Release, EP IP-15. Ensure notifications in 1.9.5 are completed as appropriate.

1.9.4 Search and Rescue, EPIP-22. Ensure ' notifications in 1.9.5.1 thru 1.9.5.6 are completed as appropriste.

p 1.9.5 Notifications and request for o f fsite assistance (as 4 required). __-_

1.9.5.1 Onsite Medical Deoartment -

Telephone , ,'

1.9.5.2 Lacey First Aid Squad / Fire Department Telephone. * -

1.9.5.3 Community Memorial Hospital Telephone , "j '

1.9.5.4 Radiation Managem t Co rpo ra,tio n, Te lephone -.

_ __/

J.9.5.5 OCNCS Security Department ,

Te lephone ,' '

1.9.5.6 Lacey Fire Department /First Aid Squad Telephone * ~- ~ c 1.9.5.7 Fire Protection Manager NOTE: Be eper activated with Initial Emergency Response Team beepers.

1.10 Initiate the following procedure s and continually monitor report s :

l 1.10.1 Emergency Radiological Survey-Onsite, EPIP-10.

l /

Date Time 1.10.2 Emergency Radiological Survey-Of fsite, EPIP-11.

/

Date Time s

9 _t

. o Q.ce:* P-ticsaro No.

Site Emergency EPIP-4 Nga 5:f 6 M::ss

%sion No. 3 Sete 7/21/82

.( '

Form EPIP-4-1 (cont 'd)

EMERCENCY DIREC':UR CHECKLIST - SITE EMERCE!CY INITIALS 1.10.3 Personnel Accountability, EPIP-12.

Dat e/ Time /

1.10.3.1 'En sure immediate notifications a re made to:

A. OCNGS Security Department via Primary : Tiark Green Phone, dial Code ._

Alternate: Tele pnone ,

B. Station Personnel via the Plant Page System per EPIP-12.

1.10.3.2 If no personnel accountability completion report is received within 30 minutes after initiation, contact Station Security for a status report.

1.10.3.3 Report of personnel accountability completion re ceived ,

personnel unaccounted for.

1.10.4 If personnel a re unaccounted for, implement Search and kescue, EPIP-22. Ensure notifications in 1.9.4 are completed. Date/ Time /

1.10.5 Site Evacuation, EP IP-13 (upon completion of personnel accountability). Dat e/ Time /

1.10.5.1 Ensure notifications in 1.10.3.1 are completed.

l P

1.11 Emergency Directors discretion, to initiate the following l procedures :

l l 1.11.4 Damage Control, EPIP-14. Da te/ Time /

1 l 1.11.5 Emergency Dosimetry, EPIP-19. Date/ Time /

1.11.6 Thyroid Blocking, EPIP-23. Da te/ Time /

1.11.7 Emergency Respiratory Eo,uipme nt , EPIP-7.

Da te/ Time /

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hereer: Ascoews No.

Site Emergency EPIP-4 s19e 6 *f 6 hgoe 4=eson No. 3 :ste 7/21/82 Form EPIP-4-1 (cont 'd)

EMERGENCY DIRECTOR CHECKLIST - CENERAL EMERGENCY INITIALS 1.12 JF emergency action levels exceed those for a Site Emergency, escalate to General Emergency classification, EPIP-5.

Dat e/ Time /

1 13 JF recovery conditions have not been met and Site Emerg ency Action Levels are no longer being exceeded, de-escalate to a 4

lower emergency classification by performing notifications in accordance with: --

i Date/ Time of reclassification /

1.13.1 Unusual Event, EPIP-2.

or i

1.13.2 Alert,-EPIP-3.

1.14 JF recovery phase conditions have been met, initiate the Recovery Phase in accordance with EPIP-29.

Det e/ Time /

1.15 J_F no further emergency actions are required, terminate the Site Emergency. Dete/ Time /

1.15.1 En sure all o f fsite agencies and GPU Nuclear personnel notified of the Site Energency receive termination notification.

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Site Emergency YPIYP . hte 1 af 2 hues lemsson .N o. 3 Care 7/21/32 , ,

I FORM EPIP-4-2' NOTIFICATION CHECKLIST - SITE EMERGENCY INITIALS Initial each item upon completion

1. With Emergency Directors approval announce appropriate lines of the following message over the Plant Page System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL A SITE EMERGENCY HAS BEEN DECLARED.

ALL ON-DUTY MD(BERS OF THE EMERGENCY RESPONSE ORGANIZATION REPORT TO EMERGENCY CENTERS. ALL OTHER PERSONNEL AWAIT FURTHER INSTRUCTIONS.

EATING, DRINKING, AND SMOKING IS PRCHIBITIED UNTIL FURTHER NOTICE.

(REPEAT THE ANNOUNCEMENT)

( 2. Notify OCNGS Security, direct them to activate. the Record-a phone and the Adas VI with the appropriate messages, activate the pagers of the Initial Emergency Response Team on duty and unlock the TSC, OSC, EACC, & NEOF. Instruct Security - to contact one member to fill each position on the Full Mobilization Emergency Duty Roster.

NOTE: The Emergency Advisor shall ensure the VP-Nuclear As suranc e , the CPU-Nuclear Board of Directors and the GPU-Reading Dispatch Control Center are notified.

Primary: Station Security / Accountability Line Dark Green Phone. Dial' Code s l Alternate: Ext'. 'd

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3. Notify the New Jersey State Police within IS minutes of l classification. Transmit " Initial Notification Message -

Site

! Emergency" EPIP-4-3 with Emergency Director approval.

Prima ry: State Hot Line (Notification Line) Gray Phone Al ternate : . g(If Primary Is Out of Service)

NOTE: IF State Police Verification Call is not received within Ee minute, re-establish contact via state Hot Line and l request verification call on the State Police l

• Verification Line immediately.

IF Al ternate Verification means is re cuN d, ins truc t i

(

State _ Police to verify

• by dialing ~ *

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Sopc: Procaeure No. -- - -

Site Emergency EPIP-4 7258 2 :f 2  %;ss Asson N o.

' 3 Care 7/21/82 i i

FORM EPIP-4-2 (cont 'd)

NOIIFICATION CHECKLIST - SITE EMERCE!CY INITIALS i 4. No tify the following agencies: Transmit " Institute of Nuclear Power Operations and Ame rican Nuclear Insu rers Notification Me ssage - Site Emerg ency" EPIP-4-4 A. Institute of Nuclear Power Operations Tel: '

B. American Nuclear Insurers Tel:

5. Notify the United States Nuclear Regulatory Commission Operations Ce nter Transmit " Initial No tification Message-Site Emergency" EPIP-4-3 Primary: NRC-ENS Line (Lif t receiver from cradle) Red Phone Al ternate: (1) Comercial via Bethesda t '

(2) Commercial via Silver Spring  !

\

(3) NRC-HPN Line - DialL_

(4) Comercial via Sachesda, q $

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

6. When requested, by the Bureau of Radiation Pro tection (BRP) transmit " Bureau of Radiation Protection Station Status Checklist

- Site Emergency" EPIP-4-5 via, the BRP Inf ormation Line located in the Emergency Command Center (Group Shif t Supervisors Office)

7. Transmit additional information messages to the Nuclear Regulatory Commission and other agencies directed by the Faergency Director using " Additional Inf ormation Message - Site Emergency" EPIP-4-6.

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FORM EPIP-4-3

• INITIAL NOTIFICATION MESSAGE - SITE EMERGENCY j MESSAGE WILL BEGIN AND END WITH:

(Circle One) THIS IS NOT AN EXERCISE - I REPEAT - THIS IS NOT AN EXERCISE QR, THIS IS A DRILL - THIS IS A DRILL THIS IS

( Name) (Title)

~~

AT OYSTER CREEK NUCLEAR GENERATING STATION THIS IS A NOTIFICATION OF A SITE EMERGENCY CLASSIFICATION THIS EVENT WAS CLASSIFIED AT ON (Time - 24 hr. clock) ( Dat e)

[ } THERE IS NO RELEASE IN PROGRESS

( ) WE HAVE A CONTROLLED RELEASE IN PROGRESS

() WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS

( ) NO PROIECTIVE ACTIONS ARE RECOMMENDED

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

() WE RECOMMEND EVACUATIO N FOR THE FOLLOWING DIRECTIONAL SECTOR (S)

EPPROVED EMERGENCY DIRECTOR DATE TIME-24 HR TIME NOTIFIED / VERIFIED THIS MESSAGE HAS BEEN TRANSMITIED TO:

/ NEW JERSEY STATE POLICE via State Hot Line (Gray Phone)

/ UNITED STATES NUCLEAR REGULATORY COMMISSION via NRC-ENS Line (Red Phone)

(DATE) (COMMUNICATOR )

NOTE: VERIFICATION OF MESSAGE IS COMPLETE ONLY AFTER RECEIVING AGENCY HAS RESTATED MESSAGE CORRECTLY IN ITS ENIIRETY BACK TO THE OYSTER CREEK COMMUNICAIOR.

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. 1 Sq.c:: Nesoure No, Site Emergency j EPIP-4 ptge 1 :f 1 8ms j l

A.nsson No. Cafe '

/ 3 7/21/82

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FORM EPIP-4-4 INSTITUTE OF NUCLEAR POWER OPERATIONS & AMERICAN NUCLEAR INSURERS NOTIFICATION MESSAGE - SITE EMERGENCY

1. This is -

at Oyster Creek

( Name/Ti tle)

Nuclear Generating Station. A Site Emergency was declared in accordance with our Emergency Plan at /

(Time) / ( Dat e )

2. Description of Emergency:

3. As sistance requested:

4. Ap proved (Dnergency Director / Emergency Support Director)

( Dat e) (Time)

Time

5. Transmitted To: Insitute of Nuclear Power ,

Operations i f'

. ., /

To: American Nuclear Insurers w -

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! (Communicato r) ( Da t e )

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Lovest: Poesswe No.

Site Emergency EPIP-4  % 1d 2 %

heson No. ere l

(~ 3 7/21/82 i l

i FORM EPIP-4-5 BUREAU OF RADIATION PROTECTION STATION STATUS CHECKLIST - SITE EMERGENCY l

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

2. Accident Classification: SITE EMERGENCY

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

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

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

6. Gaseous Release Information (a) Release Terminated: (circle one) Yes No (b) Estimated Duriation of Release: Hours (c) Type of Gaseous Release (circle one) Elevated Cround (d) Wind speed sph m/sec (e) Wind Direction: From: (0) Toward (0)

Af fected Sector: (Compass Point)-

(f) Stabilit,y Class: (circle one) Unstable Neu tral Stable (g) Release Rate Noble Gas: Ci/Sec.

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

7. Liquid Release Information (a) Release Terminated (circle one) Yes No (b) Estimated Duration of Release: Hours (c) Estimated Release Concentration uCi/cc (d) Release Rate gpm g=-p= =p -+ + - g. , , = c, ,.-me er e n=*e- - =-..e 7

, . - = = = = , ' +%= - -

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5= steer: Newe No.

Site Emergency EPIP-4 Nge 2 sf 2 anges 8ensson % :ste l l f' 3 9/21 /532 FORM EPIP-4-5 (cont'd)

8. Projected Offsite Doses (a) Whole Body Distance Miles) Dose Rate mrem /hr Time to Reach PAC (hrs.)

1.

. 2.

3.

4. --

5.

~~

(b) Child Thyroid Distance Miles) Dose Rate Rem /hr Time to Reach PAC (hrs.)

1.

2.

3.

4.

5.

9. Reconumended Protective Actions:

10. Status checklist approved for transmission to NJBRP by Emergency Director / Emergency Support Director:

(Signature) ( Dat e/ Tim e)

11. Status Checklist transmitted, to NJBRP:

Transmitted to:

( Name) . .

(OCNGS Conununicator) ( Locatio n) ( Dat e/ Time)

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Suavesc hoceew, so, Site Emergency ETIP-4 Peu 1 ef 3 Supe Mensson N& Oste 3 7/21/82

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FORM EPIP-4-6 I

i ADDITIONAL INFORMATION MESSAGE - SITE EMERCENCY

Check ( !Y ) all appropriate statements to be transmitted as inforamtion is available I

1

1. This is _

acting under the l Direction of the Emergency

( Emergency Director) t Director at Oyster Creek Nuclear Generating Station. The following is provided as additional information for the initial notification of Site Emergency.

I

2. DATE/ TIME OF CLASSIFICATION

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

b. Date: Month Dey Year j 3. Plant Status

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

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

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

core, and containment integrity is satisfactory.

l 4. Type of release (circle' one) airborne; liquid; surf ace soil.

l

5. Meteorological Data

a. Wind speed MPH

b. Wind direction ( from) (toward)

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

d. Precipitation (circle one) rain; slee t; snow l

6. Gaseous Radiological Data

( a. Noble gas release rate uCi/se c l b. Iodine 131 release race uCi/see l

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

d. Actual or estimated duration of release:

y . _;,L . . . . . , . c , . . , . . . _ , , . . _ . _ .

3

%epen haceews No.

Site Emergency EPIP-4 *tse 2 af 3 aans Menmon NA 2 ate FORM EPIP-4-6 (cont'd)

7. Liquid Radiological Data

a. Release concentration uCi/cc

b. Release rate uCi/sec

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

d. Actual or estimated duration of release

e. Es timated total rsle.tse uCi

8. 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 ar/hr mrem

c. 5 miles ar/hr mrem

d. 10 miles ar/hr mrem

9. Projected Iodine Concentration and Integrated Dose Commitment

(' '

(Based od 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

10. Es timate of Surface contamination dpm/100 cm2 (obtain from field date) mrem /h r

11. Emergency Actions in progess:

a. Radiological survey teams. onsite

b. Radiological survey teams of fsite

c. Onsite fire brigade

d. Offsite fire department

e. Damage Control

f. First aid teams onsite

g. Ambulance service

h. Medical support

i. Environmental surveys offsite

j. Other, specify

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j Susseer. Noceewe No, j j Site Emergency EPIP-4 59e 3 :f 3 Mges

! 4evisson No. Oate 3 7/21/82 2

FORM EPIP-4-6 (cont'd)

12. Additional support required (specify)

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

14. Offsite population s ector( s ) (refer to Emergency Planning Zone Sector map) affected are ,

9 9 9

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

a. None

b. Notify (projected offsite dose )

c. Take shelter (projected offsite dose )

d. Evacuate (projected offsite dose )

16. Approved

{ m. (Emergency Director / Emergency Support Director)

( Da t e) ( Time)

17. Transmitted To: TIME: NOTIFIED / VERIFIED,

a. United States Nuclear Regulatory ,

Consnis sion. /

b. New Jersey Bureau of Radiation Protection. /

c. /

d. /

(Consnunicator) ( Dat e)

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- Precedure No,

@ Jersey Central am , $'

2/23/81 p

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<s/13/o23 s/23/s2 .

(~ Power & Light Company Revision No. Cate 3 /82 I Suoject General Emergency ,

! Autncnzac By Director-Station Operations k

\ NA/d -

Oyster Creek Nuclear Gener Station

v .

t LIST OF EFFECTIVE PAGES DATE REVISION NUMBER  !

~

1 7/ 21/82 3

• i 2 7/21/82 3

) 3 7/ 21 /8 2 3 i

ATTACHMENTS Attachasut 1 (2 pages) 7 / 21 / 8 2- 3

^

Form EPIP-5-1 (5 pages) 7/ 21/82 3

Form EPIP-5-2 (2 pages) 7/21 / 8 2 3 Form EPIP-5-3 (1 page) 7/ 21/82 3 Form EPIP-5-4 (1 page) 7/21/8 2 3 Form EPIP-5-5 (2 pages) 7/ 21/8 2 3 Form EPIP-5-6 (3 pages) 7 /21 / 8 2 3 N O N - C O N T R~O L L E D This Document Will Not Be Kept Up, To Date I -

i

basese: Mesewo ae, _

General Emergency EPIP-5 4 ge ; of 3 sites 3 7/21/S2 g

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

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

1.1.2 Ensure necessary actions are taken to notify o f fsite emergency response organizations.

l 1.1.3 Mobilize the emergency response organizatrons to initiate appropriate emergency actions.

2.0 REFERENCES

2.1 OCNGS Emergency Plan i 22 NUREG-0654 Re v. 1, FEMA-REP-1, " Criteria for Preparation and l Evaluation of Radiological Emergency Response Plans and Preparedness l in Support of Nuclear Power Plants."

2.3 OCNGS Emergency Plan Implementing Procedures (EPIP) 2.3.1 EPIP-1 Classification of Emergency Conditions 2.3.2 EPIP-2 Unusual Event 2.3.3 EPIP-3 Alert 2.3.4 EPIP-4 Site Emergency 3.0 RESPONSIBILITIES 3.1 The Emergency Director is responsible for implementing this procedure.

3.2 Bnergency Director responsibilities that may N0! be delegated include:

3.2.1 Decision to notify offsite emergency management agencies.

3.2.2 Making proteqtive action recommendations as necessary to of fsite emergency management agencies.

3.2.3 Classification of Emergency Event.

3.2.4 Determining the necessity for onsite accountability and/or evacuation based upon potential exposure to non-essential personnel.

( 3.2.5 Authorization for emergency wo; .ers to exceed 10 CFR 20 l i

radiation exposure limits.

__~LL : _: . - - _ _

'~ ' - ~

Suavosn Roseawe se, GENERAL EMERGENCY 'P TP -9  % 1 8f 1 D 4evison No, Oate 3 7/21/82 4.0 PREREQUISITES 4.1 The Site is in a condition that warrants General Emgergency declaration as defined by this procedure as judged by the Group Shif t Supervisor / Emergency Director.

5.0 REQUIRENENTS 5.1 Emergency Actions 5.1.1 The Group Shif t Supervisor / Emergency Director, shall upon

~

recognition of inplant or site conditioiis that have exceeded "Ge neral Emergency, Emergency Action Levels" EPIP-5 Attachment 1, ensure " Emergency Director Checklis t-General Emergency " Form EPIP-5-1 is completed.

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f General Emergency IFYN5" , I d 2 i heson No. 3 :sta 7/21/82

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ATTACHMENT 1 CENERAL EMERGENCY - EMERGENCY ACTION LEVEI.S 1.0 Emergency Action Levels INITIATING CONDITION INDICATION 1.1 Actual or projected As indicated by any one of the following:

dose rate offsite a. A projected dose rate calculation exceeds 50 ar/hr exceeding 50 mr/hr whole body og j whole body or 250 mr/hr to the child thyroid l 250 ar/hr to the using actuarineterology and child thyroid calculated effluent leak races.

or b. Offsite'radiclogical monitoring Actual or projected reports of greater than 50 mr/hr

integrated doses offsite (ganssa) at any offsite location.

exceed 100 mrem whole c. A projected integrated dose l body or 500 mRam calculated exceeding 100 mRam to th Tchild thyroid whole body or 500 mrem to the child thyroid for the evert 1

1.2 Loss of 2 of 3 fission As judged by the Group Shif t Supervisor product barriers with a ,

from plant indications that 2 of 3 s potential loss of the fission product barriers (fuel cladding, third reactor coolant boundary, primary con-tainment) have failed and there is a high potential for loss of the third.

1.3 Ioss of physical control As judged by the Group Shift Supervisor of the planti with intrusion in progres s.

1.4 Other plant conditions are As judged by the Group Shif t Supervisor /

in progress or have occurred Emergency Director which may involve actual or a. Loss of coolant accident with insainent substantial core containment failure affecting the degradation or melting, with long term success of the ECCS.

potential for loss of contain- Core Degradation or melt in several ment integrity, or may maks hours without containment boundary.

release of significant b. Ioss of coolant accident with amounts of radioactivity failure of ECCS to perform lending in a short time possible. to core melt degradation in minutes to hours. Loss of containment may be imminent.

c. Transient occurs plus failure of requisite core shutdown systems could lead to core melt in several hours with containment failure likely.

\_

, . ~ __ _. . ___ . .

z. . m ,,_ .

W heceews No. ~

General Emergency EPIP-5 Moe 2 :f 2  %,ee sensson N o. 0*

3 7/ 21 / 8 2 l'

ATTACHMENT 1 (conc'd)

GENERAL EMERGENCY - EMERGENCY ACTION LEVELS

d. Shutdown occurs but decay heat removal capability is lost. Core degradation or melt could occur in ten hours with subsequent containment failure.

NOTE: In exercising the judgement as to the need for declaring a General Emergency, any uncertEnty concerning the potential for large releases of radioactive material, the length of time the uncertainty exists, and the prospects for the early rese'.ution of ambiguities should be considered, i.e. significant uncertainty as to the potential for large releases of radioactive material extending beyond a reasonable

__ time period is a sufficient basis for declaring a General Emergency.

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General Emergency **'8?p'.5"' 1 5 g

4ewsson No. 3 :ste 7/21/82 i

( l Form EPIP-5-1 ENERGENCY DIRECTOR CHECKLIST

• C.lERAL EMERGENCY INITIALS 1.0 EMERGENCY ACTIONS 1.1 The Group Shift Supervisor / Emergency Director is responsible to complete this checklist, initial each action completed or mark N/A (Not applicable).

1.2 Upon recognition of site conditions that- requires declaration of General Emergency Classification, the Group Shift Supervisor shall assume the duties of the Emergency Director.

Date/ Time /

1.2.1 Announce to Control Room . personnel that has assumed the duties of Emergency Director.

1.3 Assign a Communicator to make notifications to persons and agencies listed in Form EPIP-5-2 " Notification Checklist -

, General Emergency".

\

1.3.1 Provide the communicator with the Record-a phone and Adas VI messages deemed appropriate.

1.4 Announce (or instruct a communicator to announce) appropriate lines of the following message. over the Public Address System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL A GENERAL EMERGENCY HAS BEEN DECLARED.

ALL ON-DUTY MEMBERS OF THE EMERGENCY RESPONSE ORGANIZATION REPORI TO EMERGENCY JENTERS.

ALL OTHER PERSONNEL AWAIT FURTHiR INSTRUCTIONS.

EATING, DRINKING, AND SMOKING IS PROHIBITED UNTIL FURTHER NOTICE.

(REPEAT THE ANNOUNCEMENT) 1.5 Immediately initiate Offsite Dose Assessment, EP IP-9.

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Sustest: Nesouro No.

General Emergency EPIP-5 59e 2 Of 5 Nges .

1 hweson N o. :are i 3 7/21/82 '

/

l 1

Form EPIP-5-1 (cont'd)

EMERGENCY DIRECTOR CHECKLIST - GENERAL EMERCEFEY INITIALS 1.6 Emergency Support Centers Activated:

1.6.1 Ensure the pagers of the On-Ducy Initial Emergency Response Team have been activated by Security.

1.6.2 Ensure Security has unlocked and open the Emergency Ce nters.

1.6.3 Technical Support Center, EPIP-26 Time Operational 1.6.4 Operacion Support Center, EPIP-27 l Time Operational  !

1.6.5 Environmental Assessment Command Center, EPIP-31 Time Operational 1.6.6 Nearsite Emergency Operations Facility, EPIP-25 Time Operational 1.6.7 Farsite Emergency Operations Facility, EPIP-28 Time Operational l

l 1.6.8 Parsippany Technical Functions Center, EPIP-17 Time Operational l

1.7 Notification Messages 1.7.1 Complete Form EPIP-5-3 " Initial No tification Message-General Emergency" and give it to a communicator for transmission.

l NorE: New Jersey State Police are to be notifed within 15 minutes after the recongnition that a Emergency Action Level has been exceeded.

1.7.1.1 Ensure initial notification is received by:

l New Jersey State Police (division headquarters, communication center) and Nuclear Regulator Commission Operations Ce nter.

( 1.7.2 Complete Form EPIP-5-4 "Institue of Nuclear Power Operations and American Nuclear Insurers, Notification Message - General Eme rgenc y" and give it to a communicator for transmission.

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General Emergency EPIP-5 %ge 3 ef 5 Me:r

""*"N"' 3 Ocre 7/21/82 Form EPIP-5-1 (cont 'd)

EMERGENCY DIRECTOR CHECKLIST - GENERAL EMERGENCY l INITIALS '

l.7.2.1 Ensure initial notification is received by:

l Institute of Nuclear Power Operations (INPO) and American Nuclear Insurers (ANI) 1.8 Followup Messages 1.8.1 Assign personnel to gather in7ormation for update taessage Forms EPIP-5-6 " Additional Information Message - General Emergency and EPIP-5-5 " Bureau of Radiation Pro;:ection Station Status Checklist -

l General Emergency" l.8.1.1 Ensure additional information messages are received by the Nuclear Regulatory Conunission Operations Ce nter at regular intervals.

1.8.1.2 Ensure Bureau of Radiation ' Protection Station Status Checklist messages are received (when requested) by the Bureau of Radiation Protection.

1.8.1.3 Provide the facility contacts from INPO and ANI with information requested when available and/or request assistance deemed ap propriat e. l 1.8.2 Ensure appropriate followup actions are initiated in accordance with administrative Procedures 106.1 Reportable Occurrence and/or 126 Pro cedure for Notification of Station Events.

1.9 As required, initiate (if not previously implemented) the following procedures and ensure all appropriate notifications are completed in a timely manner by a communicator:

1.9.1 Personnel Injury EPIP-7. Ensure notifications in 1.9.5.1 thru 1.9.5.5 are completed as appropriate.

1.9.2 Fire EPIP-8. Ensure notifications in 1.9.5 5 thru 1.9.5.7 are completed as appropriate.

1.9.3 Toxic / Flammable Gas Release EPIP-15. Ensure notifications in 1.9.5 are completed as appropriate.

\

1.9.4 Search and Rescue EPIP-22. Ensure notifications in 1.'9.5.1 thru 1.9.5.6 are completr.d as appropriate.

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Sustec:' 7-sescuro No.

General Emergency EPIP-5 .= qa 4 af 5 % ss

%::en N o. 3 2are7/21/82 5

Form EPIP-5-1 (cont 'd)

EMERGENCY DIRECTOR CHECKLIST - GENERAL EMERCE!CY INITIALS 1.9.5 Notifications and request for offsite assistance (a s required).

1.9.5.1 onsite Medical Department Telephone _ -

1.9.5.2 Lacey First Aid Squad / Fire Department Telephone {

1.9.5.3 Community Memorial Hospital Telephone ,

1.9.5.4 Radiaiton Management Corporation Telephone _ -

1.9.5.5 oCNGS Security Department -

Te lephone '

y 1.9.5.6 Lacey Fire Department /First Aid Squad

. Telephone . - ~ /-

1.9.5.7 Fire Protection Manager NOTE: Beeper activated with Initial Emergency Response Team beepers.

1.10 Initiate the following procedures and continually monitor report s :

1.10.1 Emergency Radiological Survey - Onsite, EPIP-10

/

Date Time 1.10.2 Emergency Radiological Survey - Of fsite, EPIP-11

/

Date Time 1.10.3 Site Evacuation, EPIP-13 /

Da te Time 1.10.3.1 Ensure immediate notifications are made to:

A. OCNCS Security Department via Primary: Dark Green Phone , dial Code , g Alternate: Telephone g ~~ / Q B. Station Personnel via the Plant Pag e

\ System per EPIP-13.

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u a f &> r%:coowe No.

General Emergency EPTp.5 %se s :f 5 Mces

, Revision No. Oate' 3 7/21/92  ;

4 Form EPIP-5-1 (cont 'd)

) EMERGENCY DIRECTOR CHECKLIST - GENERAL EMERCENCY i

INITIALS ,

1.10.3.2 If no personnel accountability completion report is received within 30 minutes after initiation of site evacuation contact Station Security for a status report.

1.10.3.3 Re port of personnel accountability received, personnel unaccounted for.

1.10.4 If personnel are unaccounted for, implement Search and Rescue, EPIP-22. Ensure notifications in 1.9.4 are completed. Dste/ Time /

1.11 Emergency Director discretion, to initiate the following procedures:

1.11.1 Damage Control, EPIP-14. Da te/ Time /

1.11.2 Emergency ITosimetry, EPIP-19. Date/ Time /

1.11.3 Thyroid Blocking, EPIP-23. Date/ Time /

1.11.4 Eme rgency Re spiratory Equipment, EPIP-2.

Da te/ Time /

1.12 IF recovery conditions have not been met and General l Eergency, Emergency Action Levels are no longer being exceeded, de-escalate 'to a lower emergency classification by ,

performing notifications in accordance with:

Date/ Time of reclassification /

1.12.1 Unusual Event, EPIP-2.

or 1.12.2 AlerE EPIP-3.

or 1.12.3 Site Emergency, EPIP-4.

1.13 g recovery phase conditions have been met, initiate the Recovery Phase in accordance with EPIP-29.

Date/ Time /

1.14 H no further emergency actions are required, terminate the General Emergency. Date/ Time /

1.14.1 Ensure all o f fsite agencies and GPU Nuclear personnel notified of the General Eme rgency receive termination notification.

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n General Emergency EII5  % 1 g 2 hnsson No. 3 :ste 7/21/82 (i

l FORM EPIP-5-2 NOTIFICATION CHECKLIST - GENERAL EMERGE?EY INITIALS Initial each item upon completion

1. With Energency Directors approval announce appropriate lines of

, the following message over the Plant Page System:

Sound the " STATION ALERT ALARM" for 10 seconds.

ATTENTION ALL PERSONNEL, ATIENTION AL_L_ PERSONNEL

, A GENERAL EMERGENCY HAS BEEN DECLARED.

ALL ON-DUTY MEMBERS OF THE EMERGENCY RESPONSE ORGANIZATION REPORI TO EMERGENCY CENTERS.

ALL OTHER PERSONNEL AWAIT FURTHER INSTRUCTIONS.

EATING, DRINKING, AND SMOKING IS PROHIBITED UNTIL FURIMER NOTICE.

(REPEAT THE ANNOUNCEMENT)

2. No tify OCNCS Se curity and direct them to activate the Record-a-phone and Adas VI with the ap propria te messages, activate the pagers of the Initial Emergency Response T*am on duty and unlock the TSC, OSC, EACC, & NEOF. Ins truct Securit y to contact one member to fill each position on the Full Mobilization Emergency Duty Roster.

NarE: The Emerg ency Advisor shall ensure the VP-Nu clear Assurance, the CPU-Nuclear Board of Directors and the GPU-Reading Dispatch Control Center are notified.

Prima ry: Station Security / Accountability Line Dark Gra-a Dhane. Dial Code' ,'~j l

Alternate: Ext.- ' ~

3. Notify the New Jersey State Police within 15 minutes of t classification. Transmit " Initial Notification Message -

General Emergency" EPIP-5-3 with Emergency Director approval.

i Prima ry: State Hot Lin (Notification Line) Gray Phone Al terna te: _ ', Uf Primary Is Out of Service)

-A

. NOTE: IF State Police Verifica tion Call is not received Ethin one minute, re-establish contact via state Ho t Line and request verification call on the State Police l Verification Line im:: ediately.

IF Alternate Verification means is recuired instruct State Police to. ,verify by dialing _ ,

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Lepc:: 7* cacure No.

General Emergency EPIP-5 g,2 2 H

%: en N o. 3 Octe 7/21/82

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FORM EPIP-5-2 (cont'd) i NOTIFICATION CHECKLIST - CENERAL EMERCE?CY i INITIALS

4. Notify the Ocean County Sheriff Communication Center, Toms River. Transmit " Initial Notification Message -

General Emergency" EPIP-5-3 Primary : Ocean County Ho t Line Alternate: Station Security and Accountability Line Dial Code

5. Notify Lacey Township Po lice DepartmenE Transmit "Init al Notification Message - General Emergency" EPIP-5-3 ,

Primary:

• Alternate:

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6. Notify the following agencies: Transmit " Institute of Nuclear Power Operations and Ame rican Nuclear Insurers No tifica tion Message - General Emergency" EPIP-5-4 A. Institute of Nuclear Power Operations Tel: -

B. American Nuclear, Insurers Tel: _

y'

7. Notify the United States Nuclear Regulatory Commission Operations Center Transmit " Initial No tification Message-Ceneral Emergency" EPIP-5-3

' Prima ry: NRC-ENS Line (Lift receiver from cradle) Red Phone

~ ~ ' ~ ~ ~ " ~ ~ ~

Alternate: (1) Commeicial via Bethesda (

(2) Commercial via Silver Spri

~ * (3) NRC-HPN Line - Diali_ i (4) Commercial via Be thes~da (

~-

NorE: Open-ling communication with NRC is to be maintanined on ENS Line throughout the emergency situation.

8. When requested, by the Bureau of Radiation Protection (BRP) transmit " Bureau of Radiation Protection Station Status Checklist -

General Eme rgenc y" EPIP-5-5 via, the BRP Information Line located in the Emergency Command Center (Group Shift Supervisors Office)

9. Transmit additional inf ormation messages to the Nuclear Regulatory Commission and other agencies directed by the Emergency Dire ctor using " Additional Information Message -

General Emergency" EPIP-5-6.

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General Emergency EPIP-5 h4e I of I Nges )

Monsson NA Cote j 3

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FORM EPIP-5-3 INITIAL NOTIFICATION MESSAGE - GENERAL EMERGENCY MESSAGE WILL BEGIN AND END WITH:

(CIRCLE ONE) THIS IS NOT AN EXERCISE - I REPEAT - THIS IS NOT AN EXERCISE 9.R.

THIS IS A DRILL - THIS IS A DRILL

~~

THIS IS

( Name) (Ti tle )

AT OYSTER CREEK NUCLEAR CENERATING STATION _ , _

THIS IS A NOTIFICATION OF AN GENERAL EMERGENCY CLASSIFICATION 9

THIS EVENT WAS CLASSIFIED AT ON (Time - 24 hr. clock) ( Date)

[ ] THERE IS NO RELEASE IN PROGRESS

( ] WE HAVE A CONTROLLED RELEASE IN PROGRESS

[ ] WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS k [ ] NO PROTECTIVE ACTIONS ARE RECOMMENDED

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

[ ] WE RECOMMEND EVACUATION FOR THE '

FOLLOWING DIRECTIONAL SECTUR(S) _

AP PROVED EMERGENCY DIRECTOR DATE TIME-24 HR TIME NOTIFIED / VERIFIED THIS MESSAGE HAS BEEN TRANSMITTED TO:

/ NEW JERSEY STATE POLICE via State Hot Line (Gra y Phone)

/ UNITED STATES NUCLEAR REGULATORY COMMISSION via NRC-ENS Line (Red Phone)

~

/ OCEAN COUNTY SHERIFF COMMUNICATION via Ocean County Hot Line (Light Green Phone)

~~

/ LACEY TOWNSHIP PCI. ICE DEPARTMENT via s .

.._.s',,

(DATE) (CO.*UNICATOR)

NarE: VERI FICATIO N OF MESSAGE IS COMPLETE ONLY AFTER RECEIVING AGENCY HAS RESTATED MESSAGE CORRECTLY IN ITS ENTIRETY BACK TO THE CYSTER CREEK COMMUNICAIOR

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"*7-

Miec=' ' p.scacuro No.

General Emergency EPIP-5 M4e 1 af 1 %s Momsson s o. Dase 3 7/21/82  ;

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4 FORM EPIP-5-4 INSTITUTE OF NUCLEAR POWER OPERATIONS & AMERICAN NUCLEAR INSURERS NOTIFICATION MESSAGE - GENERAL EMERGENCY

1. This is at Oyster Creek (Name/Ti tie)

Nuclear Generating Station. A General Emergency was declared in -

~~

accordance with our Emergency Plan at / _

(Time) / (Date)

2. Description of Emergency:

(

3. Assistance requested:

4. Approved (Emergency Director / Emergency Support Director)

(Date) (Time)

Time

5. Transmitted To: Institute of Nuclear Power ,

Operations D

To: American Nuclear. Insurers ,

A

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(Communicaeor) (Date)

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f General Emergency EPIP-5 Moe 1 :f 2 Nges 3 " 7/21/82 ,

FORM EPIP-5-5 BURZAU OF RADIATION PROTECTION STATION "TATUS CHECKLIST - ALERT i 1. Date and Time of Incident: Date: Time: (24-Hr. Clock) i 2. Accident Classification: GENERAL EMCRGENCY l 3. Type of Release:(circle one) GASEOUS LIQUID i

~~

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

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

6. Caseous Release Information (a) Release Terminated: (circle one) Yes No (b) Estimated Duration of Release: Hours f (c) Type of Gastous Release (circle one)

Elevated Ground

{ (d) Windspeed mph m/sec

(e) Wind Direction

From: (0) Toward (0) i Affected Sector: (Compass Point)

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

i (h) Release Rate Iodine (if known) C1/Sec.

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

(

Susiesr. ' haceewo sa General Emergency EPIP-5  % 2 :f 2 Sct;se 4evision .N o.  ::ste

(

FORM EPIP-5-5 (cont 'd)

8. Projected Offsite Doses (a) Whole Body Distance Miles) Dose Rate mrem /hr Time to Reach PAG (hrs. )

1.

2.

3.

4.

5.

~

(b) Child Thyroid Distance Niles) Do se Ra te Rem /h r Time to Reach PAG (hrs. )

1.

2.

3.

4.

5.

9. Recommended Protective Actions:

i.

l

10. Status Che cklis t approved for transmission to NJB RP by Emerg ency Director / Emergency Support Director:

( Signature) ( Dat e / Time)

11. Status Checklist transmitted to NJBRP:

Transm'itted to:

(Name)

/

(OCNGS Communicator) (Location) ( Dat e / Time) e S

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4

%oveerf ' Ncsewo No.

General Emergency EPIP-5 h98 1 :f 3 %ges 3

• 7/ 21 /8 2

(

FORM EPIP-5-6 ADDITIONAL INFORMATION MESSAGE - GENERAL EMERGENCY Check (/) all appropriate statements to be transmitted as infomation is available

1. This is acting under the

~

Direction of the E.sergency (Emergency Director)

Director at Oyster Cre ek Nuclear Generating Station. The following is provided as additional information for the initial notification of General Emergency.

2. DATE/ TIME OF CLASSIFICATION

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

b. Date: Mmth Day Year

3. Plant Status

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

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

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

4. Type of release (circle one) airborne; liquid; surface soil.

5. Meteorological Data

a. Wind speed MPH

b. Wind direction ( from) (towa rd)

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

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

6. Gaseous Radiological Data

a. Noble gas release rate uCi/see

b. Iodine 131 release race uCi/s ec

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

d. Actual or estimated duration of release:

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Lovest: Noceewe No, General Emergency EPIP-5 8t te 7 of 3 8eges hnsson No. ste

, 3 7 / 21 / 8 2  ;

e FORM EPIP-5-6 (cont'd)

7. Liquid Radiological Data

a. Release concentration uCi/cc

b. Release rate uCi/sec

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

d. Actual or estimated duration of release

e. Estimated total release uCi

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

Whole Body

a. Site Boundary ar/hr mrem

b. 2 miles ar/hr mrem

, c. 5 miles ar/hr mrem

d. 10 miles ar/hr mPam

9. Pro jected Iodina Co ncentration and Integrated Dose Connitment (Based on actual or projected duratio'n of release).

THYROID

a. Site Boundary aci/cc mrem

b. 2 miles uC1/cc mrem

~ '

c. 5 miles uCi/c c mrem

d. 10 miles uCi/cc mrem

10. Estimats of Surface contamination dpm/100 cm (obtain from field date) mRam/h r

11. Emergency Actions in progess:

a. Radiological survey teams onsite

b. Radiological survey teams of fsite

c. Onsite fire brigade

d. Of fsite fire department

e. Damage Control

f. First aid teams onsite

g. Ambulance service

h. Medical support

1. Environmental surveys offsite t J. Other, specify P * * * -wav * -=v -e a w g e -.

Gnoca hocsows No.

General Emergency EPIP-s *198 1 f 3 SmM8 4enman N4 Octe l

-. 3 7 / 21 / 8 2 l t

i FORM EPIP-5-6 (cont'd)

12. Additional support required (specify)

13. The condition may change to an (circle one) Unusual Event; Alert; Site Energency t 14. Of fsite population sector (s) (re fer to Emerg ency Planning

}

j Zone Sector map) affected are ,

I

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

I

a. None

b. Notify (projected offsite dose )

c. Take shelter (projected of fsite dose )

d. Evacuate (projected offsite dose )

16. Approved (anergency Director / Emergency Support Director) i L ( Dat e) (Time) f

17. Transmitted To: TIKE: NOTIFIED / VERIFIED.

r

[ a. United States Nuclear Regulatory -

r Commission. /

y b. New Jersey Bureau of Radiation (Y Pro tection. /

( c. /

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d. /

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(Communicator) ( Dat e) l'

),

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,__._________:______-. , ,